rev 0 to jpn-psl-seip-96-067, "engineering evaluation
TRANSCRIPT
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i ST. LUCIE UNIT 14 .
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ENGINEERING EVALUATION,
I IMPACT OF PAST INCORRECT CALIBRATION, OF THE S/G LEVEL TRANSMITTERS-
' ON THE LOW S/G LEVEL TRIPSETPOINTS FOR RPS
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JPN PSL-SEIP-96-067,
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REVISION O,
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! SAFETY RELATEDi
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FLORIDA POWER & LIGHT COMPANYJUNO BEACH, FLORIDA
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g Jy40;gjj7'97o32sBINDER 96-48s PDR
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...-PS*.-SEIP-96-067*'' Revision O
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REVIEW AND APPROV5ENCORD~ ~ -
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F1.AMT St Lucie Plant UNITS 1
TITLE Imoact of Past Incorrect Calibration of the S/G Level Transmitters
on the Low S/G Level Trio Setootnt f or ItPS
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LEAD DISCIPLINE PSL PEG IGC ENGINTERING _
|EwGINEERIwG ORGANI1ATIOw FPL - IGC ENGINEERING i
REVIEW / APPROVAL
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OROUP INTERFACE TYPE PREPARED VERIFIED APPROVED FPLAPPROVED *
Iaput Rerww NA
unca w/A N/A w/A w/A w/Al
EIacT w/A w/A w/A w/A w/A
gj gM6 ggs ;, w/AIsc LsAD
CIVIL w/A w/t w/A h/ A' " w/A
wuc rEs w/A w/A w/A~
)EsI w/A N/A w/A D/A w/A
wuc rEs w/A w/A C - Q w/A>
FUEL fJ/h -
STAFF w/A N/A w/A'
N3 w/A
* For Contractor Ivals as determined by ProjectsReview Interface as a min on all 10 CFR 50.59 Evals and PLAs**
TPL PROJECTS APPROVAL: DATE: 22/94
OTHER INTEAFACES:
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. F x u .m
ru> wt.= m s?
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JPN-PSL-5El?-vb-LulRevicien o* *
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TABfI OF CONTENTS .__ _ . . _ _ _ _ .
SECTION TITLE PAGE
Cover Sheet 1
Review and Approval Record 2
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Table of Contents 3" .
1.0 Purpose and Scope 4.
2.0 Safety Classification 4 -
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3.0 Evaluation 4
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4.0 Verification Summary 6
5.0 Conclusions 6i
6.0 References 7
ATTACHMENTS :
1. Error Determination (6 pages);
2. Uncertainty Analysis (1 pages)
3. Error Analysis (4 pages)
4 S/G ' Hot' Dimensions (2 pages)|
5. Reactor Protection System Monthly Functional Test Completed Data (1 page)
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1.0 PURPOSE AND SCOPE*
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The purpose of this evaluation is to assess the past impact from the incorrect calibration ofthe Unit 1 S/G level tnnsmitters on the low S/G level trip setpoint for RPS. 'Iheevaluation will determine the magnitude and direction of the past error introduced, and therelative impact on the Tech. Specs. and/or analytical limit for the following' transmitters.
Tar No. Function
LT-9013A,B,C,D RPSLT-9023A,B,C,D RPS
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2.0 SAFE'IY CLASSIFICATION
This engineering evaluation involves the review and evaluation of instrumentation requiredfor the safe operation of the plant, including the Reactor Protection System (RPS). Sincethe RPS is designed to mitigate the consequences of design basis accidents, this evaluationhas been classified as Safety Related.
3.0 EVALUATION
3.1 Error Determination
'Ihe determination of the error for the past calibration of the S/G level transmitters isbased on the methodology and data from FPL calculation PSL-1FJI-93-013 (Ref.1). Inaddition, downcomer density effects are also included consistent with the original CEcalculation (Ref. 3). Attachment 1 provides a summary of the input data, formulas, andresults along with a sample calculation.
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For the purpose of this evaluation operating / reference plant conditions were based onoperation at 850 psia, consistent with the CE Calculation. The downcomer density effectis also included based on the CE Calculation which maintains consistency with the originalmethodology and has no adverse effect on the evaluation. S/G thermal growth was not |
considered since excluding it produces conservative results in that additional S/G volumewould be present, but not taken credit for. ' Itis again maintains consistency with the |
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original methodology in order to provide a consistent reference for the comparison of theresults. S/G dimensions, however, were based on the S/G as built drawings, while thecondensate pot heights were based on Plant walkdowns per the FPL Calculation (Ref.1).'Ihis overall approach addresses the mconsistencies encountered during the preparation ofthe FPL Calculation, while maintaining a consistent, yet acceptable methodology indetermining the error of the existing transmitter calibrations. j
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Other parameters, such as a reference leg temperature of Ill'F (Ref. 6), were based onmore representative Plant conditions so as to not build to much conservatism into themsults, since the results will be used to assess plant operability in the past, not~ operationin the future.
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JPN-PSL-SEIP-96-067*
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3,2 14op Uncertainty Analysis~-
the Total Loop Uncertain [(TLU) determination for the SIG level- . . _ _ -
Attachment 2 provitransmitter and bistable for the S/G low level RPS trip function. The TLU in combinationwith the calibration error determined in section 3.1 provides the necessary data todetermine if the S/G low level protection function may have been outside the TechnicalSpecifications and/or analytical limit. Since the setpoint of interest is S/G low level and isa decreasing setpoint, the SRSS Single Sided Approach will be applied (Ref.10).
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The TLU determination was prepared in accordance with FPL Standard No. IC-3.17 (Ref.
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3.3 EaTor AnalysisI
The Error Analysis, included as Attachment 3', evaluates the effect of the calibration error {
and Total Loop Uncertainty (Transmitter / Bistable) in combination with the auctioneered i'
S/G level transmitter input on the current Plant setpoint of 21% S/G level.
The use of the current Plant setpoint for the analysis is acceptable based on sample dataobtained from QA records for " COMPLETED' monthly functional tests of the ReactorProtection System S/G low level bistables. De data, included as Attachment 5,documents the as-found settings for 11 months of Technical Specification monthlyfunctional tests in accordance with Plant procedure 1-1400050. Based on the functionaltest data, the RPS bistables were always within the tolerance specifications of the
!procedure for all 4 channels for each steam generator. However, the least conservativevalue (-1.830 volts) of any channel documented during the surveillance periods reviewedwould have yielded a setpoint of 20.75%. His deviation would normally be attributed toinstiument drift, accuracy, setting tolerance, and/or M&TE cffects which have beenaccounted for in the error analysis. Therefore, use of the nominal setpoint in lieu of amore conservative value such as the Technical Specification Allowable Value is acceptablebased on the data presented.
ne Error Analysis treats the calibration error as a bias, with magnitude and direction, ,
about the 21% S/G level setpoint, ne magnitude and direction of the calibration error i
has been determined in Attachment I and is presented as the % level deviation from truelevel to the indicated level when true level is 21 %. Total 1. cop Uncertainty is thenapplied to the indicated level to establish an uncertainty band. The S/G level transmitterinputs are paired by S/G channel (i.e., LT-9013A,9023A; LT-9013B, 9023B; etc.), thenauctioneered (low select) by the S/G level channel. His ensures that the. lowest of eachof the channel pairs is selected as the bistable input for that channel of the logic matrix.
. De Error Analysis (Attachment 3) documents the worst case auctioneered level for each;'
channel pair and ultimately whether the trip function may have occurred outside theTechnical Specifications and/or the analytical limit.
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4.0 VERIFICATION SUMMARY |
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This engineering evaluation identifies an error in Ae past calibration of the S/G level - ~~
transmitters for Unit 1. ne impact of this error on the RPS setpoints has been evaluatedfor the subject instruments.
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This engineering evaluation was reviewed to ensure that the overall conclusions met I'
applicable requirements. De criteria and design inputs required to evaluate the resultswere adequately described, reasonable, and appropriately identified for subsequentreverification.
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De rationale provided in assigning the safety classification for this evaluation was I~
verified. His engineering evaluation has been correctly specified as Safety Related. I
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5.0 CONCLUSIONS1
ne FS AR (Ref. 7) specifies an analytical limit of 17.5 % for the low S/G level RPS trip.'
The results of the Error Analysis calculated in Attachment 3 are summarized in thefollowing table.
Table 5-1
RPS Channel A B C D
Transmitters LT-9013A/ LT-9013B/ LT-9013C/ LT-9013D/
(SG 1 A/SG IB) LT-9023A . LT-9023B LT-9023C LT-9023D |1
Calculated Trip 17.2 % 17.9 % 17.8 % 17.5 %
(Attachment 3)
Analytical limit 17.5 % 17.5 % 17.5 % 17.5 %
ne RPS logic for low S/G level uses a 2-out-of-4 trip logic. The S/G level inputs are |
paired by channel then auctioneered (low select) by each S/G level channel nis ensures |that the lowest of each of the channel pairs is selected as the bistable input for that i
channel of the logic matrix. However, based on a worst case scenario', that is with the !
best channel (B) bypassed and the next best channel (C) inoperative due to a singlefailure, it is theoretically possible with the above results to violate the analytical limit of17.5% as a result of the error associated with channel A. As the logic is 2-out of 4,itwould take both the A and D channels to produce a trip, and the A channel portion of thelogic would not occur until 17.2%,0.3% below the analytical limit.
' However, as described earlier in section 3.1,6e error determination and analysis do nottake into account steam generator thermal growth and therefore there is available margindue to the increase in steam generator height between the tube sheet and the RPS tripetpoint of 21%. Based on Attachment 4 (S/G Hot DimensionyRef,1) and Attachment 1,Figures 1 & 2 (S/G Cold Dimensions /Ref.1) there is an available margin ofapproximately 1.1 inches due to S/G growth. De 0.3% S/G level deficit for RPS channel
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!A equates to approaimately 0.55 inches. Based on the available margin of 1.1 inches due
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15'5/GTrowth@ deficit of-0:55-inchesem beaccommodated with a balance of_0.55inches margin remaining. Since RPS channels B, C, and D do not exceed the analytical
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that the incorrect calibration of the Unit i S/G level transmitters would not have caused'
ithe Plant to operate outside the analytical limit for the RPS trip on low steam generator
j level. Additional margin wod 3 also be available in the Rosemount seismic uncenainty |,
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specification.
6.0 REFERENCES-.
1. FPL Calculation PSL-lFJI-93-013, Rev.1, S/G 12 vel Transmitter Calibratedj
Range.
2. Procedure 1-1400153A, Rev. 7, RPS - Loop Instrumentation Calibration of S/G
12 vel.
3. CE Calculation 19367 ICE-0613-00, S/G Level Measurement.
4 Condition Report No. 96-1532.
5. CE letter F-SF-1086, dated November 5,1976, S/G Level Transmitter
Cdibrations.
6. FPL Calculation PSL-BFJI 92-003, Rev. 2, Environmental Parameters forInstrument Uncenainty Analysis.
St. Lucie Unit 1 Updated Final Safety Analysis Repon, Amendment 14, dated7.6/95.
8. St. Lucie Technical Specifications through Amendment 145.
|9. '"Ihe Crane Companion (Ver.1.0) dated July 11,1996.
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Discipline Standard No. IC-3.17, Rev. 5, Instrument Setpoint Methodology for10. I
Nuclear Power Plants.
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Master Work Orders, Reactor Protection System Monthly Functional Test11.IC 1 1400050.
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94031609 01 95014446 01-
95001633 01 95018408 01
95004267 01 95024416 01
95007698 01 95027227 01
95010826 01 95029174 0195032706 01
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ATTAcMutNT 1PaGE 1 oF 6
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- - - - - - - - ._ _ _ . _ _ ERROR DETERMINATION _ __. __ _____ _ __ _ _.--
BACKGAOLTDt
The exieting level trane'mitter calibration data contained in I&C Procedure1-1400153A (Ref.2) is based on CE letter F-$F-1086 (Ref. 5) .
It appears these valueswere developed using the methodology contained in CE Calculation 19367-ICE-0613-00(Ref. 3) for the following conditions.-S/G Operating Pressure = 850 psia-8/G Saturation Tessperature = 525.24*F-Reference Leg Temperature = 120*F G 850 psia-Feedwater Temperature = 435'T 4 850 psia (p, = $2.32 lb/f t')-Downcomer Density (pe) = 48.65 lb/ft" ,
-Circulation Ratio (CR) = 4.2 6 100% Power-Calibration Reference = Inches of H O 4 68'T (Ref. 5)2
-S/G Thermal Growth = Not IncludedBased en the CE Calculation (Ref. 3), the S/G dimensions were obtained from the S/GGeneral Arrangement & Assembly Drawing, 233-601, Rev. 4, and not the S/Gas-built drawinge utilized in the FPL calculation (Ref. 1). The reference for the
elevations used f or the final CE calibration data (Ref. 5) is unknown.condensate potIn addition, S/G growth ef f ects were not included based on operating conditions at het
and therefore are based on S/G dimensions at '* COLD" conditions and S/Gfull power,process at " HOT" conditions.
is to establish the magnitude and direction ofThe purpose of the ERROR DETERMINATIONerror introduced from the incorrect calibration of the Unit 1 5/G 1evelthe pasttransmitters on the low S/G 1evel trip setpoints for RPS.
FORMULASI
Differential Pressurer (Ref. 1)[(H + L) palAP u,, = ( (H + L)po) -
(D)pe) - [ (H + L) palAPm = ((L)po + (H - D)pg +
APva = [(H + L - d)po + (d) pe) - [(H + L) pal |
where, APa = Delta-P G the min. operating level, lb/ft*APm = Delta-P G the max. operating level, ib/ft'AP. ,a = Delta-P G variable operating level below feed-ring, ib/ft'H = 5/G Narrow Range tap to tap dimension, ftL = S/G Narrow Range upper tap to ecndensate pot dimension, ftD = Downecaer dimension (L f eed-ring to lower tap), ftd = Variable downcomer level below f eed-ring, 'f tpo = density saturated steaa 9 850 psia, 1b/ft
= density reference leg fluid 9 850 psia /111*F, ib/ft'va = density saturated liquid 6 850 psia, lb/ft'pgve = density of downecoor liquid t 850 psia, Ib/ft'
povneccer Oensitv t (Ref. 3)p,)/CR#c = f(CR-1)pt +
where, pc = density of devnecoer liquid 6 850 psia, Ib[f t' )pt = density saturated liquid 6 850 psia,Ib/ f t' / f t |
ib
= density of f eedwater 4 850 psia, i;,
CR = Circulation Ratio of 4.2 010C% Pcwer||
Note: See Figures 1 & 2 of this Attachment for S/G dimensions at cold !
conditions. i
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ATTACHMENT 1Pact 2 or 6
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TARLE 1-1(All dimensions are given in feet unless noted otherwisei
dsTRANSMITTER H L D 2i
LT-9013A 15.24 1.96 6.0075 3.20
LT-90133 15.24 1.93 6.0075 3.20
LT-9013C 15.24 1.90 6.0075 3.20
LT-9013D 15.24 1.81 6.0075 3.20
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LT-9023A 15.18 1.57 5.967 3.19"
LT-90238 15.18 1.58 5.967 3.19 -
LT-9023c 15.18 1.72 5.967 3.19
LT-9023D 15.18 1.99 5.967 3.19
NOTE: 1. Dimensions based on Figures 1 & 2 of this attachment.
TABLE 1-2| STEAM CENERATOR 1A & 1B PROCESS CONSTANTS |
Calibration Reference Density (p.) 6 68'T 62.321 lb/ft'Reference Lag Density (pe) 0 111*F/850 psia 61.95 lb/ft'S/G Liquid Density (pt) 9 850 psia 47.505 lb/ft'S/G Steam Density (pa) G 850 psia 1.876 lb/ft'Feedwater Density (p,) t 435'F/850 psia 52.32 lb/ft'Downconer Density (pe) 48.65 lb/ft'Circulation Ratio (CR) 0 100% Power 4.2
SAMPLE CALCULATION:
Steam Generator 1At (LT-9013A)
((15.24+1.96)1.876) - [(15.24+1.96)61.95) = -1033.27 lb/f t' orAP, =
(-1033.27 lb/f t') x (1 f t'/144 in') = -7.176 lb / in' o r -7 .17 6 e s i=
[(15.24+1.91)61.95)((1.96)1.876 + (15.24 - 6.0075)47.505 + (6.0075)48.65) -
APm =
(1 f t'/144 i n')= -331.01 lb/ f t' or (-331.01 lb/ f t') x
= d .299 lb/in' or -2.299 esi((15.24 + 1.96 - 3.20)1.876 + ( 3. 2 0 ) 4 8. 6 5) - ( ( 15,. 2 4 + 1. 9 6 ) 61. 9 5 )APris =
-883. 60 lb/ f t' or (-883.60 lb/ f t') x (1 f t*/144 in')=
-6.136 lb/in' or -4.136 osi=
runun. m.r = e
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[(15.18+1.57)1.876) - [(15.18+1.57)61.95) = -1006.24 lb/f t' or jAPm =
(1 f t'/144 in') = -6.988 lb/in' or -6.988 est i.
(-1006.24 lb/f t') x=
APm = ( (1. 57)1.876 + (15.18 - 5.967 )47. 505 + (5.967 ) 48.,65 ) - [ (15.18+1. 57 )61.9 5 )(1 f t*/144 in') j= -306.76 lb/f t' or (-306.76 lb/f t') x
s r= -2.130 lb/in or -2.130 esi
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[(15.18+1.57)61.95)= -857.03 lb/f t* or (-857.03 lb/f t')[ ( 15.18 + 1. 57 - 3.19 ) 1. 87 6 + ( 3.19 ) 48. 65)/14 4 in')
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APa, =
x (1 ft ,
s= -5.952 lb/in or -5.952 esi
Plant calibration will be performed using, test gauges calibrated in in. Hp 9 68'F.''~
Therefore, conversion free psi to in. Hp $ 68'r is required to be consistent withPlant conditions. The conversion factor, in in. Hp ,/ psi, is 27.727 in. E A .,/_p.gi(Ref 1).Using the conversion facto. and the 6Pa , 6Pm, and 6Pis values for Steam Generators1A and 18, the actual AP and span can ~be determined in in. Hp $ 68*T and arepresented in the following table.
TABLE 1-3
ACTUAL AP Span ACTUAL AP
6Puu, (in. I0.*,) 6Puu (in . Ep.*,) (in. Ep.*,) 6P . (in. E,0..,)32
LT-9013A -199.0 -63.7 135.2 -170.1
LT-90133 -198.6 -63.4 135.2 -169.8
LT-9013C -198.3 -63.0 135.2 -169.4
LT-9013D -197.2 -62.0 135.2 -168.4
LT-9023A -193.8 -59.1 134.7 -165.0
LT-90238 -193.9 -59.2 134.7 -165.2
LT-9023C -195.5 -60.8 134.7 -166.8
LT-9023D -198.6 -63.9 134.7 -169.9
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The RzsULTS section compares the above ACTUAL APais for the 21% S/C level setpoint tothe transmitter calibrated AP for the 21% S/G 1evel setpoint to determine the % Irrorin 4 S/G 1evel for each transmitter. See Ref erence 2 for transmitter calibrated AP.
TABLE 1-4i
Level S/G s/G Dim. Signal Xmtr. Cal. Actual Error
Transmitter Level in. mA AP AP % Level,
% in. Hp.., in. HA. ,1I
100 182.88 20 -65.1 -63.7
21 38.40 7.3) -174.0 -170.1 +2.8~
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0 0.00 4 -202.9 -199.0
100 182.88 20 -64.1 -63.4
LT-9013E21 38.40 7.36 -172.6 -169.8 +2.1 f
0 0.00 4 -201.5 -198.6
' 100 182.88 20 -64.2 -63.0
LT-9013C21 38.40 7.36 -172.9 -169.4 +2.5
0 0.00 4 -201.8 -198.3
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100 182.88 20 -63.1 -62.0
LT-9013D21 38.40 7.36 -171.8 -168.4 +2.5
0 0.00 4 -200.7 -197.2
100 182.16 20 -61.7 -59.1
LT.9023A21 38.25 7.36 -169.9 -165.0 +3.6
0 0.00 4 -198.7 -193.8 j
100 182.16 20 -60.0 -59.2
LT-9023821 38.25 7.36 -168.2 -165.2 +2.2
0 0.00 4 -196.9 -193.9 ||
100 182.16 20 -61.5 -60.8
LT-9023C21 38.25 7.36 -169.7 -166.8 +2.2
0 0.00 4 -198.5 -195.5<
100 182.16 20 -65.9 -63.9*
LT-9023D21 38.25 7.36 -174.1 -169.9 +3.0
0 0.00 4 202.8 -198.6
Wote: The terror value indicates the deviation f rom true level to indicated level*
when true level is 21%.
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JPN v3L SElP 96G7REVISION O j. ,
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j COLD CONDm0NSi
!i Conderwtai LT 4013A shown.
P88! 79.54 See Tatdo 19er LT pet etevedons.
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77.07 -~~- . . . . . . . . . . . .
Ao.v. @)'
!"*rm ,
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d| 62.36*
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LTP PH L
614.8*
503.81*
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i37.2r ' ~ ' Top of Tube jg,
Sheet ,
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84'P*'t ! I
'M Base at _ . . . ._ _I_ . .. .f.'
*3ev. gTABLE 1
LT ri n
LT-9013A 79.5sLT-90138 79.5:r
LT-9013C 79.5CT
LT90130 79.41'
Figure 1'
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STEAM OENERATOR 1B _
COLD CONDmONSij
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! LT 9023A shown. MSee Tetdo 1 tor LT pot elevations.
f yg,yg.k
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77.80' ~~- f,A;-
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Feedring'
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IOUct. dm y~0% Level (NR)g g. } }
Dev. ' 4 .
'; LTj P P i
H L |,
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I! 37.2r ~ TopofTube; g, Wi!
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Base at
Dev. @ TABLE 1LT F1 EV.
LT 9023A 71.14'
LT.90238 79.17'. '
LT 9023C 79.31'
LT 90230 79.$r i ,
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JPN PSL SEIP 96 067REVISION 0
ATTACHMENT 2Uncertainty Analy$is PAGE 1 OF 1
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ANALYSIS OF ST. LUCIE UNIT 1 SG NARROW RANGE INSTRUMENT UNCERTAINTYI
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RPS Bistable SG Lvl Xmtr% SPAN Ref. % SPAN Ref.
Accuracy 0.125 A 0.25 8M&TE 0.125 A 0.35 BSet . Tot. 0.25 A 0.25 0 :
Drift 0 25 A 0.17 8Temp. Effect 0.25 A 0.42 8, ,
Static Press. Effect 0 A 0.65 8Seismic 0 A 0.58 8SRSS 0.468 C 1.101 CSRSS Total Uncert. (B/S & LT) 1.196 C ! i
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|SRSS One Sided Approach 1.00 C
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Ref. A) ABB,CE Cak:ulaton 19367-ICE.36308. Rev 0 SI Lxe Unit 1 RPS ESF and AFS Setpo.nts and{AScwabie Values '
Ref. 8) FPL Calculation PSL.1FJi-93-002. Rev 1. St Luce und 1 RPS. AFAS $!eam Generator Downcomer LevetTranunmer Uncertarey Ostermnataan (LT 901173A.B.C.D)
;Ref. C) Desco ris Standans IC-3.17. Rev. 5. Instrwnent Setport Methodology for Nuclear Power Plants : 1r
Ref. D) W =e 1 1400153A. Rev. 8. RPS - Loop instrumertaban Cahbrwon of S/G Level. '
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Ce 96-067 x!$
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JPN.PSL.SEIP.96-067REVISION 0
ATTACHMENT 3.
PAGE 3 OF 4'
ERRORANALYSIS_ .-
ERROR ANALYSIS OF ST. LUCIE UNIT 1 SG NARROW RANGE LEVEL-
RPS Channel CLT.9013C LT 9023C
Error (% of Span) 2.5 2.2 (See Attachment 1)Indicated Level @ 21 % 23.5 23.2
| Total Loop Uncertainty is +/- 1 (See Attachment 2)
+ Uncertainty 24.5 24.2, ,
Indicated Level @ 21 % 23.5 23.2- Uncertainty 22.5 22.2
24.5
24.2A SG
B SG22.5
| 22.2
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Compare both levelloops by selecting the lowest value when levels are at theirlowestand highest values.
SG A SG B Auctioneered Lowest Value3
Lowest 22.5 22.2 22.2Highest 24.5 24.2 24.2 maxA Highest /B Lowest 24.5 22.2 22,2A Lowest /B Highest 22.5 24.2 22.5
Worst Case Auctioneered Levelis 24 2 %when True level is 21%
Worst Case Error 32 %
Calculated Trip Point 17.8 %
Analytical Limit 17 5 %i
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JPN PSL SEIP 96-067REVISION 0
ATTACHMENT 3,
PAGE 4 OF 4 i_ ._ . . _ _ - . _ - - - ERROR ANALYS!S . - - - - - - - - - - - - - -
ERROR ANALYSIS OF ST. LUCIE UNIT 1 SG NARROW RANGE LEVEL'
RPS Channel DLT 9013D LT 9023D
Error (% of Span) - 2.5 3 (See Attachment 1)Indicated Level @ 21 23.5 24
Total Loop Uncertainty is +/- 1 (See Attachment 2)
+ Uncertainty 24.5 25.-
1Indicated Level @ 21 23.5 24
|- Uncertainty 22.5 23
25|
24.5
B SGA SG
2322.5
!Compare both levelloops by selecting the lowest value when levels are at their lowest
iand highest values.
1
SG A SG B Auctioneered Lowest VatueLowest 22.5 23 22.5Highest 24.5 25 24.5 maxA Highest /B Lowest 24.5 23 23A Lowest /B Highest 22.5 25 22.5
Worst Case Auctioneered Levelis 24.5 %when True Level is 21%
Worst Case Error 35 %
Calculated Trip Point 17.5 %
Analytical Limit 17.5 %,
i
file: 96-0671s
(.. .__ - -- . . . - .~
!. JPN-PSL-SEIP-06-067| REUISZOM O
| ATTACHMENT 4PACE A OF 3 ||
I..
!- - - - - - - . _ _ . _ _ _. _ _ _ , _ _ _ __
i! STEAM OENERATOR1A
! HOT CONDmONS ||
@ndensatoLT4013A shown.P'ISee Telne _1 forLT gotelevations
I Elev. '! L-
77,77 - - . . . . . . . . .
Elev.| @R):
Refersnce'j .
! L*9Ii H
:
I
65Af .,} .~
Elev, dm62AF ~J 0% Lavel(HR)Elev.
P PH Tou t
,
:
1 LT ELEY.
LT4013A 71L5s
LT40138 79.53'
LT4013C 79.5<40130 79A1'
37.2f~ ~
Top of Tube
Elev. Sheet
Support Skirt
(Growth Point)# sue of___.ia
Elev.
t
Ye
-- - - . - . , . , . . , . _ , . - . - . . . . - , - . - - - - - . - . , - - . , - - - - - -
. . . - . . - . . . ~ . - - - , _ - - ~ ._ . . - --. - - --_- -.__-. _.._.. --_ -. _ - ~ ____..
i JPH-PSL-SEIP-96-067| REVZS80N O.
'ATTAC10ENT 4
! PAGE 3 OF 3'
!''.
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,
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STEAM OENERATOR1B
HOT CONDmONS'
|!1
I
| LT 4023A shown. M| SeeTatdo1ter LT potelevadons ) _
-i 73,1g*
|Elev. ?
pL-
, -'
~ ~~ 100% Leveli TI M g,
Elev. (NR)
ReferenceLag
;e
i H
ss n .LEk y. dn'
82.53'"- J' 0% Level (NR)
j1 Eky.
L- L,
i
I T j 'liTABLE 1
! H . , _
1 LT I ELEY.i -
i LT-9023A 79.18'{ LT 90238 73.1 7 (| LT 902SC 79.31'{ LT 90230 79.58';6
i!
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| 37 M Top of Tube' - ^ "
SheetElev..
,
!. Support Sidrt '
i
(Growth PobQ> - c.
; _ .
N| Elev.
!
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|
Fireud. e6m'? tt
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JPN-PSL-ADIP-96-057-.
REVISION OATTAC) DENT 5PACE 1 OF 1,
,
_.. __ . _ . _ _ -____ _ _ __.-Reactor- Protection System _
Monthly FunctlOnal TestCompleted Data .
The following information represents 11 months of data obtained from PSL QA Recordsfor * COMPLETED" monthly functional tests of Plant Procedure 1-1400050'(Ref. 11) forthe Reactor Protection System steam generator low level bistables. The bistables havea nominal setpoint of -1.840 volts (221%) with a tolerance of -1.830 to -1.068 volts.
$ The work orders for the functional tests required that any out-of-tolerance readingswere to be reported to the IcM supervisor, and that the AS-FOUND and AS-LEFT values
,
were to be recorded in DATA SHEET 1 of the procedure. No data was entered in DATA-
SHEET 1 for the surveillance periods listpd below nor was there any evidence of anye
adjustments based on the journeymans report. Therefore, the voltage values areconsidered AS-POUND readings per step 7.2 of the procedure.
i== w
'suavEII.u xes srzAu I enAxxxL
PERIOD GE N TOR& 3 C D
4
1/95 1 -1.847 -1.843 -1.855 -1.845
2 -1.853 -1.838 -1.850 -1.848.
2/95 1 -1.854 -1.836 -1.857 -1.847
2 -1.843 -1.843 -1.857 -1.841
3/95 1 -1.866 -1.843 -1.863 -1.850
2 -1.865 -1.842 -1.858 -1.851
4/95 1 -1.853 -1.847 -1.848 -1.860'
2 -1.854 -1.838 -1.848 -1.840.
5/95 1 -1.855 -1.843 -1.857 -1.846
2 -1.84% -1.839 -1.851 -1.b40
6/95 1 -1.846 -1.839 -1.857 -1.849
2 -1.856 -1.842 -1.848 -1.847
7/95 1 -1.861 -1.840 -1.858 -1.835
2 -1.855 -1.833 -1.851 -1.342 _'
9/95 1 -1.860 -1.835 -1.860 -1.557-
2 -1.862 -1.840 -1.866 -1.847
10/95 1 -1.860 -1.842 -1.850 -1.830
2 -1.860 -1.841 -1.850 -1.844
,11/95 1 -1.855 -1.841 -1.852 -1.851;
2 -1.845 -1.837 -1.841 -1.840
12/95 1 -1.853 -1.847 -1.861 -1.843
_ . ...
-1.858 | -1.842 -1.s51 -1.e42:
,m - ,,
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,. PC/M 96 119-
Revision 2
Page 1 of 44
- - - - - - -- .- - HINOR-ENGINEERING-PACKAGE-(MEP)----- -
.
PLANT St Lucie UNIT 1 PC/M NWBER 96-119 SUPPL 2
ORIGINATING DOC &iENT EXPIRATION DATE N/A
PC/M CLASSIFICATION X _ SR . QR NNS ADMIN.
TITLE Setpoint Chance for AFAS,-
.
ADDITIONAL REQUIREMENTS / INSTRUCTIONS YES NO.
'
AS-BUILDING TO C0ttENCE UPON ISSUANCE OF PACKAGE? X
THIS PACKAGE FAS THE POTENTIAL TO SIGNIFICANTLY X,
IMPACT PERSONNEL RADIATION EXPOSURE (See Form 71).IF YES, FORM 72 15 REQUIRED.
10CFR50.59 SCREENING YES NO,
1) DOES THE CHANGE REPRESENT A CHANGE TO THE
FACILITY AS DESCRIBED IN THE SAR? X
2) DOES THE CHANGE REPRESENT A CHANGE TO
PROCEDURES AS DESCRIBED IN THE SAR? X
3) IS THE CHANGE ASSOCIATED WITH A TEST OREXPERIMENT NOT DESCRIBED IN THE SAR? X
4) COULD THE CFANGE AFFECT NUCLEAR SAFETY IN
A WAY NOT PREVIOUSLY EVALUATED IN THE SAR? X
5) DOES THE CHANGE REQUIRE A CHANGE TO THETECHNICAL SPECIFICATICNS? X
F;rm 131. :ev 6!9. DGe 10' 3
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PC/M 96 - 119
Revision 2-
Page 2 of 4,
- - - . . -- ..
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NOTE: IF THE ANSER TO ANY OF THE ABOVE IDCFR50.59 SCREENING OVEST10NS IS YES. THE KP CANNOT BE USED
'
REVIEW / APPROVAL:.
INTERFACE TYPE
GROUP PREPARED VERIFIED APPROVED FPt. APPROVED *
INPUT REVIE N/A
"ummmmmmmmmmm mummmmmmmmmmmmmmus---
Fech X
ELECT X
I&C X
civil X
M)fM _% [#MA*
NUC" Lead g ;
kESI X
NUC FUEL X
* For Contractor KPs As Determined By Projects " Review Interface As A Mininun Ch All Non Adnin KPsi
FPL PROJECTS APPROVAL: [A/ DATE: d//Vfc!
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PC/M 96- 119-r -
Revision 2
Page 3 of 4.,
_.__ENGINEERINGJUSTIFICATION.__ - _ _ . _ _ _ . _ _ _ _ _. ___
This Minor Engineering Package (MEP) provides for an increase to the S/G leveltrip setpoint at which AFAS actuation will occur. The new setpoint will be 24.5%narrow range level. This new setpoint will conservatively bound theuncertainties associated with differences between the "as found" and design S/Ginstrument level tap elevations.
Revision 1 to this MEP includes the verified walk down elevation data~
(Attachment 1) that confirms the new setpoint as conservatively bounding theuncertainties associated with differences between the "as found" and design S/G-
instrument level tap elevations.
Revision 2 to this MEP clarifies the FSAR update error regarding the setpointvalue for AFAS actuation.
Technical SpecificationsTech Spec LCO 3.3.2.1 provides for the AFAS trip setpoint to be greater than orequal to 19.0% and the allowable value to be greater than or equal to 18.0%.
FSAR
The limiting analysis with respect to AFAS actuation is the loss of feedwateranalysis described in Section 10.5. This analysis bounds Chapter 15 events. Inthis analysis. the assumed AFAS trip setpoint_is 15.3% S/G narrow range level.This analysis value includes all necessary uncertainties.
EvaluationThe limiting transient for determining the AFAS setpoint is the loss of feedwater, event. In this event the concern is the loss of secondary side heat sink. AFAS
actuation at or above the setpoint presented in the FSAR will ensure that S/Gdry out does not occur. Note that this transient is analyzed for Mode 1. fullpower operation. For Modes 3 & 4. where this re.v setpoint will be in effect,substantial additional margin is available.
No other transient or accident described in the FSAR is adversely affected bythis cnange in set;oint. -
Section 7.3.2 describes the AFAS signal incluoing an actuaticn setpoint of 19%.The stated setpoint value of 19% is in error. The stated value should be greaterthan or equal to 19%. consistent with the amendment to the TechnicalSpecification wnich cecreased the setpoint frca 29.0% to greater than or equalto 19.0% (Ref 3). ::rditicn recort (9F.775) as accressed *.his FSAR updateerror and ccrrecucn to tne FSAR will :e Tace at its next scheduled update,'erefore. changing the AFAS setcoint to 24.5% for Moces 3 & 4 is not ccnsidered
~ge to the plant as cescribed in the FSAR.~a
erm 131 s < 6/94. Page 3 Of 2r e
'
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PC/M 96 119-
.' Revision 2
Page 4 of 4
Hode RestrictionsThis setpoint change is limited to Modes 3 & 4 only.
Design IntegrationA design integration review has been conducted, and the following sources havebeen reviewed for impact:
1) No drawings are being changed.'~
2) Safetyevaluationsarenotaffect(d.3) PC/Ms are not affected.
ConclusionThe above evaluation ensures design equivalence and conformance to the originaldesign bases as described in the FSAR. Furthermore, this setpoint change doesnot affect any procedures discussed in the FSAR. introduce any new test orexperiments or affect any Technical Specifications. Based on the above a 10 CFR50.59 evaluation is not required.
AFFECTED DOClNENTS
Operations and Maintenance will review appropriate procedures affected by thissetpoint change.
SPECIAL INSTRUCTIONS \ IMPLEMENTATION REQUIREMENTS
The original setpoint is required to be restored prior to entry into Mode 2. The I
setpoint change will be to both AFAS 1 & 2.
REFERENCES
1. St. Lucie Unit 1 FSAR. Through Amendment 14,2. St. Lucie P1 ant Unit 1 Technical Specifications. through Amendment 142.3. L 90-46, dated 3/9/90.
ATTAC!NENTS
Attachment 1: JPN-PSLP 96-0144. 7/19 96. (5 cages including 3 attachments)
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CALCULATION COVER SHEET
Calculation No: PSL-1FSN-96-002
Title: Containment Atmosphere Gaseous Monitor Response to RCSLeakage Durino Normal Plant Oneration
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No. Description | Sy Date Chkd Date Appr Date
f REVISIONSer
Fonn 82A, Rev 6/94
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Page :.
LIST _0E_. EFFECTIVE PAGES.._ . - . _ . . _ . . . . . - - . - . - - - - - - . . - - . - - .
Calculation No.: PSL-1FSN-96-002 Rev.: 0
Title: Containment Atmosphere Gaseous Monitor Response to RCS
Leakage During Normal Plant Operation
. - . .
Page Section Rev. Page Section Rev.
i 0ii oiii 0
1 02 03 04 05 0G 07 08 0
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Form 923, Rev 6e74
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iTABLE OF cQNTENTS*
, _ _ _ _ . . . _ _ - - _ __ _ ___._ ._ _ _ ___
i__ _ _ _ . _ _ _ . _ _ _ _ ____ _
:
CALCULATION NUMBER: PSL-1FSN-96-002 REV.: 0|
' SECTION TITLE PAGES
: Cover Sheet i--
List of Effective Pages 11--
,,
} Table of Contents lii--
ii 1.0 Purpose / Scope 1i
2.0 References 1,
3.0..
Methodology 2
4.0 Assumptions / Bases 34
l| 5.0 Calculation 4 l'
s
6.0 Results 7,
j ATTACH NO. TITLE PAGES4
1 Spreadsheet Results Summary 12,
2 9/26/96 Memo, Faulkner (Chemistry) to 1
4' Wasik (Engineering):J i
1 I
4
1
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Form 82C, Rev 6/94
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Colculation No. PSL-1FSN-96-002 Revision 0 Sheet No. 1e
_ ,__ _
_ _ . . ._.._
1. PURPOSE / SCOPE
Condition Report (CR) 96-2228 was written to document a need to !validate the design of the Unit 1 and 2 particulate and gaseousradiation monitors since design basis information was notavailable. The CR raised questions with respect to thefollowing aspects of system design and operation:
-the use of 10%;of scale change as an indication of a 1 gpm-
increase in reactor coolant system (RCS) leakage (as" described in the UFSAR); "
!- the requirement for isokinetic sample flow (affects
particulate monitor only);,
*ethe current practice of setting the alarm at 2 times-
background; and
- the detector response time associated with detecting a 1gpm increase in RCS leakage.
The purpose of this calculation is to address the above listeditems as they pertain to the design and operation of RE-26-32,the containment gaseous radiation monitor.
This calculation supersedes calculation PSL-1FJN-92-011(reference 2.1).
2. REEERENCES
2.1 Calculation PSL-1FJN-92-011, Response Time for theContainment Atmosphere Gaseous Monitor to Detect a 1.0 gpmRCS Leak During Normal Plant Operation, Rev. O.
!2.2 Chart of the Nuclides, Knolls Atomic Power Laboratorf, Ninth iEdition.
2.3 Memo from D.H. Faulkner (Chemistry) to Chris Wasik,(Engineering), Subject: Normal Unit 1 Reactor Coolant Rb- ;
88 and Xe-133 Values, 9/26/96. |
| 2.4 St. Lucie Unit 1 Updated Final Safety Analysis Report,'
through amendment 14, Table 11.1-1.1
'
2.5 USNRC Regulatory Guide 1.45, Reactor Coolant Pressure| Boundary Leakage Detection Systems, May, 1973.i
2.6 St. Lucie Unit 1 Updated Final Safety Analysis Report,through amendment 14, Table 6.2-9.,
2
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Calculation No. PSL-1FSN-96-002 Revision _D_ Sheet No. 2_ ',
. ._ _ ____2._7..___St _ Lucia Uni t 1 Updated-F-inal-Safety-Analysis -Reportv -- - ----- -through amendment 14, Table 6.3-6.
2.8 Chemistry Procedure No. 1-C-67, Calibration of the.Containment Process Monitor, Calibration Certificate dated!8/5/88. '
!2.9 Nuclear Reactor Engineering, Third Edition, SamuelGlasstone and Alexander Sesonske, Van.Nostrand Reinhold j
'
Company, 1981, Chapter 2.
" '3. METHODOLOGY
j*
3.1 The calculation was performed using an Excel spreadsheetwhich considered the RCS leakage event in discrete intervalsas discussed in Section 4.8.
3.2 Sheet 1 of the spreadsheet was used to calculate, in'one hourintervals,:
1
1. the total activity of Xe-133 (uci) in containment basedon a given RCS leak rate and a given RCS Xe-133concentration (uCi/cc) ;
2. the containment Xe-133 concentration (uCi/cc) based onthe results of #1 above;
3. the gaseous monitor detector reading change (cpm) basedon the results of #2 above.
3.3 Sheet 2 of the spreadsheet was used to calculate, in oneminute intervals,:
1. the total activity of Xe-133 (uci) in containment basedon a given RCS leak rate and a given RCS Xe-133concentration (uCi/cc);
2. the containment Xe-133 concentration (uci/cc) based onthe results of #1 above and factoring in a 14 minutedelay time;
3. the gaseous monitor detector reading change (cpm) basedon the results cf #2 above.
.
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Calculation No. PS L - 1 FS N - 9 6 - 0.0L Revision __0__ Sheet No. 3 !. .
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--4. An m. ..tions/ Bases - - - - - - - - - _ _ _ -1
'4.1 The containment background countrate is defined as the ,
countrate associated with plant operations prior to the |
assumed 1 gpm step increase in RCS leakage. This countrate !iis a function of the initial existing RCS leakage rate and
2 the RCS Xe-133 activity level.
4.2 All dynamic events are asw.med to occur in either one minute |
or one hour intervals. 1"
One hour intervals are used in calculating background-
readings as well as for calculating the time for detection,
of a doubling of the background countrate (given a 1 gpm stepincrease in RCS leakage) .
I One minute intervals are used in calculating the time fordetection of a lot increase in . the background countrate(given a 1 gpm step increase in RCS leakage).'
1
4.3 The only isotope considered in this evaluation shall bej, xenon- 13 3 . (Xe - 13 3 ) .. Xe-133 is an isotope which dominates
detector response. The affects of other radioactive isotopes i
shall be ignored. ||
'4.4 The radioactive half-life of Xe-133 is assumed to be 5.27 !
days (reference 2.2). |i
4.5 The RCS Xe-133 activity is assumed to be 0.00236 uCi/cc ]during typical plant operations. This value is based on an j
average of RCS sample Xe-133 activities provided by Chemistry.
(reference 2.3).,
4.6 The RCS Xe-133 activity is assumed to be 18.1 uCi/cc duringUFSAR defined normal operations of 0.1% failed. fuel
,
*
(reference 2.4).
4.7 The RCS leakage rate to be detected is assumed to be a stepincrease of 1.0 gpm. This value is based on N'RC RegulatoryGuide 1.45 (reference 2.5).
4.8 For the calculations using one minute intervals, the Xe-133activity is assumed to be unifonnly dispersed throughout the,
containment volume after a period of 14 minutes. This valuerepresents the time for the containment coonng system,operating at 180,000 cfm (reference 2.6), to provide onecomolete turnover of the containment free volume of 2.5E+6
,ft (reference 2.7). Although radioactive decay is factored,
in to this delay, the delay is intended more for time linepurposes to provide a more conservative calculation of total
.time (radioactive decay of Xe-133 over a 14 minute period is |
'
"C.13%).|
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Calculation No. PSL-1FSN-96-002_ Revision 0 Sheet No. 4.
The 14 minute delay is not assumed in the calculations usingone hour intervals since these calculations are looking at !
longer time intervals such that a 14 minute delay would beinsignificant.
4.9 All Xe-133 present in the RCS leakage is assumed to bereleased to the containment atmosphere since, at normal RCStemperature and pressure, any leakage would be flashed tosteam.
4.10 The sample flow rate has no effect on detector response due',
to low system volumes and the'long radioactive half-life ofXe-133.
.
4.11 Detector sensitivity to Xe-133 is assumed to be 1.25E-07uCi/cc/ cpm or 8,000,000 cpm /uCi/cc (reference 2.8).
4.12 Typical gaseous monitor readings are assumed to beapproximately 80-100 cpm based on discussions with cognizantpersonnel and personal observation in the control room.
5. CALCULATION
5.1 Use of a 10% change in Indication - Tvnical Operations
Section 5.2.4 of the UFSAR describes using a 10% deviationin the normal reading of the monitor as an indication of astep increase in RCS leakage from 0.1 to 1.0 gpm. Table 5.2-11 notes that it would conservatively take 15.1 hours for a10% change to be observed. Since no original design basiscalculations are available, it is not clear exactly what wasconsidered as the normal meter indication and how the 15.1hours was calculated. It should also be noted that theoriginal plant design considered normal operations with 0.1%failed fuel (reference 2.4). Since today's fuel performance
,
is much better, containment activity levels are' correspondingly lower. With the containment gaseous monitor
4 fluctuating between 80 and 110 cpm under typical. operatingconditions as observed in the control room, it would bedifficult to detect an 8 to 11 cpm increase as an indicationof increased RCS leakage.
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Calculation No. PSL-1FSN-96-002 Revision 0 Sheet No. 5
. - - . __.__ __.54_. mssous- Moni-tor-Rasnonne-t e- Res-Le a kag e -W cal-Oc e ra tirnn-- - - -~
This calculation predicts the response of the gaseous monitorto a 1 gpm step increase in RCS leakage based upon typical '
RCS Xe-133 activity levels (Section 4.5).l|The sections below describe the formulas used in the i
spreadsheet.
5.2.1 The rate of Xe-133 leaked to containment atmosphere for each1 minute interval is calculated as follows:. 1
il
Rate = (RCS Xe-133 Concentration) x (RCS Leak Rate) (!
Rate = (.00236uCi/cc) x (1.0 gpm) x (3785 cc/ gal) I
Rate = 9 uCi/ min
5.2.2 The total curie content (activity) of Xe-133 in thecontainment atmosphere for each 1 minute interval iscalculated as follows: ,
!!
|)
ActMty = (Rate of Xe-133 Leakage) + (ActMty from Previous interval) x (1 Min. Decay Factor) |
The Decay Factor is calculated using the standard radioactivedecay formula (reference 2.9) and the 5.27 day half-life ofXe-133 as follows:
;
I1
Decayed Value = (Original Value) x (e* )
Where: L = 0.693 0 693 = 9.132E-05 min"=
half-life (5.27 d) x (24 hr/d) x (60 min /hr)
t = 1 minute
Thus:
Decayed Value = (Original Value) x (0 9999)
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Calculation No. PS L - 1'FSN- 9 6 - 0 0 2 _ Revision 0 Sheet No. 6'
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- - 5 2.3-Allowing-a-14- minute--delay-te--aHow-for- containment- - - !atmosphere mixing, the concentration of Xe-133 in thecontainment for any given interval is calculated as follows:
!
Xe-133 Conc. (uCVcc) = (Xe-133 ActMtv) x (14 Min. h cav Factor) !t(Containment Volu,'ne)
Where: Containment Volume = 70800000000 cc t
Decay Factor = 0.9987 (calculated as in 5.2.2 above)w .-
t
5.2.4 The detector indication is calculated using the Section4.11 cpm /uCi/cc conversion
!
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Indication = (Containment Xe-133 Conc., uCi/cc) x (8.00E+06 cpm /uCL/cc)
6
5.3 Gaseous Monitor Response to RCS Leakace - 'O.1% Failed Fuel !
!iThis calculation predicts the response of the gaseous monitor
to c. 1 gpm step increase in RCS leakage based upon normal RCS *
Xe-133 activity levels (Section 4.6).
5.3.1 In order to assess detector response and alarm setpointmethodology under UFSAR normal operating conditions (0.1% ;
failed fuel), we first need to know the background countrate.Since typical fuel performance is much better than 0.1% i
failed fuel, the typical background countrate of 80-110 cpmcannot be used.
tThe background countrate is associated with an equilibrium '
Xe-133 concentration in the containment. Since Xe-133 has ;
a half-life of 5.27 days, the time to reach equilibrium is,
on the order of hundreds of hours. Because of this, thebackground countrate was calculated in intervals of one hour. !
The calculational methodology used is the same as that inSection 5.2, except that the 14 minute delay was not !
,
considered. Background countrates were calculated for RCSleak rates of 0.1, 0.25, 0.5, 0.75 and 1.00 gpm.
.
5.3.2 With the background count $ rate established, we can calculateithe time for detector response to a 1.0 gpm step increase in
RCS leakage (i.e., RCS leakage in addition to the initial !leakage values of Section 5.3.1). Again, the calculational !
methodology is the same as-in Section 5.2. It was determinedby preliminary calculations that the time to double thebackground countrate would be on the order of many hours;therefore, the 14 minute delay was not considered and onehour intervals were used. Since the time to increase thebackground countrate by 10% is much shorter, one minute i
intervals and a 14 minute delay were assumed (results were[cnverted o hours). i
;,
. _ _ _ _ _ _ _ _
.. . .- . _ - .. --._-_- _.- -. . .. . . - . . . . . - . - - .
.
Calculation No. ._ES L _1ESN - 9 6 - O O2 Revision _Q_., Sheet No. 7, .
. - - 5.4_.Ja n enu a . Monitor- RespoDae--to- RCS- Leakage-- 0. 01% -Fa il ed - Fuel-- --
| 5.4.1 The calculations of Section 5.3.1 and 5.3.2 were repeated forRCS Xe-133 activities associated with 0.01% failed fuel forcomparison purposes. The Xe-133 activity for 0.01% failedfuel is simply 1/10th of the value for 0.1% failed fuel.
6. RESULTS:,
6.1 The use of a 10% of indication change in detector reading as |an indication of a 1.0 gpm , step change in RCS leakage is,,
difficult given the current operating environment withimproved fuel performance.
6.2 Under typical operating conditions the containment gaseousmonitor is incapable of indicating a 1 gpm step increase inRCS leakage. Attachment 1 provides a portion of thespreadsheet results. As shown on the spreadsheet, thecountrate increase is negligible after 10 hours. This lowdetector response is due to the low RCS activitiesexperienced during typical plant operations. These resultsare consistent with NRC Regulatory Guide 1.45 commentsregarding the limited value of containment radiationdetectors in providing an early warning of very small leakswhen RCS radioactivity is low. ' !
Ii
6.3 The table below shows the results of the calculationsdescribed in Sections 5.3 and 5.4.
RESHLTS
For a i gpm RCS Leak Rate IncreaseBackground Countrate: Time for Background Countrate to:
;
iInitial Leak Rate 0.1 % Failed Fuel 0.01 % Failed Fuel Double lacrease 10% j(gpm) (epm) (epm) (bours) (hours) )0.10 8434 843 19 2.1 )0.25 21084 2108 52 4.9
0.50 42168 4217 125 9.6
0.75 63251 6325 251 14.5
1.00 94335 8434 1200 19.5
'
.
I
1
|:I
i-
f'
.- ..
v.
Calculction No. PSIN FSN- 9 6 0 02 __ Rcvicien O Shsst No. 8Dt..
The following conclusions can be mad _ej rom.thes_e__results:___
1. The time for detector response with respect to a givenpercent change in background countrate is independent ofRCS activil'y (i.e., failed fuel fraction). This resultis expectedgsince a percent change in indicated countrate-
is a function of the change in Xe-133 concentration inthe contaliiment atmosphere which is ~ a function of twofixed values: RCS leak rate (fixed at 1 gpm), and thehalf-life iof Xe-133. The figure 1 curve- shows thecountrate ihcrease as a percent of containment atmosphereequilibriudi concentration of Xe-133.
-
It is unacc|eptable to use an alarm setpoint of two times<
'
2. -
background as an indication of a 1.0 gpm step increase in -
RCS leakage since the time to an alarm would be too long(except for' initial RCS leakage <<0.1 spm) .
3. Except for when RCS Xe-133 activity levels are low, it isacceptable to use a 10% change in countrate as anindication.of a 1.0 gpm step increase in RCS. leakage.The results'show that the detector can respond within 24hours as n,oted in UFSAR Section 5.2.4.6.
Fiaura 1
COUNTRATE INCREASE vs. TIME
100% 3-- ,. . .. . . . ,
l ! l i i90 %
d 80% j i!! i i i i | i :i t 4,
I*
I60%70% ! I I I )| y,>
,j
j/~l' . ; j: i, ,*
O 'A% ; !'
'
! ! |'
14% ' ' '
b | I i i
g ,%
- .
@ 20% - '
E i
8 10% - ;o,
0%.
k kkkkkk$kr
TIME (HRS) ;
i
I
j
!
1
*-
., ,
Attachmtnt i IPSL-1FSN.96 002, Rev. 0 '
,,
..- . _ . _ . _ _ _ - - _ _ . . _ _ . . . _ _ . __ i
_| UNIT 1 CONTAINMENT GASEOUS MONITORI
i | |RCS Xe-133 Conc. m ,2.30EOswar uCi/cc
RCS Leak Rate ' 1.00 - ~ gpmActivety into RCB 9 uCL/ min
b 14 MIN DELAY DETECTORRC8 RCB Xe-133 ADJUSTED READING
TIME ACTIVITY CONC. TIME CHANGE"
(min) (uCI) (uCifbc) (min) (cpm)
0 0.00E+00 0.00E+00 14 0
1 8.93E+00 1.26E-10 15 0 |
2 1.79E+01 2.52E-10 16 03 2.68E+01 3.78E 10 17 04 3.57E+01 5.04E-10 18 0
5 4.47E+01 6.30E 10 19 0,
6 5.36E+01 i 7.56E-10 1 20 0 l7 6.25E+ 01 8.82E-10 21 0 1,
I8 i 7.14E+01 ! 1.01E-09 22 1 0'
9 8.04E+01 1.13E-09 23 0'
10 i 8.93E+01 1.26E 09 24 0
11 | 9.82E+01 1.39E-09 25 0
12 i 1.07E+02 1.51 E-09 26 013 1 1.16E+02 1.64E-09 27 0
14 i 1.25E+02 i 1.76E-09 28 0
15 1.34E+02 ~ ~" 1.89d-09 1 29 0-
,
16 1.43E+02 2.01 E-09 ; 30 ! 0 !17 1.52E+02 2.14E-09 i 31 i 0
_
18 I 1.61 E+02 2.27E-09 1 32 I O,
2.39E-09 i 33 i 0 |
20-~~ 1.70E+0219 '
~~
1.78E+02 BI2E-09 34 0 )1
21 | 1.87E+02 i 2.64E-09 1 35 I Ol
22 1.96E+02 i 2.77E-09 ! 36 I O
23 2.05E+02 '_ 2.89E-09 37 0'
24 2.14E+02 3.02E-09 38 0 j,
39 1 025 2.23E+02 3.15E-09 '
26 2.32E+02 3.27E-09 1 40 i 0
27 2.41 E+02 3.40E-09 i 41 i 0
28 2.50E+02 3.52E-09 42 0
29 2.59E+02 3.65E-09 43 0.
~ 30 2.68E+02 ~ 3.77E-09 44 0
31 2.76E+02 3.90E-09 45 0
32 2.85E+02 4.03E-09 46 0
33 2.94E+02 4.15E-09 47 0'
34 3.03E+02 4 28E-09 48 0
35 3 12E + 02 4 40E.09 49 0,
36 3 21E+02 4 53E-09 50 0
Page 1
i
|.
.
Attachment 1PSL-1FSN-96-002, Rev. 0i
.
_ _ _ _ _ . . . . _
37 3.30E+02 4 65E-09 51 0_ _ _ _ _ _ . . _ _ _ _ .
38 3.39E+02 i ~iNE 09 i 52 ! O39 3.48E+02 1 4.90E-09 53 0' i
40 3.57E+02 1 5.03E-09 54 0 141 3.66E+02 5.16E-09 55 0 I42 3.74E+02 5.28E 09 56 i 0 !43 3.83E+02 5.41 E-09 57 0 |44 3.92E+02 5.53E-09 58 045 4.01E+02 5.66E-09 59 046 4.10E+02 5.78E-09 60 047 4.19E+02 ; 5.91 F,-09 i 61 3-__
48 4.28E+02 l 6.03E-09 i 62 i
49 4.37E+02 6.16E 09 1 63 > 050 4.46E+02 i 6.28E-09 i 64 ! O51 4.54E+02 1 6.41 E-09 65 1 052 4.63E+02 6.54E-09 66 1 0.
53 4.72E+02 i 6.66E-09 67 I O
54 4.81E+02 6.79E-09 68 0,
}55 4.90E+02 { 6.91 E-09 69 O
56 4.99E+02 i 7.04E-09 70 ! 057 5.08E+02 i 7.16E-09 ' 71 i 058 5.17E+02 7.29E-09 72 1 059 5.25E+02 7.41 E-09 73 1 060 5.34E+02 7.54E-09 74 I O61 5.43Et02 7.66E-09 75 l 062 5.52E+02 7.79E-09 76 | 063 5.61E+02 i 7.91 E-09 77 i 0
~
64 1 5.70E+02 8.04E-09 78 0'
65 i 5.79E+02 ,,_ , _8.16E-09 79 066 ! 5.88E+02
~~8.29E-09 I 80
_
0>
67 5.97E+02 8.41 E-09 i 81 1 068 6.05E+02 8.54E-09 82 069 6.14E+02 3.66E-09 83 0 I
.
70 1 6.23E+02 t 8.79E-09 i 84 071 i 6.32E+02 8.91 E-09 ! 85 04
72 i 6.41 E+ 02 9.04E-09 i 86 073 i 6.50E+02 9.17E-09 i 87 074 i 6.59E+02 9.29E-09 ; 88 0,
75 6.67E+02 9.42E-09 i 89 0i
76 6.76E+02 9.54E-09 : 90 077 6.85E+02 9.67E-09 91 078 6.94E+02 9.79E-09 92 079 7.03E+02 9.92E-09 93 080 7.12E+02 1.00E-08 94 081 7.21 E+02 1.02E-08 95 082 7.30E+02 1.03E-08 96 0,
83 7.38E+02_ _1.04 E-08 97 0
84 7.47E+02 1.05E-08 98 085 7.56E+02 1.07E-08 99 086 7 65E+02 1.08E-08 100 0
<
Page 2
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|Attachment 1PSL-1FSN.96 002. Rev 0t
',. '
~ ~ ~
^87 7 ~~ ~ ~~~
^
7.74E+02 109E 08 i 101 l 0.
88 I 7.83E+02 1.10E-08 102 ! O
,
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~89 7.92E+02 1.12E-08 | 103 0 |i~ ~ *
8.005'~0T l 1.'i3'E-08 104 'O~ - ~ ~ ~ " ~ ~
90 +
91 8.09E+02 1.14E-08 105 0 .'92 8.18E+02 1.15E-08 106 1 093 8.27E+02 1.17E 08 107 1 0 ,
94 8.36E+02 1.18E-08 108 095 8.45E+02 1.19E-08 109 096 8.53E+02 1.20E-08 110 097 8.62E+02 i 1.22E-08 111 0-
,
98 8.71 E+02 | 1.23E-08 112 0|'
99 8.80E+02 i 1.24E-08 113 0100 8.89E+02 1.25E-08 114 0101 8.98E+02 1.27E-08 115 0102
_
9.07E+02 | 1.28E-08 116 0103 | 9.15E+02 1.29E-08 117 0104 i 9.24E+02 1.30E-08 118 0
'105 9.33E+02 1.32E 08 119 0106 9.42E+02 1.33E-08 '1'20 0107 9.51 E+02 ! 1.34E-08 121 0108 9.60E+02 I 1.35E-08 122 0 l
109 9.68E+02 1.37E-08 123 0110 9.77E+02 1.38E-08 124 0111 9.86E+02 1.39E-08 125 0112 9.95E+02 1.40E-08 126 0
_ 113 1 1.00E+03 j _1 42E-08 127 0114 1.01E+03 I 1.43E-08 128 0 4
115 1.02E+03 ~ 1.44E-08 129 0-
116 1.03E+03 i 1.45E-08 130 0117 1.04E+03 1.47E 08 131 0-
118 1.05E+03 1.48E-08 i 132 0;
119 1.06E+03 i 1.49E-08 i 133 1 0'
1.07E+03 1 1.50E-08 134 0 I120 +
121 1.07E+03 i 1.52E-08 135 0122 1.08E+03
_ _1.53E-08 | 136 O'
123 1.09E+03 | 1.54E-08 1 137 I 0>
124 1.10E+03'
155E-08 138 0,
125 1.11 E+ 03 1.57E-08 139 0'i
0 |126 1.12E+03 1.58E-08 140 |
127 1.13E+03 1.59E-08 141 ; O
128 1.14E+03 1.60E 08 142 i 0129 1.14E+03 1.62E-08 1 143 0,
130 1.15E+03 __ 1._63 E-08 144 0131 1.16E+03 _ , _ . _ 1.64E-08 145 0-
132 1.17E+03 165E-08 146 0-
133 1.18E+03 _ 166E-08 147 0134 1.19E+03 1.68E-08 148 0135 1.20E+03 1.69E-08 149 0136 1.21 E+03 1.70E-08 150 0
Page 3
**
6
6,
.., f Altschmsnt 1PSL-1FSN 96-002. Rev. 0,
*
i
137 | 1.22E+03 i 1.71E-08 1 151 0138 1.22E+ 03 1 1.73E 08 1 152 ! O139 1.23E+03 1.74E-08 i 153 0.
140 1.24E+03 1.75E-08 154 0141 1.25E+03 1.76E-08 155 0142 1.26E+03 1.78E-08 156 0143 1.27E+03 1.79E-08 157 0144 1.28E+03 1.80E-08 158 0145 1.29E+03 1.81E-08 159 0146 1.29E+03 1.83E-08 160 0147 1.30E+03 1.84E.08 161 0
-
148 1.31 E+03 1.85E 08 162 0149 1.32E+03 1.86E-08 163 i 0150 1.33E+03 1.88E-08 164 1 0151 1.34E+03 1.89E-08 165 i 0 -
152 1.35E+03 1.90E-08 166 0153 1.36E+03 1.91 E-08 167 0154 1.37E+03 | 1.93E-08 | 168 1 0155 1.37E+03 l 1.94E-08 169 I O156 1.38E+03 8 1.95 E-08 170 1 0157 1.39E+03 1 1.96E-03 ! 171 1 0158 1.40E+03 1.98E-08 172 i 0159 1.41 E+03 1.99E-08 173 0160 1.42E+03 2.00E-08 174 0161 1.43E+03 2.01E-08 175 0162 1.44E+0 - 2.02E-08 176 0163 1.44E+03 2 n4E-08 1 177 0 |164 ! 1.45E+03 : 2.05E 08 | 178 0165 1 1.46E+03 i 2.06E-0C i 179 i 0166 i 1.4 7E+03 t 2.07E-08 ' 180 1 0167 | 1.48E+03 i 2.09E-08 i 181 1 0168 1.49E+03 2.10E-08 182 0169 ! 1.50E+03 2.11 E-08 ! 183 i 0+
170 1 1.51 E+03 i 2.12E-08 1 184 1 0171 : 1.51E+03 2.14E-08 185 0'
172 1.52E+03 2.15E-08 186 6 0r
173 1.53E+03 2.16E-08 ! 187 t 0174 1.54E+03 2.17E-08 I 188 i 0'
175 1.55E+03 2.19E-08 i 189 0176 1.56E+03 2.20E-08 190 0177 1.57E+03 2.21 E-08 191 0178 1.58E+03 2.22E-08 192 0179 1.58E+03 2.24E-08 193 0180 1.59E+03 2.25E-08 194 0
*
181 1.60E+03 2.26E-08 195 0182 1.61 E+03 2.27E-08 196 0.
183 1.62E+ 03 2.28E-08 197 0184 1.63E+03 2.30E-08 198 0185 1.64 E+ 03 '~2.31 E-08 199 0186 1.65E+03 ~2.32E-08 200 0
Page 4
_ .__ __ . _ . __ _ __ . . _ _ _ . _ _ . _ _. _. _ - . _ _ . _ . _ _ _ _ _ _ _ _
.
-
t
Attachment 1 |PSL-1FSN 96-002 Rev. 0, *
* 4
.i
,
'
187 1 1.65E+03 j 2.33E-08 201 1 0 j188 ! 1.66E+03 2.35E-08 202 0
'
{189 1 1.67E+03 2.36E 08 203 0 i190 1.68E+03 2.37E-08 204 0191 1.69E+' 03 2.38E-06 205 0192 1.70E+03 2.40E-08 206 0^
193 1.71E+03 2.41E 08 207 0194 1.72E+03 2.42E-08 208 0195 1.735!403 2.43E-08 209 0 i196 1.73E+03 2.45E-08 210 0197 1.74E+03 2.46F.,;08 211 0
-, . _
i 198 1.75E+03 2.47E-08 212 0199 1.76E+03 2.48E-08 213 0200 1.77E+03 2.50E-08 214 0201 1.78E+03 2.51E-08 215 0
'
202 1.79E+03 2.52E-08 216 0203 1.80E+03 2.53E-08 217 0204 1.80E+03 2.54E-08 218 0205 1.81E+03 _ _ 2.56E-08 219 0206 1.82E+03 2.57E-08 220 0207 1.83E+03 2.58E-08 221 0208 1.84E+03 2.59E-08 222 0209 1.85E+03 2.61 E-08 223 0210 1.86E+03 2.62E-08 224 0211 1.87E+03 2.63E-08 225 0212 1.87Et03 2.64E-08 226 0213 1.88E+03 . 2.66E-08 227 0214 1.89E+03 i~ 2.67E-08 i 228 | 0215 1.90E+03 2.68E-08 i 229 0i
216 1.91 E+03 2.69E-08 1 230 0~217 i 1.92E+03 ! 2.70E-08 i 231 0 j
218 1.93E+03 2.72E-08 232 0 1
219 i 1.94E+03 2.73E-08 1 233 i 0220 1 1.94E+03 ! 2.74E-08 i 234 0221 i 1.95E+03 1 2.75E-08 i 235 0222 1.96E+03 i 2.77E 08 236 0223 1.97E+03 i 2.78E 08 t 237 i 0,
224 1.98E+03 i 2.79E 08 i 238 i 0225 1.99E+03 i 2.30E 08 I 239 i 0-
226 2.00E+03 2.82E-08 1 240 1 0-
>
227 2.00E+03 2.83E-08 i 241 i 0228 2.01 E+03 2.84 E-08 i 242 1 0229 2.02E+03 2.85E-08 243 y 0230 2.03E+03 2.87E-08 244 04
231 2.04E+03 2.88E-08 245 1 0
_232 2.05E+03 .., 2.89E-08 246 ! O I, ,_
.233 2.06E+03 2.90E-08 247 0'
234 2.07E+03 2.91 E-08 248 ! 0235 2.07E+03 2.93E 08 249 0,
236 2.08E+03,
2.94E-08 250 0
|
. Page 5
. .- - .. .
.
*!
| Attachment 1 || PSL-1FSN-96-001, Rev. 0 <
l
! i
237 2.09E+03 2.95E-08 i 251 i 0*
238 2.10E+03 i 2.96E-08 1 252 1 0 |
; _ 239 i 2.11E+03 | 2.98E-08 253 i 0 |240 2.12E+03 2.99E-08 254 i 0 ;
241 2.13Ev03 3.00E-08 255 0 {242 2.14E+03 3.01E-08 256 0243 2.14E+03 3.03E-08 257 0 1
244 2.15E~ 03 3.04E-08 258 0 )+
245 2.16E+03 3.05E-08 259 0246 2.17E403 3.06E-08 260 0247 2.18E+03 3.075-08 261 0.-
248 2.19E+03 3.09E-08 262 0249 2.20E+03 3.10E-06 263 0250 2.21 E+03 3.11 E-08 264 0251 2.21E+03 3.12E-08 265 0252 2.22E+03 3.14E 08 266 0253 2.23E+03 3.15E-08 267 0254 2.24E+03 3.16E-08 268 i 0255 2.25E+03 3.17E-08 269 i 0256 7 2.26E+03 ~~ 3.18E'08 270 i 0257 2.27E+03 - ! 3.20E-08 271 i 0258 2.28E+03 | 3.21E-08 272 i 0259 2.28E403 3.22E-08 273 0260 2.29E+03 3.23E-08 274 0261 2.30E+03 3.25E-08 275 0262 2.31 E+03 ! 3.26E-08 276 0263 2.32E+03 3.27E-08 277 0'
~264 2.33E+03 i~ 3.28E 08 278 i ~~~~67265 2.34E+03 3.30E-08 279 1 0266 2.34E+03 3.31 E-08 280 l 0267 | 2.35E+03 i 3.32E-08 281 1 0268 2.36E+03 3.33E 08 282 0'
269 2.37E+03 3.34E-08 283 1 0'
270 2.38E+03 i 3.36E-08 284 1 0271 2.39E+03 3.37E-08 285 1 0272 2.40E+03 3.38E-08 286 ! 0
273 2.41 E+03 3.39E-08 287 i 0274 2.41 E+03 3.41 E-08 288 i 0275 I 2.42E+03 3.42E-08 289 i 0276 i 2.43E+03 3.43E-08 | 290 i 0277 i 2.44E+03 3.44E 08 i 291 t 0278 2.45E+03 3.45E-08 i 292 .0,
279 | 2.46E+03 3.47E-08 j 293 0
280 2.47E+03 3.48E-08 6 294 0281 2.48E+03 3.49E-08 i 295 0
282 2.48E+03 3.50E-08 j 296 ! 0; .
283 2.49E+03 3 52E-08 i 297 0|
| 284 2.50E+03 3.53E-08 ! 298 0
|- 285 2.51 E+03 3.54 E-08 299 0286 2.52E+03 3.55E-08 6 300 0
i
j Page 6
. . ._ -. .- . . _ - _ - _ _ - - .- --. - - ~ _ - - .. _ -_ .__ .
*.
.
AttachmInt 1PSL 1FSN.96-002, Rev 0 t
4 P
.
287 ! 2.53E+03 3.57E-08 1 301 0288 | 2.54E+03 i 3.58E 08 1 302 0
289 J 2.54E+03 3.59E-08 303 0290 2.55E+03 __ 3.60E-08 304 0
,
291 2.56E+03 3.61E-08 305 03
292 2.57E+03 3.63E-08 306 0*
'
: 293 2.58E+03 3.64E-08 307 0294 2.59EM3 3.65E-08 308 0
'
295 2.60E+03 3.66E-08 309 0-
,
j 296 2.61E+03 3.68E 08 310 0297 2.61E+03 3.69E=08 311 0
-
298 2.62E+03 3.70E-08 312 0299 2.63E+03 3.71 E-08 313 0
=
; 300 2.64E+03 3.72E-08 314 0: 301 2.65E+03 3.74E-08 315 0
*
) 302 2.66E+03 3.75E-08 316 0303 2.67E+03 3.76E-08 317 0
I 304 2.67E+03 1 3.77E-08 318 0305 2.68E+03 j 3.79E-08 319 0
4 306 | 2.69E+03 i 3.80E-08 320 0'
j 307 2.70E+03 1 3.81 E-08 321 0308 2.71 E+03 I 3.82E-08 322 0309 | 2.72E+03 3.83E-08 323 0310 2.73E+03 3.85E-08 324 0
4 311 2.74E+03 3.86E-08 325 0;
312 2.74E+03 3.87E-08 326 0313 2.75E+03 3.88E-08 327 0 I
314 ! - 2.76E+03 3.90E-08 i 328 0315 i 2.77E+03 i 3.91 E-08 329 0,
316 i 2.78E+03 I 3.92E-08 330 0.
317 ! 2.79E+03 i 3.93E-08 331 0l
'; 318 2.80E+03 3.94E-08 i 332; 319 ! 2.80E+03 ! 3.96E 08 1 333 0! 320 2.81E+03 i 3.97E-08 I 334 0i
321 1 2.82E+03 i 3.98E-08 i 335 0322 2.83E+03 3.99E 08 j 336 0.
323 1 ' 2.84E+03 4.01 E-08 j 337 0324 | 2.85E+03 4.02E-08 i 338 0325 2.86E+03 4.03E-08 i 339 0,
326 2.87E+03 i 4.04E 08 i 340 0327 2.87E+03 4.05E-08 341 0328 2.88E+03 4.07E-08 342 i 0329 2.89E+03 4.08E-08 343 i 0330 2.90E+03 4.09E-08 344 i 0 !331 2.91 E+03 4.10E-08 345 i 0 '
332 2.92E+03 4.11 E-08 346 1 0 |'
+
333 2.93E+03 4.13E-08 347 0'
334 2.93E+02 4.14E-08 348 i 0335 2.94E+03 4.15E-08 349 0336 2.95E+03 4.16E-08 350 i 0
Page 7
.
_ _
- _ _ . .
m
All chmInt iPSL 1FSN 96 002, Rev. 0
,
__.____._--'~337 2.96E+03 4.1_8.E-08 ,__ 3 51, _ , _0338 2.97E+03 4.19E-08 352 03T, 2.98E+ 03 4.20E-08 353 0340
_
2.99Et03 _ 4.21 E-08 354 0341 2.996+03 4.22E-08 355 0342 3.00E+03 4.24E-08 356 0343 3.01 E+03 4.25E-08 357 0344 3.02E+03 4.26E-08 358. 0
<
345 3.03E+03 4.27E-08 359 0346 3.04E+03 4.29E-08 360 0347 3.05E+03 4.30E-08 361 0, , ,
_l' 8 3.06E+03 4.31 E-08 362 0349 3.06E+03 4.32E-08 363 0350 3.07E+03 4.33E-08 364 0351 3.08E+03 4.35E-08 365 0352 3.09E+03 4.36E-08 366 0353 3.10E+03 4.37E-08 367 0354 3.11 E+03 4.38E-08 368 0355 3.12E+03 1_ ,,4;39E-08 369 0356 3.12E+03 4.41 E-08 370 0357 3.13E+03 4.42E-08 371 0358 3.14E+03 4.43E-08 372 0359 3.15E+03 4.44E 08 373 0360 3.16E+03 4.46E-08 374 0381 3.17E+03 4.47E-08 375 0362 3.18E+03 4.48E-08 376 0363 3.18E+03 4.49E-08 377 0364 3.19E+03 4.50E-08 378 0365 3.20E+03 i 4.52E-08 379 0366 3.21 E+03 4.53E-08 380 0367 3.22E+03 4.54E-08 381 0368 3.23E+03 4.55E-08 1 382 1 0369 3.24E+03 i 4.56E-08 383 0370 3.24E+03 4.58 E-08 384 0371 3.25E+03 4.59E-08 385 0372 3.26E+03 1 4.60E-08 386 0373 ! 3.27E+03 i 4.61 E-08 387 0374 i 3.28E+03 i 4.63E 08 388 0375 i 3.29E+03 : 4.64E-08 389 0376 1 3.30E+03 1 4.65E-08 390 0
.
377 i 3.31 E+03 4.66E-08 I 391 0+
378 i 3.31 E+03 4.67E-08 | 392 0<
379 t 3.32E+03 4.69E-0C 1 393 ! O380 3.33E+03 4.70E-08 r 394 1 0,
381 3.34E+03 4.71 E-08 1 395 j 0'
3.35E+03 i 4.72E-08 i 396 0382 -
'
383 i 3.36E+03 i 4.73E-08 i 397 0384 3.37E+03 1 4.75E-08 1 398 0385 3.37E+03 4.76E-08 399 0386 3.38E+03 4.77E-08 400 1 0
Page 8
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Att: chm:nt 1,
PSL 1FSN 96-002, Rev. 0'
i
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387 ~ 3'.79E+ 03 4.78E-08 401 ; O |388 3.40E+03 4.80E-08 402 l 0389 3.41 E+03 4.81E 08 403 i 0;
3390 3.42E+03 4.82E-08 404 0 |391 3.43E+03 4.83E-08 405 0392 3.43E+03 4.84E-08 406 0393 3.44E+03 4.88E-08 407 0394 3.45E+03 4.87E-08 408 0395 3.46Elt03 4.88E-08 409 0396 3.47E403 4.89E-08 410 0397 3.48Et03 4.90E,08 411 0398 3.49E+03 4.92E-08 412 0399 3.49E+03 4.93E-08 413 0
!400 3.50E+03 4.94E-08 414 0 '-401 3.51 E+03 4.95E-08 415 0402 3.52E+03 4.97E-08 416 0403 3.53E+03 4.98E-08 417 0 |404 3.54E+03 4.99E-08 418 0405 3.55E+03 5.00E-08 419 0406 3.55E+03 5.01E-08 420 1 0407 3.56E+03 5.03E-08 421 i 0408 3.57E+03 5.04E-08 422 O I
409 3.58E+03 5.05E-08 423 0410 3.59E+03 5.06E-08 424 0411 3.60E+03 5.07E-08 425 0 |
412 3.61E+03 5.09E-08 426 0413 3.61E+D3 5.10E-08 427 0414 3.62E+03 5.11 E-08 428 0415 3.63E+03 5.12E-08 429 0416 3.64E+03 5.13E-08 430 0417 3.65E+03 5.15E-C3 I 431 0418 ! 3.66E+03 5.16E-08 i 432 04
419 ! 3.67E+03 ! 5.17E-08 | 433 1 04?0 ! 3.67E+03 | 5.18E-08 I 434 1 0421 | 3.68E+03 4 5.19E-08 .I 435 1 0
_422 | 3.69E+03 1 5.21 E-08 i 436 i 0423 i 3.70E+03 i 5.22E-08 : 437 i 0424 1 3.71 E+03 i 5.23E-08 i 438 i 0425 l 3.72E+03 i 5.24E-08 1 439 i 0426 1 3.73E+03 i 5.26E 08 I 440 1 0427 3.73E+03 5.27E-08 1 441 ; O428 3.74E+03 5.28E-08 442 ! O
'
429 3.75E+03 5.29E-08 i 443 i 0'
430 3.76E+03 5.30E-08 t 444 i 0'
431 3.77E+03 5.32E-08 445 i 0>
,
432 i 3.78E+03 5.33E-08 6 446 i 0,
433 ! 3.79E+03 5.34E-08 i 447 ! O434 3.79E+03 5.35E-08 448 0>
435 3.80E+03 5.36E-08 449 0436 3.81 E+03 5.38E-08 450 0|
Page 9
-,
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3Attachment 1
PSL 1FSN 96-002. Rev 0,
\'. ,.
437 ( 3.82E+03 1 5.39E-08 i 451 1 0438 i 3.83E+03 l 5.40E 08 1 452 1 0'
439 3 84E+03 1 5.41 E-08 i 453 1 0,
440 3.85E+03 5.42E-08 454 0441 3.85E+03 5.44E-08 455 0
| 442 3.86E+03 5.45E-08 456 0443 3.87E+03 5.46E-08 457 0444 - 3.88E+03 5.47E-08 458 0445 3.89E+03 5.48E-08 459 0448 3.90E+03 5.50E-08 460 0447 3.91E+03 5.515s08 461 0
-
448 3.91E+03 5.52E-08 462 0449 3.92E+03 5.53E-08 463 1 0
| 450 3.93E+03 5.54E-08 464 0451 3.94E+03 5.56E-08 465 0452 3.95E+03 5.57E-08 466 0453 3.96E+03 5.58E-08 467 0454 3.96E+03 5.59E-08 468 i 0 i455 3.97E+03 5.60E-08 I 469 0 I
456 3.98E+03 ! 5.62E-08 i 470 0457 3.99E+03 5.63E-08 471 1 0
'
458 4.00E+03 5.64E-08 472 0 1
459 4.01 E+03 5.65E-08 473 0 |
460 4.02E+03 5.67E-08 474 0461 4.02E+03 5.68E-08 475 0462 4.03E+03 5.69E 08 476 0463 4.04E+03 5.70E-08 477 0464 4.05E+03 5.71 E-08 478 0465 ! 4.06E+03 ! 5.73E-08 479 1 0 I
466 i 4.07E+03 5.74E-08 480 i 0.
467 i 4.08E+03 i 5.75E-08 481 ! O
468 4.08E+03 5.76E-08 482 0469 i 4.09E+03 5.77E-08 483 0470 t 4.10E+03 1 5.79E-08 484 0471 1 4.11 E+ 03 5.80E-08 | 485 0 i472 ! 4.12E+03 5.81 E-08 486 i 0 |473 1 4.13E+03 ! 5.82E-08 1 487 i 0474 4.14E+03 5.83E-OS i 488 i 0
'-
475 4.14E+03 5.85E-08 i 489 0476 4.15E+03 5.86E-08 i 490 i 0477 4.16E+03 5.87E-08 491 0478 4.17E+03 5.88E-08 492 0 !479 4.18E+03 5.89E-08 493 0480 4.19E+03 5.91 E-08 494 0481 4.20E+03 5.92E-08 495 0482 4.20E+03 5.93E-08 496 0
.
483 4.21 E+03 5.94E-08 497 0484 4.22E+03 5.95E-08 498 0 |
485 4.23E+03 5.97E-08 499 0486 4.24E+03 5.98E-08 500 0
i
Page 10
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*1 I
I
AttachmInt 1PSL-1 FSN-96-002, Rev. 0.
. . . . - . - - . . . . . . . . - - . . . - - - -. - - ---. - - - . - - - - - -
487 i 4.25E+03 i 5.99E-08 501 0 |'
488 4.25E+03 | 6.00E-08 I 502 i 0
!{489 4.26E+03 6.01E 08 i 503 0490 4.27E+03 6.03E-08 504 0 |491 4.28E+03 6.04E-08 505 0 ;492 4.29E+03 6.05E-08 506 0 1
493 4.30E+03 6.06E-06 507 0'
494 4.31E+03 6.07E-08 508 0495 4.31E403 6.09E-08 509 0
,496 4.32E+03 6.10E-08 510 0 l''
497 4.33E+03 6.11E-08 511 0498 4.34E+03 6.12E-08 512 1 0499 4.35E+03 6.13E-08 513 1 0500 4.36E+03 6.15E-08 514 i 0501 4.37E+03 6.16E-08 515 l 0502 4.37E+03 6.17E-08 516 I O I503 4.38E+03 6.18E-08 517 ! 0 !504 4.39E+03 | 6.19E-08 i 518 i 0505 4.40E+03 6.21 E-08 | 519 i 0 |
506 4.41E+03 6.22E-08 520 i 0 |
507 4.42E+03 6.23E-08 521 1 0{508 4.42E+03 6.24E-08 522 0
509 4.43E+03 6.25E-08 523 1 {510 4.44E+03 6.27E-08 524 1 j511 4.45E+03 6.28E-08 525 1 l
512 4.46E+03 6.29E-08 526 1
513 4.47E+03 6.30E-08 527 i 1
514 4.48E+03 i 6.31 E-08 1 528 1
515 4.48E+03 | 6.33E-08 I 529 i 1
516 i 4.49E+03 i 6.34 E-08 I 530 i 1
517 ! 4.50E+03 6.35E-08 531>
1'
518 4.5 ? E+03 6.36E-08 ! 532 1i
4
519 ! 4.52E+03 i 6.37E-08 i 533 | 1
520 I 4.53E+03 i 6.39E-08 j 534 ! 1
521 ! 4.53E+03 t 6.40E-08 1 535 1
522 i 4.54E+03 6.41 E-08 536 i 1*-
523 1 4.55E+03 1 6.42E-08 I 537 ! 1
524 I 4.56E+03 i 6.43E-08 I 538 i 1
525 1 4.57E+03 6.44E-08 i 539 i 1
526 4.58E+03 6.46E-08 I 540 i 1i
527 4.59E+03 6.47E-08 541 1
528 4.59E+03 6.48E-08 542 1-
529 4.60E+03 6.49E-08 543 1
530 4.61 E+03 6.50E-08 544 1
531 4.62E+03 6.52E-08 545 1>,
532 4.63E+03 6.53E-08 546 ! 1'
533 4.64E+03 6.54E-08 547 1
534 4.65E+03 6.55E-08 548 1
535 4.65E+03 6.5EE-08 549 1
536 4 66E+03 6.58E-08 550 1
Page 11
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|
|. Attachment 1_ PSL 1 FStJ-96-002, Rev_._0. _,, _
-
537 1 4.67E+03 i 6.59E-08 1 551 1
538 4.68E+03 6.60E-08 552 1
539 4.69E+03 6.61 E-08 553 1
540 4.70E+03 6.62E 08 554 1
541 4.70E+03 6.64E 08 555 1
542 4.71E+03 6.65E-08 556 1 ;543 4.72E+03 6.66E-08 557 1
| 544 4.73E+03 6.67E-08 558 1
545 4.74E+03 6.68E-08 559 1
546 4.75E+03 6.70E-08 560 1
547 4.76E+03 6.71 E-08 561 1
548 4.76E+03 6.72E-08 562 1
549 4.77E+03 6.73E-08 563 1
550 4.78E+03 6.74E-08 564 1
551 | 4.79E+03 6.76E-08 565 1
552 ( 4.80E+03 6.77E-08 566 11
553 j 4.81E+03 6.78E-08 567 1 i
554 i 4.81 E+03 6.79E-08 568 1,
555 6 4.82E+03 6.80E 08 569 1 )556 i 4.83E+03 6.81E-08 570 1
557 4.84E+03 6.83E-08 571 1
558 4.85E+03 6.84E-08 572 1
559 4.86E+03 6.85E-08 573 1
560 4.87E+03 6.86E-08 574 1
561__ 4.87E+03 _ , _ _6 87E-08 575 _1,.562 4.88E+03 6.89E-08 576 1
563 4.89E+03 1 6.90E-08 577 1
564 1 4.90E+03 6.91 E-08 578 1
565 l 4.91E+03 6.92E-08 579 1
565 4.92E+03 i 6.93E-08 580 1
567 4.92E+03 6.95E-08 581 | 1
568 4.93E+03 6.96E-08 582 1 1
569 6 4.94E+03 1 6.97E-08 583 1 1
570 4.95E+03 i 6.98E-08 1 584 1
571 4.96E+03 ) 6.99E-08 | 585 1
572 i 4.97E+03 i 7.01E 08 586 1
573 4.97E+03 7.02E-08 587 1i
574 4.98E+03 7.03E-08 I 588 1
575 4.99E+03 ' 7.04E 08 | 589 1
576 5.00E+03 7.05E-08 i 590 ! 1
577 5.01E+03 7.06E-08 591 ! 1
578 5.02E+03 7.08E-08 592 1
579- 5.03E+03 7.09E-08 593 1>.
580 5.03E+03 7.10E-08 594 1,
581 5.04E+03 7.11 E-08 i 595 i 1
582 5.05E+03 7.12E-08 i 596 1.
583 5.06E+03 7.14E-08 597 1.
584 5.07E+03 7.15E-08 598 | 1
585 5.08E+03 7.16E-08 599 1+
586 5.08E+03 7.17E-08 600 1
Page 12
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_ _ _ _ _ -_._- _ _ - _ _ __.____ ___. ._. _
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j.| ,- A He< % 4 2 4 PSL- 2Fw-9f-cc.1, Au
Pa 1/2| - - . - _ . --_ _ . . _ _ _ _ _ __ _ _ _
_ .,_ _ La___.
FROM: D.H. Faulkner DEPT: CHEMISTRY
SUBJECT: Normal Unit 1 Reactor Coolant Rb 88 and Xo 133 Values
UNIT 1 REACTOR COOLA'NT SAMPLE ANALYSIS;
Aaivity reported in uCi/cc." <
SAMPrR DATE/ RIME RB 88 XE-133
26-SEP-1996 09:05 1.98E 01 2.86E-031.75E-01 2.47E 0324-SEP-1996 09:05 -
22-SEP-1996 00:50 1.78E-01 2.72E-03
12-SEP.1996 08:48 6.51E-02 1.64E-03 .'
10-SEP-1996 06:50 5.46E-02 1.29E-03-
8-SEP-199614:10 1.01E-01 1.39E-03
6-SEP-1996 08:45 6.70E-02 1.48E-03
5-SEP-1996 08:30 4.22E-02 1.16E-0331-AUG-1996 22:20 2.57E 03 3.45E-0331-AUG-1996 01:50 1.62E41 2.65E 0327-AUG-1996 02:20 1.10E-01 2.09E-0325-AUG-1996 00:50 1.11E-01 2.03E-03
23-AUG-199610:20 1.80E-01 2.87E-03
21-AUG 1996 09:45 1.48E-01 3.33E-03
20 AUG-199610:25 1.26E-01 2.92E-03
18-AUG-1996 01:40 1.72E-01 2.37E 0317-AUG-1996 01:30 3.24E-01 2.55E-03
16-AUG-1996 08:45 2.38E-0? 3.29E-03
'Ihese values represent typical activity levels for this time in core life and with littleor no fuelleakage.
If you have any questions or need more data, please contact me.
Thanks,
Dave FaulknerChemistry Supervisor
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!* STEAM GENERATOR _.
| REPLACEMENT PROJECT! -
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PROGRESS REPORT; MARCH - APRIL 1996'
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General.
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The Steam Generating Team (SGT)
*
B&W Canada Steam Generator Fabrication
Engineeringi
| Quality
Replacement Outage Preparation
i !' Attachments:
ISGRP Budget Status - Capital Dollars ''
'
SGRP Budget Status - O&M Dollars1
1 Summary Bar Chart for SGT,
'Engineering / Design Pkg. Development Status Graphs
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Construction Work Pkg. Development Status Graphs.
Steam Generator Fabrication Status SchematicSummary Bar Chart for B&W4
I Photographs |.
Steam Generator Replacement Outage Schedule ;,
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eseep . m,. * .=e e m_
b| ... .....-. , ~ ....:. ,- ~ ;.L. : "~~'~ ~ --
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ST. LUCIE UNIT I SGRP IllGilLIGilTS REPORT |-
~ _ MARCII - APRIL 19%. j
GENERAL
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The MK-F contract organization responsible for engineering, procurement and construction has been |
renamed. The previous organization ,was comprised of Morrison Knudsen (MK), Duke Engineering(DE&S) and Framatome Technologies (FTI). "Ihe new organization is called the Steam OvneratingTeam (SGT) and is a 50/50 partnership between MK and DE&S. Each of the three entities is stillresponsible for the same scope as before. MK is still providing overall project and construction
.
management while DE&S is providing design engineering an licensing support. FTI continues to )provide technical services for reactor coolant pipe measurements, decontamination and RCS pipe Imachining / cutting and narrow groove pipe welding.
TIIE STEAM GENERATING TEAM (SGT, Ltd) l
The structural steel and bolts for the Main Steam Trestle PCM have been delivered.
Engineering completed review and preliminary approval of work packages which have incorporatedFRG comments.
SGT is continuing to interface with Mammoet, the rigging contractor, to review heavy lift / riggingdesigns and resolve comments.
MK-F SUBCONTRAGTOR SUMMARY
SUBCONTRACTOR SERVICF1 MATERIAL STATUS
1 Davenport Mammoet Steam Generator Rigging and Engineering2 Transco Products Inc Transporting Development3 LAW Engineering- Steam Generator insulation Engmeering
OSG Storage Facility Soil Boring DevelopmentCompleted
4
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ST. LUCIE UNIT I SGRP IIIGIILIGIITS REPORT*
MARCII - APRIL 1996
B&W CANADA STEAM GENERATOR FABRICATION
Curwnt Statusi
Assembly of the heat exchanger sectio'ns in Cambridge, Ontario is nearing completion. Aftercompleting the machining of base supports, the units will be cleaned, closed, nitrogen filled andprepared for shipment to Mt. Vernon, Indiana where final manufacturing and assembly will take )place.
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1
1The new steam generators will arrive on site prior to June 1,1997. '
The table below shows that five of the six new contract milestones have been completed ahead ofschedule. All other B&W activities are also proceeding ahead of schedule.
B&W MILESTONE STATUS
-
M/S S/G MILESTONE STATUS TARGET ACTUALNO. NO. DESCRWrION COMPLETE COMPLETE j
i #1 Final Weld Repatr - Weld #4 (Stay Cylinder to 2/1/95 12/24/94Pnmary 11 cad).
2 #2 Weld ID Seal Pass - Weld #4 (Stav Cylinder to 2/1/95 11/18/94 '
Pnmary Head)-|
3 al Complenon of Pnman llead to l'ubesheet to Shell 5/9/95 2/28/05Assembly Welds through MT repairs of Support
4 Base to Shell Weld;
a: Completion of Primary Head to Tubesheet to Shell 7/5/95 4/14/055 Assembly Welds through MT repatrs of Support6 Base to Shell Weld
Both Completion _of Tube to Tubesheet Seal Welding 6/l1/96 !6/06Roth Final Delivery of S/G's at PSL 6/1/97
M:iior Accomplishments
Cambridge, Ontario - lleat Exchangers
First Unit Lower Assembly- Com,pleted hydrostatic test of primary side
Completed post hydro UT exammation-
Completed eddy current testing of heat exchanger tubes.-
- Machinine of base support is in progress
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ST. LUCIE UNIT 1 SGRP IIIGIILIGitTS REPORT~ ~~
--MARCII -APRIIr1996 -- - - - -.
Second Unit Lower Assembly- Completed hydrostatic test of primary side.- Completed post hydro UT examination.- Completed eddy current testing of heat exchanger tubes.- Machining of base support is'in progress.
Mt. Vernon, Indiana - Steam Drums
First Unit Steam Drums- Completed all PWHT NDE.- Drum has been upended for assembly of intemals.- Completed installation of secondary deck seal skirt and
primary support skirt.- Completed welding gooseneck to feedwater header.
Second Unit Steam Drums- Completed all PWHT NDE.- Completed installation of sec. manway covers and linkages.-
Intemals- All Ove separator modules are assembled for both units.
ENGINEERING
FPL has been working closely with B&W in the review and acceptance of the B&W EngineeringReports. These reports cover all performance, stress and design issues. There are only five reports
Iof the 26 t,otal that are still outstanding. The final report is the wrap-up ASME Design Report ,which will be issued 12/1,96.
B&W's transportation plan for shipment of the heat exchangers from Cambridge, Ontano to Mt.Vemon Indiana was reviewed during a Design Review. One of the actions that resulted was thatFPL will perform a manne survey of the channel depth from the intracoastal waterway to the bargeslip after the 1996 hurricane season. In addition, FPL will do a depth survey of the area west of thesi p, which will be used as the unloading area
The steam g[enerator disposal effort requires a characterization of both the extemal dose rate and theradioisotope content of the primary side. Dunng the current outage, radiation profile surveys wereperformed and will be sent for radioisotope analysis of the cleaning material used during tubepluggmg. The information will be transmitted to the vendors for fmal bid development. Bids areexpected by August 1,1906
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. ST. LUCIE UNIT 1 SGRP IIIGIILIGIITS REPORT i
. _ _
MARCII - APRIL 1996 |
OU AIIIT l
Surveillance continued at both the Mount Vernon and Cambridge manufacturing locations.|
Acceptable RSG quality was evidenced at both locations. The eddy current test cycle was completed |
for both RSGs. The results are that the tubes are acceptable, crevice depth is acceptable, no missed,
Gxpansions, and no tubes required plugging. All tolerances were in accordance with the applicabledrawings.
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REPLACEMENT OUTAGE PREPARATION
Attached are preliminary schedules of the activities leading up to the outage and the breaker tobreaker outage schedule. l_
1.
i
Distribution: j
T.F. Plunkett i|J.A. Stall
W.H. BohlkeK.R. Craig -
,
C.L. Burton |D J. DenverH L. FagleyJ W Connor
: J. MarcheseC.A. PellJ.C. ScarolaC.D. MarpleSGRP
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- ST. LUCIE UNIT I- SGRP BUDGETSTA TUS - CAPITAL DOLLARS
._ ..
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-| |' N ! $ | U 9fi
6.000 y * - - 20.000
_?s 18.000
!<
' MONTHLY BUDGET ' I=
5.000 ' mMOhHLY ACTUAL'9 * CUM DVDGET
.1 a16 000*
_ _ |+ CUM, ACTUAL,
>- , g14 000 >y * G, .iu.__.____.._._. _ - . _ _ _ _ . . _ __ o _ ._. 5,z ,o 3
b #o, :s12.000 3
m # Bg a m#
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{e 'g a non g10 000m i aO s am Og ,' - e 000 gfn .D 5,
g ,000 m __ __ _ __ _ ., _. _ . . . _ _ _ _, gE ,' e.000 g,
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($000)CURR MONTH YR TO-DATE TOTAL TO-DATE YR-END FCST
BUDGET $752 $3.968 $65.209 S18.881ACTUAL /FCST $407 $1.373 560.892 $13.033VARIANCE ($345) ($2.5,95) (54.317) (55.848)
|Significant contributors to the Year-To Date budget underrun: I
- SGT payment schedule was changed due to the rescheduling of the SGRO fro 9/97 to 2/98 ($1.791 K)Deferred payment for blowdown line analysis done by SGT (5100K)
- Deferred QA/QC contractor support. ($245K)- Neactiated ehrt,unation of BWI scope change for barge transportation of new S/G's. (236K)
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f 'ULCR$EOWDRCv'*CPSRT&SW AR\C AP9t,04 KL.W rem Daie 5/17Ev6 WJC
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ST. LUCIE UNIT I-
SGRP BUDGETSTA TUS - O& At DOLLARS |
1/>R// / 99611
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180 r___
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Project Support eff0Ms are DelOW the 10 Vel estimatea for the 1996 buaget due pomanly to the hoia '
aced on thc 000 Stora3c Facaty iMausc| cum) end tb.c chmination of the Main Steam TrcstlePCM from the 1996 Outaga scope The Mausoleum will remain on hold until August 1996 when it icanticipated tnat the OSG on 'ite storage vs disposal alternative weil be decided upon. The Main iSteam Trc ; tic PCM has becn defctred until the SGRO in 1998. !
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FCcility =-PSL Unit _=.01- System _= 21_, Comp. Type = ID Sub-Type = Gl__Componente PDIS-21-6B Associata= SWITCH UTC: ~Nrme : PRESSURE DIFFERENTIAL INDICATING SWITCH FOR CCW HX 1B STRAINER
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-Facility = PSL --Unit -01 System = 21_ Comp. Type - ID Sub-Type - Gl__Component = PDIS-21-7B Associate = SWITCM UTC:Name : PRESSURE DIFFERENTIAL INDICATING SWITCH FOR TCW HX 1B STRAINERmaza ssan= = - - -- -- -- - - - - - - -_-- -- . . - ----
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Fccility -=- PSL Unit = 01-System =71_ Compr-Type"= ID Sub-Type i=~Gl__Component = FIS-21-9A, Associata= SWITCH UTC:Nama : FLOW INDICATOR SWITCH FOR ICW CCW HX 1A OUTLET_ _ . . . _ _ . . . . _..r- -----ar-- - =a -- . - =
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Facility = P51, Unit =-01 System = -21_ Comp. Type - ID Sub-Type _= Gl__C;mponent= FIS-21-9B Associata= SWITCH UTC:
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TIMD034 .RAME. L' O4/18/96 17:04'
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Pacility-- -PsL%it = 02 system = 21_ -Comp. Type - ID sub-Type e G1;Component = PDIS-21-25-1A1 Associate = SWITCH UTC:Name : PRESS DIFF INDIC SWITCM FOR SEAL WAT C SUPPLY STRAINER SS-21-3Al~g33333333333333---__m m_ -- .. -- . ...-_____6.-,. ---
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FGcility_= PSLCCaponent= PDIS-21-25-1B1_ Unit = 02.__Systen.=_21______ comp._ Type =-ID Sub-Type --G1;
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F0cility =-PSL-4 nit = ~ 02 System _=_21_ Comp. Type = ID Sub-Type = G1Component = PDIS-21-25-1B2 Associata= SWITCH UTC:Name : PRESS DIFF INDIC SWITCH FOR SEAL WATER SUPPLY STRAINER SS-21-3B2_
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Facility =- PSL-Unit = 02 System---21_ - Comp. Type - ID Sub-Type = c1 ;Crmponent= PDIS-21-6A Associata= SWITCH
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Facility = PSL -- Unit = -02 -System =-21_ Comp. Type = ID Sub-Type = Gl__ |!
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Facility = -PSL - Unit = 02_ System _=_21_ Comp._ Type..=.ID Sub-Type _=.Gl__Ccponent= PDIS-21-7A Associate = SWITCH UTC:
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Facility * PSL -Unit = O2 System = 21, Comp. Type = ID Sub-Type = Gl__,
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Facility = PSL-- Unit = 02 System = 21_- Comp. Type = ID Sub-Type-= Gl__Cccponent= FIS-21-9A Associate = SWITCH UTC:Ncte : FLOW INDICATOR SWITCH FOR ICW CCW HX 2A OUTLET
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FOcility = PSL Unit = 02-Component = FIS-21-9B ~
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ACTUATION UNITS #1-1 I N/A B-
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The Steam Generating Thama me m u. em w. ca,,,,,,
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October 14, 1996 'r 96-SGTF-027 I.-
Mr. Richard SiposProject ManagerFlorida Power & Light Company -
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SGR/PSL -
P. O. Box 128Ft. Pierce, Florida 34954
Subject: SGR Monthly Progress Report - September, 1996
Dear Mr. Sipos:
Enclosed is the September, 1996 Steam Generator Monthly ProgressReport.
If you have any questions or comments, please contact me at (561)468-4331.
Sincerely,
I [4 $6 .
Martin D. C pkauskasPresident
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MDC: rap
Enclosure
cc: W.A. Fox - ''E&S weFile 11-1 w/
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TABLE OF CONTENTS
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I. MANAGEMENT SUMMARY_
II. ORGANIZATION,
. III. SCHEDULE STATUS '
Pre-Outage Overview Milestones
Pre-Outage Schedules
SGT PCM/DP/WP Status
IV. SEPTEMBER ACTION ITEMS LIST
V. PIIOTOGRAPliS
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The SGT: .11K/DE,ts,
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ST. LUCIE PLANT - UNIT 1.
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STEAM GENERATOR
REPLACEMENT PROJECT
MONTHLY P~ROGRESS REPORT
SEPTEMBER 1996
This document was prepared specitically for the CONFIDENTIAL use of the SGT of N1orrisonKnudsen and Duke Engineering & Services management and should be treated as such.
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SECTION I
. MANAGEMENT SUMMARY
A. OVERVIEW OF PRO.IECT !
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NTEAM GENEllATOlt itEl'l.ACEMENT The M;T: M K/l)E&S,
\T. l.It 'll: /*l..|NT - IWIT I Al(DNTill.Y PROGRILW REPORT |1
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MANAGEMENT SITMMARY |
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A. Proicci Overview |
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The St. Lucie Steam Generator Replacement Project is being perfonned for Florida Power & Light by |1
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the Steam Generating Team (SGT), a limited 50/50 partnership between Morrison Knndsen (MK) and|I
Duke Engineering & Services (DE&S). MK is providing overall project and construction management.
DE&S is providing design engineering and licensing support. Framatome Technologies (FTI). now a |.
|subcontractor is providing technical services for steam generator reactor coolant pipe mensarements,
decontamination. RCS pipe machining / cutting and narrow groove pipe welding. )||5
The project is located on Hutchinson Island. south of Ft. Pierce Florida. The brief scope of services ,
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being provided to FPL by the SGT is engineering, procurement, and construction services for the ;
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!replacement of 2 Combustion Engineering steam generators with 2 BWI steam generators fabricated!
m Canada.
This is the lith monthly progress report issued for the Phase 2 or the SGR implementation phase of j
the pro.ieet and covers the period liom August 26,1996 through September 29. 1996. l'hase 2 hasi
been defined as the period from the beginning of November 1995 through project completion or the end
of December loo? The scope of Phase 2 i3 procurement of implementation materials, constructioni
worklorce mobihzation. erection of outage facihties. receis e and prepare the new steam generators for
mstallation. mockup trainmg. and the actual team generator replacement..
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SECTION I
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NIANAGEMENT SUMMARY
11. 31A.JOR ACCOMPLISIIMENTS
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NTEAM GENERATOR HEPLACEMENT The SGT: M K/DE& S,
ST.1 tir1C PLANT . IINIT I .stDNTilLY PROGREW REPORT. _ . . _ _ _ . _ ... -- . _ _ _ _ _ . _
MANAGEMENT SUMMARY|i
H. Maior Accomplishments|
Major Accomplishments for current period include:.
* Process FPL/BWI controlled documents as they are received.
The QC services contract change has been negotiated with FPL (verbal approval).
' '' Construction Work Package Status: (89 Total identified. 4 New)
Internal Review by Team: 89FPL Review / Comment: 89FPL Approved: 87On Hold: 1 (Painting)-(See Status Report)
Overall, CWP effort'is approximately 98% complete.
FpL will not build the OSGSF, OSG's to be shipped off site (verbal).''
^Mammoet performing detailed engineering, fabrication & procurement to supportOctober 20.1997.
Transco is proceeding to support October 20. 1997 outage. SGT & Transco are'
discussing insulation installation options. Negotiations to begin January 1997 forinstallation of insulation.
Special Processes teutting, machining & welding) out for quotation.
SGRP Project Review Meeting held 4/23/96.'
Engineering / Licensing
Contmued interfacmg with Mammoet to review design informanon and resolvecomments. Review mg Mammoet shop drawings.
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13ecan plannine engineering / licensing activities and resources necessar,s to support theSGRO rescheduled from begmning m early 1998 to October 1907
Conducted general project aeovities te c. project management. document control).
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NTEAM GENEltATOR REl'I.ACEMENT The SGT: MK/DE&S.
VT IITIE l't. 8 %T 1%IT I A10NTill.Y PROGRl;ss REPORT~~ - --- -
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MANAGEMENT SUMMARY
B. Maior Accomplishments - Cont'd
Work planned for October includes:.
Management / Pre-Construction -
FPL to amend contract to incorporate QC services.
SGT to prepare. review and issue " FRAG" net schedules for pre-outage"
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Project Review meetine with FPl. !'
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Deploy Ollice Engineer to the SGT Site Office to suppon pre-outage activities.
Review Transco installaiion option, negotiations to proceed January 1997.1
|SGT to mobilize Project Control Engineer to site to suppon pre-outage planning ja
activities.~
Engineering / Licensing
Plan engineering / licensing activities and required resources to suppon the'
SGRO rescheduled from beginning in early 1998 to October 1997.
Deploy Design Engineer to SGT Site Office to suppon planning for the October1997 SGRO.
Continue interface with Mammoet as necessary.'
Condnct general project activities ie.g. project management. document control).1
Continue to resiew and approse mtert' aces for BWI RSG tirawines as they are: ecen ed.
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SECTION I-
MANAGEMENT SUMMARY1
- C. ITEMS OF CbNCERN !|1
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STEAM GENERATOR REPLACEMENT The .NGT: MK/DE&S |.
}* ST. Li'CIE h.wT . LINIT I AIONTHLY PROGRESS REPORTI'
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! MANAGEMENT SUMMARYl
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!- C. Critical items of Concerns'
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The Steam Generator Replacement Outaae date needs to be defined. - The present target- - -
date is October 20.1997. This has changed from Feb. 3.1998,
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SECTION I,
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MANAGEMENT SUMMARY
D. SUBCONTRACTOR SUMMARY
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\1 1 I I Il /*l t N I 1%Il i AltlN11tl i' l'MIHo*RI %.V RI l*tlHl'. _ _ . _ _ - _ _ . - -
MANAGEMENT SUMMARY.
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D. Subcontractor Summarv.
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SUBCONTRACTOR SERVICE / MATERIAL STATUS
)' Davenport Mammoet Steam Generator Detail EngineeringRigging / Transport for rigging evolution
proceeding
Transco Products, Steam Generator Preparation ofl u c. Insulation engineering
documentation to; support release for! fabrication:
LAW Engineering OSGSF Soil Boring Completed; Contract closed4 Special Processes Request for Proposal
issued tosubcontractors
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- SECTION II
ORGANI7ATION1
A. PHASE 2 ORGA NIZATION CHARTS.
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ST. LUCIE STEAM GENERATOR REPLACEMENTPHASE 2 ORGANIZATION
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FPE 5GRPPROJECT MANAGER
Richard Sipos_,
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Projeci~~~ Project Quality |2_| Manager Director ----------- Manager (Acting) !
! Sharon Williams Marty Cepkauskas Andy Walcutt !
Group Welding-,
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Engineeri Alan Artayet
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ENGINEERING TECHNOLOGY CONSTRUCTION Manager (DE&S)| | Mark Sangeri
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Design Process Technology Site Projecti Engineering / licensing Project Manager Manager
| Manager Max BinghamBill Fox;
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ST. LUCIE STEAM GENERATOR REPLACEMENTPHASE 2 ORGANIZATION
SITEPROJECT MANAGER
Max Bingha_m_:
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CONSTRUCTION . PROJECT CONTROLS CONSTRUCTION ENGINEERINGMANAGER | MANAGER I I
Stbve Mager | Glen Bickel _ . _. Rob Pommerening !!
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^5iT5 D55 IGA OFFIC5 FIELD $NGINEERINGENGINEERING / LICENSING ENGINEER ENGINEER i ;
MANAGER Hyde Griffith Dale Vest Bob Herod,
[ _. . Bill Fox _ i
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: ST. LUCIE STEAM GENERATOR REPLACEMENTENGINEERING & LICENSING'
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PHASE 2 ORGANIZATION
DESIGN ~5M5iNE5 RING /LIC5NSINGMANAGER
Bill Fox_ . _ _ _ _ . _ _
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. PROJECT QUALITY DESIGN QUALITY PROJECT
MANAGER MANAGER - - - - - - - - ENGINEERMark Sanger Mike Anthony
Andy Walcutt (Acting [.
SIT 5 ENGINE 5R
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Hyde GriffithTECHNICAL
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SUPPORTRandy _Ab_ernethy
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SUPPORT CIVIL / STRUCTURAL PIPING /SR MECHANICAL LICENSING'i Mark Ceralch' Dan Grundman Rick Parler Stan McDowell Larry Davis
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| ST. LUCIE STEAM GENERATOR REPLACEMENT:
PROCESS TECHNOLOGYPHASE 2 ORGANIZATION
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:PFiOdE5S TECANdLOdY| PROJECT MANAGER!
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PERFORMANCE /STARTUP TESTINGMANAGER ENGINEERING MANAGER ;MANAGER j
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MEASUREMENTS MACHINING WELDING ENGINEERING DECONTAMINATION >!MANAGER MANAGER' MANAGER MANAGER '
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SECTION III
SCIIEDULE STATUS.
A. PRE-OUTAGE SCHEDULES
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STEAM Gl'NEl(ATOl{ |(El't,ACEMI'NT The SGT: MK/DE&S..
NT. l.IlflE Pl.,4NT - !! NIT I410NTillt' PROGRESS REPORT
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i B. Pre-Outane Schedules
| The Pre-Outage schedule included has been divided into 5 major categories of work,Engineering, Licensing, Procurement FPL Responsibility, and Pre-Outage Construction.
! Pre-Outage construction activities include facility erection, craft training, receive and prepare..
the new Steam Generators.
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01 Lu vlL t-f ttVU l/AOC UuttW!t tf8 ,
KEY MILESTONES1L92 1993 1994 1995 1996 1991 i
4th 1 st | 2nd | bi | an.egy j {}s{ j, 2nd i 3rd [ em t st j 2r'd | 3rd j 4:n 1 st | Jd _ |_ 3rd _ j | 2nd | 3*d jsth 1st
4 Cordract Award ;
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+ Begin Prepare Project Procedures / Work Packagesi . |' + Begin Ucensing Report
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e Spring 1993 Outage / Data Collection Complete,
!i+ Begin Engineering Design Packages
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eissued SASE / SGRR Revision 0i
Fall 1994 Outage / Verification Completee
!* Engineering Packages Complete
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j e Work Packages Complete i
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e FRG Reuew of PC t1 Complete |i
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e Phase 1 Complete
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!, + Begin Revision OA/QC Scope !
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Complete Revision OA/OC Scope + |,; , j
+ Unioad New SG's!!
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Begin CAB Erection +|
Begin Outside Gantry Footngs +
.' |Mobilize SGT Final +
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!Begin SGR Outage +
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:'.: .:.... ~0T LUCIE SGRP - SGRO- 10/97 R09 96.
::: . .. :" w n .. .. ... uorrison xnuesu::.: ..:: :: . .> PRE - 0VTAG E < - -" "-
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i tetet ettei esist effet teint i
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ST. LUCIE SGRP SGRO. 10/97 .R09.96 :-.... . ....... uorrison xnvesen.... e..~. ~.. "..... .. .....
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"' . '.' 2....- ST. LUCIE SGRP SGR0: 10/97- R09 96 !'
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I::::n..!*':U:......... Morrison Knudsen .:t.. .. " . . :: ::" " ~ _ -> PRE - 0UTAGE <--::::-
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IOf91 01101 94f01 9T701 a19701 |
98 97 97 97 17 >
12:00A 12:09A 12'O9A fll Ill:iliffti - 15Illi tillil III:!I 12:004 12:60A' '~
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hiiii li::tii il Cetlit fi,C1 Us!i si !! 11 it til !:ll II It i(I ill rT-~~
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SGT PCM/DP/WP STATUS,
Type # Description Related WP's FRG j__ . _ _ _ - ^^
Approval '
PC/M 151-193 SG 1 A Replacement Modification 2560A,2540A,3020A, 03/22/963061 A. 3081 A
PC/M 152 193 SG 1B Replacement Modification 2560B,25408,30208, 03/22/9630618,3081B
PC/M 153-193 SG 1 A Manway Platform Moo. 1523A 3523A,1560A, 02/01/96 '
3560APC/M 154-193 SG 18 Manway Platform Mod. 15238,3523B,1560B, 02/01/96
r 3560BPC/M 155-193 SG 1 A Blowdown Mod. 1521A,3521A 04/05/96PC/M 156-193 SG 18 Blowdown Mod. 15218,35218 04/05/96PC/M 157 193 SG 1 A insulation Modification 1540A.3540A 04/05/96^
PC/M 158-193 SG 1B insulation Modificaiton 1540B.35408 04/05/96PC/M 159 193 OSG Storage Facility 2080PC/M 194 193 SG 1 A Main Steam Ruoture 2551A.3551A 01/29/96
Restraints ,
'
PC/M 195-193 SG1B Main Steam Rupture 2551B,35518 01/29/96 !Restraints,,'
lPC/M 206 193 Safety injection Line Ruoture Res. 1536 01/29/96 >
PC/M 207 193 Surge line rupture restraints 1535.3535 01/29/96PC/M l 70-194 SG 1 A Supports |2520A.3050A i 02/01/96PC/M 71-194 SG 18 Supports 2520B '3050B 02/01/96 )PC/M 11 195 RCS Pipe Elbow Replacements 3061CA,3061CB
{PC/M 40-195 Main Steam Trestle TG Suoport 1030 01/31/96|SGRR Steam Generator Replacement Rep 08/07/95
SGER Steam Generator Eauivalency Reo 08/21/95DP 2.6 Containment Access Building 2050,4050DP 3.1.1 Containment Jib Conduit 1510.3510DP 3.1.2 SDC MOV 3652 Motor Conduit 1510,3510DP 3.1.3 FCV-25 7 & FCV-25 8 Conduit 1510.3510DP 3.1.5 Steel Const. Hatch Lighting 1510,3510
ConduitOP 3.1.6 Cont. Va. Relief Valve Horst 1510,3510
ConduitDP 3.2.1 RCP 1 A1 and 1 A2 DP instrument 1522A,3522A i
LinesI DP l 3.2.2 Shield Building Ventilation Duct i 1520,3520 i i
} DP 3.2.3 RCP 181 and 1B2 DP Instrument | 15228. 35228Lines I,
DP i 3.2.5 i CVCS RCP Seal iniection Line i1522A.3522A a
! DP i 3.2.6 i Shutdown Cooling MOV V3652 i15228.3522B I i' DP I 3.2.7 l Instrument Air Pioing in Annulus !1522.3522 I |
DP 3.2.9 Service Air Quick Disconnect 1522,3522Pioing
' DP 1 3.2.10 i HVA Cont. Ventilation Duct Risers | 1520,35201 1
i DP~
3.3.1 | Platform on SG 1 A West WMI i1530.3530 i I!
jDP i 3.3.2 1 Platform on SG 18 West Wall i 1530. 3530 l i '
I DP 3.3.3 I Cons. Hatch Platform inside Cont. I 1530. 3530 i i
I DP i 3.3 4 1 Tool Room Area i1530,3530 i
' DP l 3.3.5 I Annutus Structures i 1530.3530 *|
| DP 4.1.1 Shield Building Concrete Const. 1551,3551 j jHatch i '
i DP i 4.1.2 | Cont. Vessel Construction Hatch 6 1550,3550 i. i1'
! DP i 44 I Reactor Cavity Deckino i 1060.5060 i iDP F '1 Steam Ger.erator Of fload 3010A.3010BDP , 5.1.2 | Steam Generator Transport |2570A,25708,3030A,
I | ! l30308.4501.3040A.30408| I I
< ,
DP : 2 ~emnorary Gantrv 'TGi 1031.5031 |CP 5.3 Temocrary Lif tinq Device 1032.5032,
1i DP 54 i Hatch Transfer System i1032.5032 I ii
i DP i 6.1.1 i RCS Hot Lee Piping 1 A Cavity !2530A.3051A | 1Page1
I
9
.
SGT PCM/DP/WP STATUSa
Type # Description Related WP's FRG.__ _ . . - _. _ .._._.~-~ - -
rd~~~
DP 6.1 3 RSC Hot Leo Piping 1B Cavity 25308.30518.
1
DP 6.2.1 SG 1 A Main Steam Piping Temp. 2550A,3070A)S/R
DP 6.2.2 SG 18 Main Steam Piping Temp. 25508,3070BS/R
DP 6.3.1 Feedwater Piping Temp. S/Rs 2550A,3070ASG1A
DP 6.3.2 Feedwater Piping Temp. S/Rs 25508,30700 jSG1B '
DP 6.5.1 SG1 A Primary DP fnstrument Lines 1522A,3522ADP 6.5.2 SG1B Primary'DP instrument lines
1 R 22 P. 3'5 2 28~mDP 6.6.3 SG1 A Second. Water Level inst. 150,4 A, 3522 A
LinesDP 6.6.5 SG1B Second. Water Level inst. 1522B,3522B
LinesDP 7.3 Containment Ventilation i1020,5020DP 7.6 Temporary Electrical Power i 1050.5050
~
WP 1020 installation of Temp HVAC I I
WP 1030 install Steam Trestle Strue. Steel i I|WP | 1031 Erection of temporary TG and HTS I i |
WP ! 1032 Erect TLD inside Containment i I
WP l 1050 Install Temporary Power i |
WP 1060 Install Reactor Cavity Deckinq l
WP 1070 Construction Service AirInstallation
WP | 1510 Electrical Interference Removal IWP 1520 Removal of Perm. HVAC in
ContainmentWP 1521A Remove Blowdown - OSG 1 A 04/05/96WP 15218 Remove Blowdown OSG1B 04/05/96WP | 1522 Small Bore Pipe Rem. In the
| || Annulus | I
WP i 1522A | Remove Small bore SG1 A i | 03/22/96WP I 15228 I Remove Small bore - SG1 B t 03/22/96
| WP | 1523A Remove RCS Piping - SG1 A 02/29/961 Platforms
| WP | 15238 Leakoff tubing rem. . SG1B O2/29/96| I Platforms
WP 1530 i Remove Structural Steel I4
, WP 1535 | Surge Lme Rupture Restraint| 02/29/96
{ l Removal I
! WP 1536 i SI Ruoture Restraint Mod. - SG1 B i j O2/29/96| WP 1 1540A | Remove insulation SG1 A i I 04/05/96i WP i 15408 I Remove insulation SG1B i i 04/05/96j WP | 1550 | Construction Hatch Steel Cap.
I I Rem. .;
"J P 1551 Remove Concrete Hatch i'i
! WP l 1560A 6 Remove Steel Platf orms - SG1 A I O2/29/96WP t 15608 i Remove Steel Platforms - SG1 B 6 i 02/29/96WP 2050 i C AB install i I
'
| WP 2080 i Construction of OSG Storace Fic.1 I'
WP 1 2520A I Aemove Supports - SG1 A I O2/29/96WP i 2520B I Remove Supports - SG1B I O2/29/96.
WP 1 2530A i install RCS Restraints - SG1 A i I
WP 25308 I 'nstall RCS Restraints - SG1 B '
WP 2540A RC Pipe Cuts SG 1 A 03/22/96'i
i
i WP ! 25408 i RC Pipe Cuts SG 1B i i 03/22/96WP i 2550A I Remove Temn. Sec. Restr. . SG1 A I i
's P 25508 i Remove Temp. Sec. Restr. SG1 B ! y.
! WP i 2551A 1 Remove MSSR SGI A i 02/29/96, WP i 25518 I Remove MSSR . SG1B O2/29/96
Page 2
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.
-
SGT PCM/DP/WP STATUSS
-- Type- -# - Description Related WP's FRG_-
ApprovalWP 2560A MS and F/W Pipe Cuts SG1 A 03/22/96WP 25608 MS and F/W Apo Cuts - SG1B 03/22/96WP 2570A Remove / Transport OSG 1 A 03/22/96WP 2570B Remove / Transports OSG 1B 03/22/96WP 3010A Offload SG 1 AWP 3010B Offload SG 1BWP 3020A Prepare and Stage SG 1 A 03/22/96WP 30208 Prepare and Stage SG 18 03/22/96WP 3030A Transport RSG 1 A
_WP 3030B Transports RSG 1B
IWP 3040A Install RSG SG1 A 03/22/96WP 30408 Install RSG - SG1 B 03/22/96WP 3050A Install Supports - SG1 A 02/29/96WP 3050B install Supports - SG1 B O2/29/96WP 3051A Remove RCS Restraints SG1 A -'
WP 3051B Remove RCS Restraints SG1B-
WP 3061A RC Pipe installation - SG1 A 03/22/96WP 3061B RC Pioe installation SG1B 03/22/96 {WP 3061CA RC Pipe Elbows SG - 1 AWP 3061CB RC Pipe Elbows SG 1BWP 3070A install Temo Seendary rest - SG1 AWP 3070B install Temp Secndary rest - SG1BWP 3081J. Install MS/MF SG1 A 03/22/96WP 3081ts install MS/MF SG1B 03/22/96WP 3510 install ElectricalWP 3520 Install Perm. HVAC in cont, and i
'
ann. I
IWP 3521A install Blowdown - SG1 A 04/05/0? jWP 35218 Install Blowdown SG1B l 04/05/96 '
WP 3522 install Small Bore in Annulus iWP 3522A install Small Bore SG1 A i 1 03/22/96WP 3522B Install Small Bore - SG1 B | | 03/22/96 i
WP | 3523A Install SG1 A RC Piping-SG A Plat. I I O2/29/96 jWP 35238 Install Leakoff Tubing V3651 & | | 02/29/96 jV3652 i I
iWP I 3530 install Structural Steel i iWP i 3535 Install Pir Surge line RR - SG1 B l I 02/29/96WP 3540A Install Insulation SG1 A I I 04/05/96WP 35408 install Insulation SG1 B i i 04/05/963P 3550- I Const. Hatch Steel Cao install IWP I 3551A I install MSSR SG1 A i O?/29/96 I
WP l 3551B i install MSSR SG1B i 02/29/96WP | 3560A | SG 1 A Manway Platform install. I O2/29/96WP i 3560B I SG1B Manway Platform Install. ' 02/29/96WP 4050 Containment Access Building
RemovalWP > 4501 i Safetv Load Test I iWP 5020 Removal of Temp. HVAC in Cont.,
BuildingWP I 5031 | Demob TG and HTS i I
WP i 5032 i Demob TLD I IWP i 5050 1 Aemove Temocrary Power j'/ P 5060 Aemove Cavity Deconn
{ WP | 5070 Const. Breathing / Service Air| !
I Removal I
*/ P 6521 P aintinqj
Page 3.
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_
SECTION IV~ |
'
- ACTION ITEMS LIST - SEPTEMBER i
|
.
- _ _ . - _ __
_ _ - .- . _ . . . . .- . . . . - .- - . . .. . - . . . . . - .- . . . . . . . . .
. , ,
i fi '
St. LuCie Steam Genertator Replacement -Team Action List Page t of 6
13-Oct-96
Item No. Activity DATE/ Type / Reference tio ACTION BY NEEDED BY Comments ' Listed Promised Scheduled Closed95100 Procurement Plan MK St. Lucie FPL St. Lucie MK Bill of Materials to be purchased - 5/13/95 1/30/96 1/30/97
Cep auskas Sipos Permanent plant matenal
f.11 G 2/1/95 (Old item 314)
| '
95 104 S(liedule Activities MK Cleveland FPL St. Lucie Revised schedule with 2-3-98 stait date - 4/14/95 7/31/96 9/30/96 |
Sager Cowdrey development continuing - SGT Letter 96- :MF-010 and 96-SGTF-012 4
f.11 G 414! Weefly T.leeting |
|t
I
!
95127 Shy. ping Configuration BW1 CANADA MK St. Lucie RSG final shipping configuration 7/26/95 9/30/96.
Young Cepkauskas
tiO 95 f.1F 093
,
I
95 131 S6H Rescheduled MK St. Lucie FPL St. Lucie 1) Payment schedule revision 2) Outage to 9/13/95 11/30/95 9/30/96 10/30/9610/20/97 reference Ltr 9S-SGTF-026Cepkauskas Sipos ;
i 11 1%I SGRP 95-297e
i
!,
s
_ _ _ _ - - _ _- --_
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Page a of 6St. L,ucie Steam Genertator Replacement -Team Action List
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13-Oct-96
Item Nb. Activity DATEITypf IReference No ACTION BY NEEDED BY Comments Listed Promised Scheduled Closed
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96-001 Bid for Ouality Control Services SGT FPL St. Lucie FPL to issue Change Order to SGT 6/10/96 6/12/96 9/30 mContract - verbal approvalCepkauskas Sipos*
LTl 6-4-96 Letter No Number
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96-00 Temp Gantry Crane (Outside SGT FPL St Lucie Analyze changing the mode restriction from 8/20/96 2/28 97M-5 to M-1RCB) Pommerening Sipos
LTl PSL SGRP-96-085 j
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96-00) SG1 A & 1B MS Rupture SGT FPL St. Lucie Determin0 which actrvities can be started 8/20/96 2/2" ''7
I Restraint - Sieel prior to M-0. Redefine mode restrictionsPommerening Sipos|
accordingly. Break activity into more detail j
LTI! PSL. SGRP-96-085 to determine which activities' can be workedin paratlett
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96-004 SGI A MS Rupture Restraint - SGT FPL St. Lucie Move M 0 to M-5 P'20/96 2/23:'87
Jib Crane Removal & Pommerening Srpos
LTI- PSL-SGRP-96-085
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St. Lucie Steam Genertator Replacement -Team Action List Page 3 of 6
13-Oct-96
Item No. Activity DATE :
1 Type 1 Reference No . ArilON BY NEEDED BY Comments Listed Promised scheduled' Closed96 005 Jib Crane Conduit and Cable SGT FPL St. Lucie - Move from M-0 to M-5 8!20/96 2/28!97 |
Pommerening Sipes
t i! PSI SGRP DG 085,
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96 oil 6 Srb A&B Platforms at 73' SGT FPL St. Lucie Move removal and Replacement from M 0 8/20/96 2/28/97Eleution to M-5Pommerening Sipos
t il PSI SGRP-96 085
96 607 Ait tiimmoet lleavy Equip (TG. SGT FPL St. Lucie Review schedule activities upon completion 8/20/96 2/28/97Skot Trans. It D & Mobile of DP's for possible schedule reductionsPommerening Sipos
and or logic changes1.11 PSI SGRP 96 085
96 008 Ed@ Current Tests of S/G A&B FPL St. Lucie SGT FPL is not performimg tests - completed - 8/2d/96 2/28/97 2/28/97 9/30!97in Veitical Position verbalGross Cepkauskas
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1.11 PSI SGRP-96 085
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P@ M 6St. Lucie Steam Genertator Replacement -Team Action List;13-Oct-96
Item No. Activity DATE *
IType I Reference tio ACTION BY NEEDED BY Comments Listed Promised Sclieduled Closed
96 009 Surge Line Rupture Restraint SGT FPL St. Lucie Move from M-0 to M-5 8/20/96 2/28/97
RIR Pommerening Sipos
!I il P ,L-SGRP 96 085
96 010 Surge Line Rupture Restraint SGT FPL St. Lucie Analyze for possible elimination of this 8/20/96 2/28/97equipment via Leak Before Break Analysis ;Replacement Pommenening Sipos
a 11 l':it SGRP 96 085 !
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96 011 RGB Laydown Areas - Storage FPL St. Lucie SGT Identify the storage locations of equipment 8/20/96 2/28/97included on MK's " Storage Areas for RCG"of Permanent Plant Equipment f.ictaughlin Cepkauskaslist
t il Pdt SGRP 96 085F
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96 012 Siti 1B f.tanway Platfo m - SGT FPL St. Lucie Modify package to show capping leak off 8/20/96 2/28/97.line from V-3652. The leak off line from V- (Remove, Modify & Reptace Pommerening Sipos3651 was capped by Mech Main in 1995
t il 1851 -SGRP 96 085 Outage Move platform reinstattation fromM-0 to M-5.
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St. Lucie Steam Gencrtator Replacement - Team Action List Page 5 of 6
|13-Oct-96
Item No. Activity DATE i
f t pe i Reference No ACTION BY NEEDED BY Comments Listed Promised Scheduled Closedy
96 013 SIG 1 A Manway Platform - SGT FPL St. Lucie The current schedule logic shows 8/20/96 2/28/97reinstallation of the RCS instrument linesRemove. Modify & Replace Pommerening Siposprior to reinstallation of p!atform Change
I il Pbl SGRP 96 085 logic to show a finish-to finish relationship. i
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90 017 Construction Hatch SGT FPL St. Lucie Determine documentation requirements for 8/2d/96 2/28/97
Pommerening Sipos danging the weld process from double tosingle bevel. |
t Il PSL SGRP-96-085|
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90 (119 licavy Litt Lquiprnent Schedule SGT FPL St. Lucie Analyze to identify any conflicts there may 8/20/96 2/28/97be in the use of the Polar Crane. MobilePommerening SiposCrane, etc.
t Il Pbt -SGRP 96-085
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96 020 S. hedule Codes SGT FPL St. Lucie Present plan for coding activities to indicate 8/20/96 2/28/97
Pommerening Sipos Plant System, Work Packages, EP/DP,Area, WBS. Mode, etc
t 11 Pbl SGRP 96 085
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St. Lucie Steam Genertator Replacement -Team Action List Page 6 of 6; 13-Oct-96e
l'em No. Activity DATE I
1 Type I Reference No- ACTION BY NEEDED BY Comments Listed Promised Schedule'd Closed96 021 1IVAC Containment Vent Duct SGT F'PL St. Lucie Move removat and replacement from M-0 to 8/20/96 2/28/97 |
Hisers M-5Pommerening Sipos
I 11 l'SL-SGRP-96-085
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SECTION V,
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PHOTOGRAPHS
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STEAM GENERATOR REPLACEMENT The SGT: MK/DE&S.
ST. LUCIE PL4NT - UNIT I MONTHLY PROGRESS REPORT_ , ... _ . . . . _ _ - . . .- . . . _ _ __ . _
PHOTOGRAPHS
A. - Proiect Photogranhs.
There are no new photos in%)uded for this month's report...
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; _ _ _SGRP/SGT_ STATUS SEETING FORMATi
b.aI. Onenine Remarks - R. Sinos
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II. Point Beach Uodate - M. Ceokauskas 567 F< - . > i- Mo c&
b! /rs o#~s \ .
IILSfsT Reoort1. Project Manager comments: -
2. Pre-outage milestones achieved since last report3. Progress report on upcoming milestones'4. SGT schedule status ,
- Pre-outage |,
j - Outage*
5. What is needed from SG7P )"
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IV. SGRP Reoort )'
1. Project Manager comments(A, e Ps =-2. Pre-outage milestones achieved since last report
(4. Overall schedule status#"'
3. Progress report on upcoming milestones.
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5. V5iat is needed from SGT|
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V. Ooen Discussion |~
1. Review of Action Item Tracking System items not previously discussed! 2. Other issues not previously discussed
VI. Review of Action Items From This Meetinz
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VII. Schedule Next Proiect Review Meeting6
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w \tHUMAN I )_ -OLOyPERFORMANCE EXECUTIVE SUNNARY l
9ENHANCENENT |
, SYSiEM -, _
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1. Nuclear Unit 2. Report Date 3. Report 4. Evaluator.
Plant Unit Time Month Day Year Number Name|St. Lucie 2 1915 02 01 95 95-02 Locke.
5. Event Descriptionn! |
The instrument and Control (l&C) department in conjunction with the Operations and TecFStaff departrnent were performing troubleshooting activities on the letdown system. An i
1&C specialist lifted the leads on the transducer to perform tests on it. After completing ;
these tests, the specialist re-connected the leads to the transducer. Later, when the I i
control room operator attemoted to have the valve take control of letdown, it was,
discovered that the leads had been re-connected incorrectly.i
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6. Human Performance Problems_
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Item Description of inappropnate Action Repeat Consequences
1 Leads landed incorrectly Yes Insufficient letdown j
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7. Etuipment Failure (s) or Condition (s) Affecting Human Performance-
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Descripbon of Equipmert Problem Repeat Consequences
None N/A N/A i
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[k 8 Evert Nanative (Ci.udg; cal Description)p . . _ _ _ _ . . . _ . -_ _
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The letdown system for Unit 2 had been experiencing unstable operations. In an attemp;
to determine the root cause of this problem, troubleshooting activities were commenced.On Tuesday, January 31,1995, Letter Of instruction LOl-T-89 was generated toprovide detailed instruction for the troubleshooting activities on the system. The focus ofthe troubleshooting activities was to be on valves LCV- 2110P and LCV-21100.Operation of these valves is selected from a common hand control switch in the controli
jroom. The switch allows"P", "Q" or "BOTI-f' to be selected for operation.
'1 A tailboard meeting was held involving the Operations crew, the I&C crew and
representatives from Tech Staff. LCV 21100 was placed out of service in preparation foi testing. An I&C supervisor and a specialist went to the Reactor Auxiliary Building (RAB)| with the Nuclear Watch Engineer (NWE) and a Senior Nuclear Plant Operator (SNPO).i The l&C spec lifted the positive and negative leads on E/P-21100 and taped them to| prevent the leads from coming in contact with the case. A static flow scan instrumentj was connected to the E/P and valve diagnostic tests were performed. The flow scan1
instrurnent was disconnected and a 50 ohm resistor was connected in series with thei! positive lead on E/P-2110P. Another piece of test equipment was connected to the E/P! and a stroke test was successfully performed. The test equipment was disconnected
from the E/P, and the two leads were re-connected to E/P-21100. At this time, LCV-!. 21100 was to be placed back in service with monitoring equipment connected to it to
record characteristics with various charging pump and pressure control valvei arrang6TE-nts. The control room was notified that the valve could be retumed to service
The Reactor Control Operator transferred control from LCV-2110P to LCV-21100. LCV-,
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!21100 failed to open as required and charging was secured. After some investigation by
i the I&C personnel, it was discovered that the positive and negative leads on the E/Pi had been re-connected incorrectly. At this point, the testing was secured.I
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! 9. Surnnary of Factors that influenced Htanan Perfomunce !
! Behavioral Analysis - How it happened for each inappropriate action '!
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j Unawareness -The l&C spec who re-connected the leads to E/P-21100 did noti i
i realize that the leads had been connected to the wrong terminals. .I
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10. Summary of Causes,
Causal Analysis - Why it happened for each. inappropriate action _- -
Work Practices - Error Detection Practices - Self checking not applied to ensureintended action is conect -The l&C spec re-connecting the leads did not apply the selfchecking process when the leads were re-connected to the terrninals. The leads hadwire markers designating (+) and (-) on the leads and (+) and (-) was etched into the,
case of the E/P above the teminals. These markings would have provided positiveidentification if they had been checked.
. Work Practices - Error Detection Practices . Independent Verification not perfsnadanr=ctly -The LOI called for an Independent Verification after the leads were re-connected to the E/P. The I&C supervisor assisting in the troubleshooting activitiessigned off the IV after observing the I&C spec re-connect the leads. The supervisorthought that the " level of IV' needed for this job was less than that required for controli
room work or work on sensitive or safety systems. Independent Verification should be a .
truly independent look at the task or step performed, and should have the same level ofh.
detail applied for all plont systems.-
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WHtten Communication - Method of Presentation -Inappewiate emphasis of step orinformation - Step 4.2.24 of the LOI states, " Remove the Transmation, reconnect thepositive and negative leads to E/P 21100 and connect up the valve position recorder fot;
the test." Two spaces are provided after this step; the first for a sign-off by the performer-
; and the second is for I.V. (independent verification) that the step was performed. The ;I&C supervisor stated that when he signed off the IV he interpreted it to be that theleads had been re-connected and that the valve was available to be placed back inservice. In retrospect, he says that for the valve to be placed back in service, the leads [.
would have to be correctly connected,
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11. Evaluator CommentsExplanation of repeat problems, exceptionally good perfomnance noted, etc.
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11 %== tion (doctanents, logs; references, interviews, etc.)._. _.
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2-LOI-T-89 " Diagnostic Testing of Letdown Level Control System" 't
Unit 2 Reactor Control Opuator Chronological Log
Interviews with various plant personnel
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13. PKW Conective Actions,
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1. Procedures or LOls whicn require independent verification should be specific in the |;
step (s) to be taken and v. hat the independent verification means. In this case, the step |'should have directed the spec to land the positive lead on the positive terminal, etc. Thidformat would ensure that the intent of the independent verification is clear.
2. This event should be incarporated in In-House Event Training for all Maintenancei disciplines. Independent Verification should be the focus of the lesson; definition of IV,
|'what management's expectation of IV !s, how IVs are to be performed, etc. (STAR#950342) l
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3. A plant procedure e citled " Independent Verification" has been written to ensure ;
independent Verification by all plant personnel is consistent. A generic review of plant I '
procedures will be performed to identify, and change all definitions of IV to oneconsistent definition. (STAP #950341) i
4. Maintenance Management will assess the knowledge and interpretation of (independent Verification and Self Checking by maintenance personnel After this
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assessment has been ca.ncieted, Maintenance Management and Training will develop |:and provide training as necessary to ensure the level of knowledge and application ofthe Independent Verification process is consistent with Plant Management'sexpectations. (STAR #950242)
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Submrtted: ///l)R$- 4HPES Coordinator ' Date Rev.
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To: Distribution
Subj: PSL POLICY 105 REVIEW; OPERATIONS OF UNIT 1 ON ONE MAIN
TRANSFORMER WITH ITS ASSOCIATED COOLING EQUIPMENT
1. On 4 Sep 1996 a Policy 105 team was assembled to review the power operation of Unit 1 onthe single 1 A Main Transformer with its associated cooling equipment. The team was comprisedof the following members and disciplines:
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J. A. West System Engineering (SRO) Team LeaderR. Raidiris System Engineering _W. Busch Design Engineering .
B. Czachor Operations Support (SRO)S. Patterson Operations Support (SRO)B. Griner Electrical Maintenance TechnicalB. Enfinger Operations Support
2. The following documents were reviewed in support of the subject evolution: 1
Engineenng Evaluation JPN-SPSL-96-0399, Evaluation of Temporary Operating . _ _ _ _-.
Configuration with IB Main Transformer Out of Service
Temporary System Alteration to disable equipment servicing the IB Main Transformer.
while operating on the 1 A Main Transformer
Procedure Change Request to NOP l-0030124,Rev 5, " Turbine Startup Zero to Full.
Load"
3. The engineering evaluation was reviewed for technical content in support of operation of theunit on a single main transformer. The follow observations were made:
Based on a review of the engineering evaluation against the Unit 1 FUSAR it was the*
recommendation that the 50.59 screening be expanded to include a full 50.59 evaluation.Responsibility: Design Engineering
The transformer load curve developed by design engineering required a verification and.
approval by Transmission and Distribution to ensure that the assumptions used in thedevelopment of the curve were conservative and correct., Responsibility: Transmission and Distribution, Design Engineering interface
The operating restriction of" the average temperature of the cooling air for any 24 hour.
period shall not exceed 30 degrees C." Was judged to be to restrictive. It was requestedthe this operational limit be reviewed by Transmission and Distribution.Responsibility: Transmission and Distribution, Design Engineering interface
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~ .~ Tuisole operation on the~1XMain Transformer, it was requested that Operations td:ereadmgs on all available data provided by installed instrumentation on this transformer.
|This data will be taken by use of the data loggers. I
Responsibility: Operations Support in concurrence with Operations|
A precaution to the load operating curve was recommended which is similar to " The main.
generator shall not be operated above 200 MW with the startup transformers in service".
The load operatmg curve "x" should be modi 6ed to include a zero point to ensure there|
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are no human factors concerns throughout the generator loading sequence for the|
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Operators.
Responsibility: Design Engineering, Operations Support
The engineering evaluation should be modified to include an explanation of the load.
operating curve.Responsibility: Design Enginecting
Numerous questions arose surrounding the operations of the isophase cooling system:.
1. If the isophase cooling system were to be blanked off on the IB main transformer whatwould be the effect on the flow to the 1 A main transformer? Will the setpoint for the flow
|switch require a change? Can it be changed with the isophase cooling system in |
operation? Are the any heating effects that we should be concerned with on the B I
isophase side of the cooling?
2. Why can't the isophase cooling system be operated in a normal configuration since theisophase box will no be removed? Is it necessary to insulate the bus link ends? If theymust be insulated with the system in service how will this be accomplished to prevent apossible failure of the isophase cooling system if the insulation should come loose? Canyou have a valid dispatchers clearance ifyou can not verify the air gap on the linksvisually?
Responsibility. Design and System Engineering
A letter is requested from Protection and Control Management which states that a.
thorough review of the intended operation has been conducted and that the properrelaying has been disabled and there will be no effect on the l A transformer operation.Responsibility: Protection and Control, System Engineering interface d
IThe fire d.eluge system supervisor control will be added to the Temporary System.
Alteration.. 1
}The engineering evaluation requires that the oil systera cross-tie valves be closed and I
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locked. It is recommended that it require the valves to be closed and a danger tag be |placed on the valves to prevent operation. I
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Specific information on where to break the IB Main Transformer deluge line for capping*
is required. A PWO to perform this work is also required.Responsibility: System Engineering, Maintenance Planmng
Specific information on where to lifi leads and install the jumper to disable the IB Main*
Transformer deluge line is required A PWO to perform this work is also required.Responsibility: System Engmeering, Maintenance Planning..
Provide the details necessary to perform the'IB main transformer relay work via Relay*
Work Order and capture the associated components on Figure 1 of the TSA procedure fordocumentation of the abnormal configuration.Responsibility: System Engineering / Protection and Control
5. The Procedure Change Request to NOP l-0030124 was reviewed during the scope of the _.
engineering evaluation review. Observations were captured during that review and documented_
above. The following additional observation was made: __._. .
A_h.Backfeed through the main transformers was not addressed and the associated procedures*
which launch this task have not been changed. It was requested that this be reviewedagain.Responsibility: Operations Support
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It is requested that Licensing perform a review to ensure that we do not have any licensing I.
commitments which require the capability of backfeeding through the main transformers tobe available.Responsibility: Licensing
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2B Steam Generator Level Anomaly '
Problem Statement:| At appronimately 5:00ar 11/14/96 cperatcrs noticed a spike ir! 2B Steam Generatcr Level to appro:nmately 695 (4i high:.
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After transient returned to normal Steam Genera:Or le'rel was iobserved to ramp up uncontrolled at a 3-4i/hr rate. Manualcontrol was taken on the feed water control syster. Thesystem is now stable under operator manual control.
Immediate Actions:1. While in Auto mode Steam Generator setpoint was ck aged
- to 631. The ramp rate was observed to level off ior atime period and then continue the ramp increase as I
- before. -
2 FCV-9021 was visually inspected and SNOOP tested for airleakage and normal operation. Results indicate no airleaks and good valve operation.
| 3. Non intrusive data was taken on the feedwater regulationcontroller inputs and power supplies. Results indicateinputs look normal and the power supplies are withinacceptable tolerances. AC ripple has increased since the
| last test but remains within tolerance.--
Coupleted Actions:
| 1. Collect non-intrusive data to further assess condition'
while in manual. !
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I/C-PWO to be planned by 1:00pm- I/C OPS & SCE - tailboard 1:30pm
ERT team - Collect Data and review results 2:30pm
| ~ 2 Analyze Daca and make recommendation on further moreintrusive tccting or component replacement.
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| 3. Identified and located spare parts available forrepairs.
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Conclusions: -
; - _ Data indicates that automatic feedwater controller has failed| and requires replacement. As a prudent measure the power
supplies should also be changed while the controller isreplaced. Additional low risk testing in automatic mode atpower could help confirm the mode of failure.
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Short term test Plan: ).
' . . ER: Team - f.na__:e tes: setup and preceaures f : ne:: _ :
phase of testinc with the system in auts. ||Due 0800 11/15
2. Ops /ERT Team - monitcr system in Automatic Mode. j0900-1200 11/15 1
3. ERT Team - review data from system in automatic modeand make final recommendations for repairs.
Due 1500 11/15 |
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Repair Plan: |1. I&C Maintenance - prepare spare controller, 24 volt &
45 volt power supplies for service.Due 1600 11/15
2. I&C Valve - Prepare AOV test equipment to verify valveoperation. Due 1600 11/15
3. ERT team - Finalize spare parts requirementsDue 1200 11/15
3. Work controls - set time / schedule for downpower toreplace controller, power supplies and verify valveoperation.
Due 1500 11/15
4. Conduct downpower to replace controller, power suppliesand verify proper valve operation.
1:to k DEGR AD E.D G R ID F Lo ta CNT.
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Assignments:-
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2. Dave Steward - Create time line and CCl eC: data: ,, , - ~ - _ _-- __.._-._ _.. - _. . _ . -. - - . ... .y._ , __ _ _-
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:. a,nalysis team r.eview ckt design f or ne:: ster6. I&C - bench test replacement components-
p O L, e,.,.s.o _ _ Qe , , Ve N, e. O C O n t C ., ., o 2 - ). / e a.,.,.c As sem i uqi
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| 1. The resulte of your review and investigation of the notedproblem including identification af prnhahle root cause(s) .<
; My review of the noted overtime guideline adherence problemi indicates several problems which need resolution. My! investigation also concludes that violations are more apt to! occur when the workforce is scheduled on extended hours, or
people with unique talents are needed to perform work at thesite. Finally, my investigation indicates that contractors,maintenance personnel and key technical people are most likely to-
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approach guideline limits.
Problem - The bi-weekly timesheet does not progranmaticallyidentify which overtime hours are turnover time and which hours '
are work time. It is left up to the worker to annotate the formfor this identification.Problem - No standardized mechanism exists for contractadministrators to nonitor the overtime worked by contractors.Problem - The amount of turnover time is inconsistent amongdepartments and that workers and lower level supervisors aredetermining for themselves how much turnover time is acceptable.Problem - Some workers / supervisors may be falsifying timesheetswith respect to when overtime hours are worked, in an effort toavoid detection of any guideline violation.Problem The timesheet format does not contain informationabout the six calendar days prior to the beginning of the sayperiod, which precludes any identification of an early weekviolation of the 72 hours in 6. days guideline.Problem - Cross checking of timesheet data is not beingperformed at any organizational level.
If the Nuclear Division adopts a "no pay for exemptNote -
overtime" policy, the timesheet, as it is currently configured,will lose its usefulness as a tool in identifying guidelineviolators This is evidenced by the current inability toaccuratelh determine the ccmplaince of management personnel withthe guidelines.
The probable root causes of these noted problems are threefold:Root cause - Timesheets are not formatted to clearly identifyturnover hours and unpaid hours which must be accounted for indetermining overtime guideline compliance. They were not designedto accomplish this task.Root cause - Management expectations for compliance with.
guidelines and with documenting hours worked are not sufficientlyrobust to preclude violations.Root cause - There is no efficient mechanism in'31 ace formanagement to routinely verify compliance with the overtimereautrements.Root cause - No efficient means exists for supervisors or [)managers to crosscheck data entered on timesheets. !
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- 2: Review-depart 2nental self-Resessment activities to identify whythis problem was not self-identified. Why did the worker level or
| supervision not find thie pmblem?
Departmental self assessment activities consist of reviewing bi-weekly time sheets for approval. Some managers and departmentheads specifically review the time sheets for overtime guideline
! conpliance, but many do not. The lack of timesheet clarity:.egarding turnover time and unpaid hours worked (which still mustcount against the guidelines) precludes an efficient mlf-assessment.
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3. A determination of the generic impact of the problem i.e.whether the pmblem extends to other areas, systems, drawings,*
procedures, etc., or whether it is isolated to those examplescited in the audit report.
The overtime guideline problems are widespread across FPLpersonnel, and contractors alike. The results of the QA sample donot bound the population of personnel who may be in violation ofthe overtime guidelines. The corrective actions will assume thatall departments and contractors are equally susceptible to thisproblem.
4. Actions taken or planned to correct the problems identifiedand to prevent recurrence of the deficiency. Corrective actionsshould address any self-assessment /self identification weaknessesfound in (2) above.
1. Inmediate (interim) corrective actions:a. Mtter from Site VP emphasizing Nuclear Policy comoliance
and better defining limits on turnover time.b. Perform a mantal, monthly surveillance of a sampling of
plant personnel and contractor timesheets versusgatelogs.
c. Determine discipline for any individuals foundto have deliberately manipulated their timesheet in aneffort to avoid detection of guidelinn violation.
2. Progranmatic (long term) corrective actions:a. Time Sheet Improvements
- Alter form to requi.re documentation of all overtimehours worked, regardless of pay status
- Alter form to require documentation of previous sixdays overtime status (prior to current pay, period)
- Alter form to clearly delineate turnover time- Alter form to add a statement for the submitter's'
signature that reads "I have not exceeded NP 306overtime guidelines."
- Alter form to add a statement for the accrover'ssignature that reads "I have reviewed th'e surmittalfor compliance with NP 306 overtime guidelines."
-- .. . _ . _ . . __ _ _ _ . _
|-,
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4 -
11,
-b. Revise QI--6-1-to requiz.e uvuL1. actor submittal of- hours ~ ~|worked to contract administrator on a biweekly. interval. I
1
'c. Irrprove the reporting capability of the Security accesscotoputer program to generate a routine report thatexamines the hours on site for obvious NP 306exceedences.
1
5. Date when above corrective acciaa(s) was or will be achieved. 1Corrective action la. - 8/ 96 |
Corrective action 1b. - 8/ 96- Corrective action 1c. - 8/ 96
Corrective action 2a. - 9/ 96Corrective action 2b. - 10 /96Corrective action 2c. - 10 1/96 |
6. Individual (s) responsible for each corrective action.la. - C. Burton (Services) PMAI ,
ib. - C. Burton (Services) PMAI )Ic. - Joe Marchese PMAI '
2a. - R. Heroux (Resource Control) PMAI2b. - R. Heroux (Resource Control) PMAI2c. - u. Patel (I&C) PMAI
__ .__ _ _ _ _ _ - - _
. . - - - .- -. _ _ _ .. .- .
--- .--
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1.,
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<. _ . _ . _ _ _ _ _ - - . - - SGRP/SGT STATUS MEETING FORMAT __ .__ _ .
, 1
i !
1I. Ooenine Remarks - R. Siods4
II. Point Beach Uodate - M. Cepkauskas ,.- , ,<
:- . . .
III. SGT Reoort f~*"
" 1. Project Manager comments -
2. Pre-outage milestones achieved since last report
! 3. Progress report on upcoming milestones4. SGT schedule status
- Pre-outage- Outage
5. What is needed from SGRP
IV. SGRP Reoort -
1. Project Manager comments,
;-, < i f . Pre-outage milestones achieved since last report2
3. Progress report on upcoming milestones ;
( 4. Overall schedule status' 1
5. What is needed from SGT:;
V. Ooen Discussion1. Review of Action item Tracking System items not previously discussed2. Other issues not previourly discussed
VI. Review of Action Items From This Meetine
VII. Schedule Next Project Review Meeting
a
a
6
// // //
-- . _ _ _ . . ___ _-- _ __
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..
>
STEAM GENERATOR'
REPLACEMENTPROJECTPROGRESS REPORT
,'
MAY - JUNE 1996
,| \
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;
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8" 1
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.
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Nrtle
(O'SGFW40047-CVR-R1)'
- - _ _ _ _ _ _ _ _ _ - _ _ _ _ . - - _ . - _ _ _ _ . . . .--
. . . _ _ . .
j..,
!. |
| TABLE OF CONTENTS!
i.
.
s
!
| The Steam Generating Team (SGT)!i
! B&W Canada Steam Generator Fabricationi
Engineering! l
| Quality'
i |1 :; Attachments:}
SGRP Budget Status - Capital Dollars
| SGRP Budget Status - O&M Dollars |
| Pre-Outage Bar Chart for SGT l
| Engineering / Design Pkg. Development Status GraphsConstruction Work Pkg. Development Status Graphs:
! Steam Generator Fabrication Status SchematicPhotographs
; l
i '
i!
|-
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t
.. . . _ ._. _ . .. --..-. .
. _ . - - __ _- _,
-._ - -.
1
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ST. LUCIE UNIT 1 SGRP HIGHLIGHTS REPORT.
MAY - JUNE 1996
THE STEAM GENERATING TEAM (SGT. Ltd).
SGT has completed 95% of the PC/M engineering and work packages, and haS contracted for long leadmaterial aS Shown in the table below.
,
1
1Major work will re utr.e January 1997 when SGT mobilize $. At that time, all engineering and licensing
'
q documents will be reconciled for implementation.4
ISGT, LTD SUBCONTRACTOR SUNSiARY lm ...
; ,; . _. __ _ . _ . . ;__.._._;. . . _ _ . _ . _ . _ -_
I
St'BCONTRACTOR SERVICE /hiATERIAL STATUS
I Davenport Mammoet Steam Generator Rigsmg and Transporting Engmeerms Development2 Transco Products. Inc Steam Generator Insulauon Engmeenng Development"
3 LAW Engmeerms. OSO Storage Facahty Soil Bonns Completed
||
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|
B&W CANADA STEAM GENERATOR FABRICATION.
The new Steam generators are planned to arrive on Site June 1,1997.
The table below ShowS that five of the Six new contract milestones have been completed ahead of=chedule. All other B&W activities are alSo proceeding on Schedule.
il
B&W MILESTONE STATUS1
j:. :,: :== m - : . - - - - - : -- - - - - -= =.= . - . -
M/S S/G MHETONE STATUS TARGET ACTUALNO. NO. DESCRIPTION COMPLETE COMPLETE
I si Foal Weld Repar - Weld s4 (Stay Cylinder to Pnmary 2/1/95 12/24<94 |Headh
2 #2 Weld tD Seal Pass - Weld s4 (Stay Cylmder to Pnmary 2/195 1l'1894Head).
3 st Compteuon of Pninary Head ic Tubesheet to Shell Assembly 5'9'95 21:19 5Welds through MT repass of Support Base to Shell Weld
4 82 Completion of Pnmary Head to Tubesheet to Shell Assembly 7!5/95 41495Welds through MT repars of Support Base to Shell Weld
5 Both Completion or Tube to Tubesheet Seal Weidmg 6/11/96 2 6/966 Both Final Dehvery of 5/O's at PSL 6,l'97
7
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|4
'
ST. LUCIE UNIT 1 SGRP HIGHLIGHTS REPORTMAY - JUNE 1996
B&W CANADA STEAM GENERATOR FABRICATION (continued)|
Maior Accomplishmeng
|
Cambridge, Ontario - Heat Exchangers .I|
Both Lower Assemblies |'
,
Complete and loaded on rail cars for transport to Toronto for barge loading.-
Mt. Vernon, Indiana - Steam Drums,
~
First Unit Steam Drum
Complete - waiting for heat exchanger to arrive from Canada.-|4
Second Unit Steam Drum
lCompleted all PWHT NDE.
l-
Completed installation of sec. manway covers and linkages. {-
Welding of internals in progress. '. -
Internals
Complete - All five separator modules are assembled for both units.-.
ENGINEERING
Outare Preparation
Commitments have been made to return the three FPL engineers to the project on July 1,1996. Theseresources are needed to complete the remaining engineering issues and prepare for a potential earlySGRO in October 1997.
SGT and Mammoet Engineering will mobilize J .nuary 1997 to complete the project.
A draft project engineering erganization chart for the outage has been developed.
B&W Engineerine
Engineering reports are being worked for completion in 1996. FPL resources will be available to reviewthese documer ts in 1996.
-2
.._ _ . _ _ _ _
e
ST. LUCIE UNIT 1 SGRP HIGHLIGHTS REPORT-
MAY - JUNE 1996
ENGINEERING (continued)
SGT Eneineerine|
SGT has completed the engineering with the exception of the heavy rigging Design Packages which areexpected to commence in January 1997. All the packages completed to date have been approved byFRG. j
j
Early Outare
Impact evaluations were done on the early outage scenario versus the current contract outage of February1998. The results showed that the Contractor and the steam generators can support installation as earlyas June 1997.
Steam Generator Disposal
Two vendors are bidding on the disposal of the Unit I steam generators. Bids are expected on August1,1996. FPL will determine if the near term disposal is cost effective compared to long term storage.
OUALITY
Surveillance continued at Cambridge and Mt. Vernon manufacturing facilities. Both I'SG heat exchangersections completed manufacturing and were transported by rail from the Cambridge shops to the Port
.
of Toronto. This transport and the subsequent loading on to the barge was successful. )Archive weldment and material samples were receipt inspected and found acceptable. |
Radiographic Hims for the heat exchanger sections were shipped to PSL. These Elms were inventoried |and inspected. All were found acceptable and are in the PSL record vault. i
Distribution:
T.F. Plunkett |
J. A. StallW.H. BohlkeL.W. BladowJ.M. BradyK.R. CraigC.L. BurtonD.J. DenverJ. MarcheseC.D. MarpleK. A. McKennaJ.C. ScarolaC.H. Wood
-b
< _
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: i !-
ST. LUCIE UNIT 1'
SGRP BUDGETSTA TUS- CAPITAL DOLLARSi1
!
JUNE 1996:
a
|
7,500 |i, '
| !
' 7,000
14
'
5 6.500 I L-- -lMoNTHLY BUDGET
i MONTHLY ACTUAL oC = CUM DUDGET # T IO'#6.000 - "
# '---O- CUM. ACTU ALo e
5.500 - -
- ,-4 ,
| 3 *
5,000 f,------ -- --- - - - - - - - - - ----s. gp ,
sm , ,
4,500 p'- 13.500
) @ 4.000 l A, i m_
' u#
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3,*g 3,500 j o, ; a
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O l am .-i $3.000 pm ,
@ 8.500 ei
< i o 1
2500 L p"- - )
'_ ' S )E I,
i m' g2.000 e|
o ; 1| 4
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1 - ."O -
1 3.500 |
'
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ILI+3 y _E: - I0+ - - - ---
3
,E e M E R ,5 4 9 a t a 8'
.500
, w s 4 s < m o = a ;
500 1 -1
_
(5000) I
CURR MONTH YR-TO-DATE TOTAL-TO DATE YR-END FCST|BUDGET $627 $5,162 $66,403 $18,881
ACTUAL /FCST $753 $2,027 $61,546 $16.405VARIANCE $127 ($3,134) ($4.857) ($2,476)
Significant contributors to the Year..To-Date budget underrun:- SGT payment schedule was changed due to the reschedu!ing of the SGRO fro 9/97 to 2/98. ($2,121K)- Deferred payment for blowdown line analysis done by SGT. ($100K)- Deferred QA/OC contractor support. (5357K)- Negotiated ehmination of BWI scope change for barge transportation of new S/G's (236K)
I,
F '.USERSICOWDREPRE TMD5-v ART AT'36'i RV, Onnt L;,is 721?C KJC
- _. ._ __ __ __.
u
ST. LUCIE UNIT 1SGRP BUDGETSTA TUS- O& M DOLLARS
-
JUNE 19962
1
80 -,000
t
! iMONTHLY BUDGETi,
I MONTHLY ACTUAL ',
= C " CUM BUDGET gj --O---CUM. ACTUAL e 00
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, w s < ' < m = 6i
I; ($000)
CURR MONTH YR-TO-DATE TOTAL-TO-DATE YR END FCSTBUDGET $43 S277 $1,381 $550ACTUALIFCST $13 $89 $981 S550VARIANCE ($29) ($188) ($400) 50
Significant contributors to the Year-To-Date budget underrun:; Project support efforts are below the level estimated for the 1996 budget due pnmarily to the hold
placed on the OSG Storage Facility (Mausoleum) and the elimination of the Main Steam TrestlePCM from the 1996 outage scope. The Mau"8eum will remain on hold until the OSG on-sitestorage vs. disposal alternative is decided upon. The Main Steam Trestle PCM has beendeferred until the SGRO.
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! REPLACEMENT PROJECT|',
| SEPTEMBER REPORTi
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Report Contents:Project Pre-Outage Milestone Schedule Page 1Executive Summary Page 1B&W(S/G Construction) Status Page 2SGT (Installation Contractor) Status Page 2Engineering Status Page 2Quality Assurance /C,ontrol Status Page 3Plant Construction Status Page 3Operations / Support Status Page 4Health Physics Status Page 4Project Controls Status Page 5
)O&M Budget Performance Page 6Capital Budget Performance Page 7 ,41
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SF gy,4NOV_DEC,..LAN_ ,FEB , MAR, APR_ .MAY_. .r ~ SC -,0CTINO 'JuL '#UOlOENTIFY SGRO CRITICAL PATH 30SEP98 _.4 _ [ ;
APPROW SGRO CRITICAL PA 170 ctg 8 '
f'AMENO SGR CONTRACT 01NCMG 01NOV
COMF1RM UCENSING DOC's 130ECet . jyC1YOIDENTIFY PLANT OLTTAGE SCOPE 130EC06
AWARD OSC DISPOSAL CONTRACT 310ECes 3yC |COMPLETE RELOCAT NORTH 31JAN07 I'hAN
DEVELOP LAYDOWN PLAN 01PE897 0 ESCONDUCT 2nf PARTY REA04NE 01 7 0 ES
DEVELOP HP PLAN 0$FE807 05PE8y)
SELECT CPECl 15FE897
|RECONCILE EP/DP/WP 21FEB97 2 EB '
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DEVELOP CRANE PLAN 14 MAR 97 $ Id'
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COMPLETE INITIAL MOBILIZATION OF 31gARg7 31 MAR '
SGT (MK / DESf) VDETERMINE UNIT 2 OUTAGE IMPACT 01APR97 1
01 APR |
ICENTIFY NON SGRP PROJECT 01APR97INTERFERENCES I I
CyRRESOLVE NON SGRP PROJECT 30MAyg7 i30MAY
f' Y !.INTERFERENCESRECEIVE NEW SCs 02JUN97 02
START CRAFT MOBILIZATION 01JUL97 OpAPPROVE ALL WORK DOCUMENTS 20AUG97 20A
VERIFY PARTS, PAPER 20Apog7 20^
STMtT CRANE OUTSIDE CONSTRUCTION 20AUG97 2
START SCRO 200CT97_ Tf j
Executive Summary
Considerable progress has been made in areas of project staffing and identification ofschedule needs, An inillal meeting was held formally with the Plant Staff to inform them ofproject status, Nuclear Olvision decisions were made on severalimportant issues.
- Immediate disposal of the original S/Gs was approved.- The QAlQC scope of the replacement project has been awarded to theimplementation contractor.
- Approval was gained for an independent assessment of our licensingbasis.
Our implementation contractor has begun the replacement of SIGs at the Point BeachPlant, and we are watching closely to gauge their readiness, their skills, and their abilityto ir,tegrate lessons learned into the St Lucle project. '
Wo are dissapointed with the lack of aggrossivo scheduto improvement on Si. Lucle'soutage sinco the contract was awarded, and with the real time participation in our outagemanagr .nt mootings. I have discussed both of these issues with Marty Cepkauskas,Presiden of SGT, and received assurances of expedient action by SGT.My staff and I have determined that the existing contract needs renegotiation to bringterms, incentives, and scope up to date with current FPL performance standards. Thiseffort is currently underway with support from the plant contracts organization. Our goal Iis a contract amendment that more clearly defines our expectations for world classperformance, while ensuring that FPL receives fair value for every dollar spent.
Dick Sipos - Project Manager, ,
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B & W Status:;
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Closure seam welding of the first replacement steam generator is in progress.The facility in Mount Vernon is working 24 hours / day, 7 days / week on welding to
i
ensure the 6/1/97 delivery date to the site is met. I
1
Accomplishments: |- The primary head mockup and archive samples were shipped to the site. '
Hardspets: J- B&W has used some of their float. FPL is monitoring progress weekly toassure delivery schedule is met.
. m m m ... m .. m . m m .. m .. m m m m ... m m m m . m ...... m m .
SGT Status:
The Point Beach SG replacement outage began 10/5/96. A vast majority of theSGT project team which will perform the St. Lucie implementation is gaininginvaluabla experience during this replacement.
|
Accomplishments:- A Construction Manager (Steve Mager) has been assigned full time to the
PSL site.- A commitment was made to provide a full time DES engineering personand a scheduler.
Hard spots:- Mgmt Rep needed at PSL Unit 1 outage meetings.- Aggressive schedule reduction expected.
m .. m . m m ......********** .. * m ... *******...***... ....*.. **..*******
Engineering Status:The focus of the Engineering Group is on the fabrication of the RSGs at MountVernon, Indiana, and various project support efforts such as technical review cfdisposal bids and water depth surveys of Big Mud Creek.
Accomplishments:- A contract for a third party review of the completed 50.59 evaluation wasissued.
- A survey of Big Mud Creek depth confirmed that no dredging will berequired to accommodate the barge carrying the replacement SGs.
- Technical bids for SG disposal were evaluated.
Hard spots:- None at this time. -
Ron Gross
o,nn n
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Quality Assurance / Control Status:<
QA/QC activities continue to focus primarily on the manufacture of thereplacement steam generators. This focus requires routine visits to themanufacturing facility, as the shop is now working 24 hours / day, 7 days / week.Overall progress continues to be good. The transfer of QC responsibilities fromFPL to the implementation contractor has resulted in the Project Quality Planneeding revision. This revision is underway, with completion scheduled forNovember,1996. Quality records are now being received from B&W.
i
Accomplishments: *
- Replacement S/G material archive samples have arrived at PSL. Thesesamples have been receipt inspected and stored in the North Warehouse.
- Received QA records such as RT films, tubing CMTRs, and tubing PSI data.These records are in the vault.
- All history docket information for the steam generators has been reviewedand is up to date.
- Point Beach was visited during their preparation phase for replacement.
Hard spots:- FME during manufacture of the RSGs continues to he an area of concern.
M #" Rick Weisu.u.u.
Plant Construction Status:
The Construction Group acquired Fred Gigele from Maintenance. Activitiescenter around gaining familiarity with the PCMs, Design Packages, WorkPackages and project schedules. An observation trip to Point Beach to observecontractor controls and performance is underway at the time of this report. '
Accomplishments:- Supported Outage Management with initial laydown area needs insidecontainment.
- Canvassed Plant department heads to identify projects that would impactpolar crane, station air, service water, temporary power, or laydown areasthat would represent a threat to SGR success.
Hardspots: ;- MK does not have a proven track record with FPL to ascertain their ability j
'to deliver a quality work product within cost and schedule constraints. '
- PrelimineJy review of MK/DESI documents (PCMs, work packages) and theimplemeniation schedule indicates that more work is required to ensure noproblems are encountered in the completed work turnover process.
- MK does not yet have a Level 2 design schedule prepared for the heavyrigging contractor, Mammoet. The lack of this design schedule couldimpact our ability to effect an early start to Steam Generator Replacement.
- Although it is agreed that removal of the pressurizer missile shield fromcontainment is needed, there is no owner for the missile shield once it is |removed from containment.
c.e2//w Fred Gigele
Pann3 |
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Operations / Support Status:_ _ _ . _ __ _ _ _.__ _ _. -_ _
John Tepley has been assigned to manage the SGRP's Operations / Supportgroup. This group's recent focus has been on the development of an action itemtracking system for the SGRP. A support technician has been added toadminister the input and output of the tracking system, as well as microfilmSGRP records in the QC vault. Action has been initiated to gain approval by thePlant of the post maintenance testing associated with the SGRP.
Accomplishments: j- Action item tracking System developed and implemented.- Departmental training guideline developed for SGRP personnel.- Testing for SGRP work has been identified.- A matrix of all SGRP documents has been developed.-
Hard spots:- The impact of QI 7-PR/PSL-1 on the SGRP has not been determined. Actionhas been initiated to review this Ol.
- Engineering Packages and Design Packages contain mode restrictionswhich appear to be overly conservative. A review is underway to identifyareas for relaxation which will improve the schedule.
/John Tepley
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Health Physics Status:
Development of the Radiation Protection Plan was initiated. A prcblem with theSG replacement Manrem Goal was identified. The original target was niet at 370Manrem based on previous changeouts. More recent SG changeouts tell us thatwe can accomplish our task with a budget of approximately 200 Manrem.Manhour estimates for each activity are needed from MK before a final,legitimate target can be set.
Accomplishments:- Developed outline of Health Physics responsibilities / activities / concernsregarding the project.
Hard spots:- HP issues with original steam generator disposal
- Coatings- Filling SIG with other radwaste'
- Removal of water from inside SIG- RCS Pipe End Decon (cost ver sus Manrem saving)- Manrem estimates and incentives- Radwaste minimization initiatives
Ken Payne Y
Pace 4
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Project Controls Status:'
- - - . - -
Level 2 schedule development is underway for each project discipline. Dailyinterface meetings with Plant outage management are held to review progress |
on the Unit 1 refueling outage schedule. All existing pre-outage schedules arebeing converted from Primavera to a Schedule Publisher format to beconsistent with Plant software.
Accomplishments:- The project cashflow (as been adjusted to accommodate a projected10/20/96 start date.
- MK has been formally notified of our intent to replace the S/Gs in fall of1997.
- Level 1 schedule for pre-outage work has been developed.
Hardspots: I'
- Decision on original SIG disposal requires contract amendment andisubmittal of additional budget item ($12 million)
- Contract amendment needed to acknowledge incorporation of QA/QCscope with MK, North Service Building use for workforce, and to tiedeliverables to payments more closely.
- Need input from MK on selection of subcontractors and parts deliverydates.
- Need to establish a project readiness date.- A more aggressive critical path schedule for MK activities is needed. Thiswill occur in early October.
Chris Burton C#8
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ST. LUCIE UNIT NO.1*
SGRP BUDGET STATUS - O&M DOLLARSf - - -- SEPTEMBER 1996
!80,000 -
600,000
j llElHIM BUDGET - MONTH ,o 550,0001 ' ACTUAL - MONTH= "
- * - BUDGET - CUM ,a 500,000""C-- ACTUAL - CUM ,,
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200,000 |
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(5000)| f CURR MONTH | YR TO.DATE TOTAL-TO-DATE L YR END FCST! BUDGET $57 $422 $1,526 5550 '
ACTIFCST $3 $105 $997 $550ACT/FCST VAR ($54) ($317) ($528) $0
$ '
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Year-To-Date Variance ($316,695)
t' Significant contributors to tb.!s vonance:d * Project support efforts are below the level estimated for the 1996 budget duei partially to the elimination of the CmG Storage Facility (Mausoleum) and
the deferral of the Main Steam Tretta PCM until the replacement outage,
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ST. LUCIE UNIT NO.1*
; SGRP BUDGET STATUS - CAPITAL DOLLARS---
SEPTEMBER 1996
7,500,000 22,500,000,
7,000,000| 20,500,000
6,500,000
MBUDGET MONTH 918,500,0006,000,000 = ACTUAL MONTH- '
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8UDGET CUM ,'5,500,000 + ACTUAL CUM - 16,500,000
5,000,000-
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j 4,500,0001 6; I #
, 12,500,000 Ij 4,000,000,
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$ .# E; 3,500.000 - - - - - - o' - 10,500,000 jh ' ;$ 3,000,000 N - 3
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8,500,000 g2,500,000 p',
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($000)CURR MONTH YR.TO DATE TOTAL TO-DATE YR-END FCST
BUDGET $718 $11.068 $72,309 $18,881A_CTIFCST $81 $4,252 $63,771 $10,160 a
ACT/FCST VAR ($637) (56,817) (58,539) (58,721)
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Year-To-Date Variance ($6,815,815)
Significant contributors to this vanance:
* SGT- Revised payment schedute to reflect the SGRO schedule change. 51 071.200)* SGT - Deferred Blowdown Une analysis. ,sioo coo)* BW1 Delayed corrpletion of First Steam Generator Closing Seam weld. 52.436 ees)* BW1 Negotiated the elimination of extra costs related to Barge Transportation. (5252,750)* QA/QC Deferred contrador support due partia!!y to eliminating the OSG-SF and
defemng the Main Steam Trestle Mod. activity until the replacement outage. rs47s 277)TOTAL explained vanances.(se.saa.eet)
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REPLACEMENT PROJECT'
OCTOBER REPORT.
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Report Contents:; Project Pre-Outage Milestone Schedule Page 1| Executive Summary Page 11 Organization Chart Page 2| B&W (SIG Fabrication) Status Page 3; SGT (Installation Contractor) Status Page 3! Engineering Status Page 3} Quality Assurance / Control Status Page 4i Plant Construction Status Page 4i Project Controls Status Page5{ Health Physics Status Page 5 <[/j O&M Budget Performance Page 6 ( g4j Capital Budget Performance Page 7 / )
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# _ _ .. . sF[ i f 'NOV_DEC_.JAN_ FEB_ MAR APR.MAY_.JUN _ .JUL_ AUG _ sEP_ _oCT NOV.loENTIFY SGRO CRITICAL PATH 0toCT96
TAPPROVE sGRo CRITICAL PATH BY 23oCT96MGMT.
ECAMEND sGR CONTRACT 01DEC96
IDENTIFY PLANT OUTAGE SCOPE 13DEC96 IhAWARD osG Disposal CONTRACT 31DEC96 ,
COMPLETE RELOCATION TO NORTH 31JAN97SERVICE BLDG. Y
EBDEVELOP LAYDoWN PLAN 01FEBC7
SELECT SPECIAL PROCESSES 1$FEB97CONTRACTOR I
DEFINE scope To RECONCILE 21FE897 24EBEP/DP/WP IOMCONDUCT 3rd PARTY READINESS 01 MAR 97
REVIEW Y ,
0 jDEVELOP HP PLAN 01 MAR 97
I#DEVELOP CRANE PLAN 14 MAR 97.
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COMPLETE INITLAL MoBluZATioH oF 31 MAR 97sGT (MK / oEst) IOMDETERMINE UNIT 2 OUTAGE IMPACT 01APR97 y j
IDENTIFY NoN sGRP PROJECT 01APR97INTERFERENCES
RESOLVE NoN sGRP PROJECT 30MAY97 I
INTERFERENCES02)UNRECEIVE NEW s/G s 02JUN97 iv i
START CRAFT MoBtLt2ATioN 01JUL97
#APPROVE ALL work DOCUMENTS 20AUG97 v
VERIFY PARTS. PAPER & PLANNING 20AUG97 20A WCOMPLETED vI |
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START CRANE ouTsIDE CONSTRUCTION 20AUG97 #v
START sGRo 20oCT97 yT
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Exocutivo Summary
The SGRP pro-outago preparation reached a milostono in October: the outage start datois loss than 12 months away. As the countdown to October 20,1997 has begun, the SGRPTeam has increased it's efforts to micro-plan the Unit 1 project. To ensuro success, a self-assessment of the project team (organization, mantoading, skilllovo!) is in progress.
Our stratogy is fundamental: build on the in-house project and industry experience withIndustry exporlonce from outsido (Point Beach, Salom, North Anna, etc.). A series ofroadiness reviews are planned which includo FPL Internal,implomontation Contractor,and Third Party. With tho vast data that is availablo,it is anticipated that informationsystems applications will play a significant role in the SGRP's success.
As SGT (the Contractor) completos SG changoout work at Point Beach, a focus to ,prepare their facilities (officos, computers, phonos) for a sharp personnel ramp up isunderway. Nino SGT people are expected in Occomber. The number willincrease to morethan 30 in January. The FPL SGRP complomo will be at 20 poople in Januar .
John Toploy - Project Managor
Page1
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SGRP'
ORGANIZATION CHARTJ
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,VCE PRESIDENT
JA STALL ;
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SGRP SmMANAGER OutuTY M AN AGER# L W. BL ADOW
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LEAD MANAGER MANAGER. LEAD g, ggggK. PAYNE R.C. GROSS C BURTON F.G OELE I
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_PLANT INTERFACE
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MECHNUCL EAR- M. M ACLEOD WORK PACKAGES
L. LOSTOCCO SCHEDLLERS- TtNDNNER
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_ D.MOSAPOM. MAISANO
ILICEN94G
- TBD -
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M. BRYAN ICS
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|_ Contractor Status:-
,
,>| B&W: _. _
-- - --
!' - Closure seam welding continues on the second unit while radiography is'
performed on the first unit's weld,- Decision made to ship both replacement SGs on a single barge to PSL.e
SGT:
- The Point Beach SG replacement outage is in progress. The polar cranehas been modified and load tested in preparation for steam generator lifts. |
- The original steam gpnerators have been cut from the reactor coolantsystem with no resulting movement of the RCS piping.
- A 36 day critical path schedule has been provided to PSL.
********:.eeeeee !
Engineering Status: ||!
Outage Preparation:The project has accelerated mobilization to begin in 1996 due to the new outagestart date of 10/20/97. Integrated Plant /SGRP outage meetings, scoping, and |scheduling are taking place. '
|
B&W Engineering: (fabrication contractor)Engineering reports are being worked for completion in 1996. FPL hasreviewed and commented on these documents. FPL will issue the final recordCertified Design Specification by December 1996.
i
1
SGT Engineering: (implementation contractor) |The scope of reconciliation of engineering and licensing documents is in '
progress. The production effort will begin in 1997. An engineer from DES is nowon site full time.
|
Disposal:The decision was made to dispose of the old steam generators. Two vendors bidon the off-site disposal. Contracts is completing the commercial evaluation.
,
Contract award is due in early November. !
10 CFR 50.59 Review:A draft report from the third party review of the completed 50.59 evaluation wasreceived on 10/18/96. An internal review of the report is underway.
Hard Spots:- Awaiting final barge / shipping configuration from B&W.- Need full time engineering support for the disposal project and the 50.59reconciliation.
- Complete the planned staffing of the SGRP engineering area.- Settle outstanding contract issues with B&W.
s
Page 3
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Project Controls Status:,
- Discussions were held wit'h the Operations Manager and subordinates to define1
expectations for Mode related activities. This discussion resulted in a number of |proposed changes to the work packages and engineering documents that will !benefit the project scheduformat the work packages,le. Additional discussions focused on how tc bestto facilitate case of NPS approval during '
implementation. The videotape which overviews the replacement was providedto the Ops Manager for review by the Operations Department. 1
iAccomplishments: i,
- A copy of the North Anna Plant / contractor interface document wasreviewed and will forrn the basis for our interface document with SGT.
- A preliminary review of construction work packages for recommendedrevision to accommodate the Operations Department needs is 90%
!
complete.1
-
Hard spots:- Procedure detailing the PSL Plant /SGT interface needs to be written.- Additional procedures which define previously unencountered RCSconditions need to be' identified to the Plant procedures group. (Example:complete draining of the reacivr coolant system)
.........................................................;............................
Health Physics Status:
Development of the Radiation Protection Plan is on-going. Revision 0 of the HPstaffing plan for the outage has been developed and is under review by PlantHealth Physics supervision. Observations at Point Beach and Salem areunderway to evaluate benefits of pipe end decon.
Hard spots:- Completion of the HP readiness review requires input from SGT and theassociated due date has been pushed back to March 1,1997.
- Need to make recommendation to Site Management regarding a streetclothes clean RCB. SGT input is needed.
-Individual tasks / outage manrem estimates require major effort by SGT.This will be an immediate priority following Point Beach completion.
- Access to RCA and containment plans need to be finalized for SGT topermit planning for dosimetry and other HP controls.
Ken Payne
7DPage 5
. _ - . _ _ _ _ _ _ - _ _ _ - - - - - - - - - . - . - - - - .- - - - . - - - - . _ . - .
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{ , ST LUCIE UNIT NO.1-
}i SGRP BUDGET STATUS - O&M DOLLARS |
;
1
| OCTOBER 1996ii
i 80.000600.000
MBUDGET MONTHo + 550,000
i ACTUAL MONTH ,'|
i
- '* - BUDGET . CUM o' |
<
--O-- ACTUAL CUM # ~
'
,- o
'60,000 ,' 450.000
'|
- 400.000
_ ,' |o
' - 350,0007
I 4
40.000 - - - - -- - - - - - - 300,000
: : :i - 250.000
' ',
i
- 200.000
20.000 4 - -f - - --- - -- 150.000|
'
+ 100.000.4 +
'* -
50.000
j 0- --
-0| 5 $ $ i i j $ $ i E i E; 4 a < g 2 a a s s,
.
($000)CURR MONTH YR-TO-DATE TOTAL TO DATE YR END FCST
I BUDGET $43 $464 $1,568 $550ACTIFCST S1 $106 5998 $200ACT/FCST VAR ($42) ($358) (5570) ($350)
t -
:
] Explanation of Year-To-Date budget underrun: ($000); . Project support efforts are below the levet estimated for the 1996 budget duej partially to eliminating the OSG Storage FacilttyJMausoleum) and
___1
defernng the Main Steam Trestle PCM until the replacement ou' age (5358)
j TOTAL explained variances ($358)
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ST. LUCIE UNIT NO.1j -
SGRP BUDGET STATUS - CAPITAL DOLLARSOCTOBER 1996 |
. . . - . . _ _ - . - - _ . - - . . . _ . - - . . - - -- - - - |1
7,500,000 22,500,000
7,000,000- 20,500,000
t
6,500,000 i
|
THE BUDGET OVERRUN IN OCTOBER WAS THE RESULT 18,500,0006,000,000 OF A DELAY BY BWIIN COMPLETING THE CLOSING '
SEAM WELD OF T(IE FIRST STEAM GENERATOR. THE 8
PAYMENT FOR TylS MILESTONE WAS BUDGETED IN #5,500,000 AUGUST AND ACCRUED IN OCTOBER.
- 16,500,000
x ,]i
5,000,000 -
I,- + 14,500,000||
4,500,000 ' /- -
I#
g - 12,500,000 _} 4,000,000 M BUDGET MONTH ---
,-
.E |5 #t iACTUAL MONTH |
r
f 3,500,000 + s '
o . BUDGET CUM o - , ,000 _.
+ ACTUAL CUM -
3,000,000 - - ' - - - - - - - - ---
o,
o2,500,000 -,
- 6,500,000 I
2,000,000 r - '
o'1,500,000 -.-- - 7 ,c'- - - - - - - 4,500,000
*
J1,000,000 -- 7 -
7 2,500,000
500,000 r - M - - t -
| T 500,000
0}k 2 5 k $ k E E $ 5 E ku
!
-500,000 - - - 1,500,000
($000)CURR MONTH YR-TO-D AT E TOTAL-TO-DATE YR-END FCST
BUDGET $1,220 $12,288 573,529 $18,881ACT/FCST S3,088 S7,340 $66,859 $10,000ACTIFCST VAR S1,868 ($4.948) (56,670) (58,881)
Sigt'ificant contributors to the Year-To-Date budget underrun: ($000)SGT - Rev' sed payment schedule to reflect the SGRO schedule change ($3,598)
Deferred Blowoown Une ana!ysis ($100)BWI - Negotated the eliminabon of extra costs related to Barge Transportaton (S253)C A/OC Reduced contractor support due partally to eliminatng the OSG-SF and
rce ernna the Main Steam Tresne PCM unti the replacement outage ($520)TOTAL erotained variances (54,471)
. # wstasecownatwicponrummoresio nw en o. sin 2m
.- ._ - ._. .- -. ._ _ __ - _ -- - . - _ - .
,.1
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,
i STEAM GENERATOR;
i REPLACEMENT PROJECT ;
j NOVEMBER REPORT :
: I|
<
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IJ, :
5
76 / i.
y- > </ ;1
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R'
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,~ % 1~
; . se L- |! ,
, %. . - . . .
_ ~ -.
h;
! k#| y 1 --
: w4
: Report Contents:Project Pre-Outage Milestone Schedule Page 1'
Executive Summary Page 1;
Engineering Status Page 2;
| B&W (SIG Fabrication) Status Page 3
j SGT (Installation Contractor) Status Page 3: Plant Construction Status Page 3
| Quality Assurance / Control Status Page 4
i Project Controls Status Page 4Health Physics Status Page 5
4
: Action item Tracking System Status Page 6
) O&M Budget Performance Page 7
i Capital Budget Performance Page 8
i SIG Disposal Fragnet Page 950.59 Review Fragnet Page 9 j*
Facility Relocation Fragnet Page10 {SGRP Documentation Fragnet Page 10
'
___ _ _ _._
e
. 030EC96ST LUCIE i SGRP LEVEL 1J TEPLEY
PRE OUTAGE SCHEDULE FOR 10-20- 97 SGRO*
.SF T. OV_ . . .
'010CT96 T~g -~~ ~ ~ ~DEC_ AN.FEB. MAR,APR;MAY., .. J L Au SE P ,0C .NOVtoENTW SGRO CR171 CAL PATH ,~" ~
APPROVALSGRO CRITICAL PATH BY SENIORMANAGEMENT 230CT96
AMENO SGR CONTRACT 010EC96 y-IDENTIFY PLANT OUTAGE SCOPE 130EC96 j 9
ISSUE OSG OISPOSAL CONTRACT 310EC96 j 31DEC
COMPLETE RELOCATE SGT TO NORTH ISSUESFACluTY 3g;4Ngy N.MOBTAIN MGMT. APPROVAL OP LAYDOWN FOR '
< SGRP 01FE897 l 'f,i
'SELECT SPECIAL PROCESSES CONTRACTOR 15FE897 i sf,EB
, ;,
DEFINE SCOPE TO RECONCILE EP/DP/WP EB97 Y-
IMPLEMENT THIRD PARTY SGRP READINESSREVIEW 01 MAR 97!
' DEVELOP HP PLAN|
01 MAR 97
DEVELOP CRANE PLAN 14 MAR 97 NR'
COMPLETE INIT1AL MO81U2ATION OF SGT (UK / 31 MAR3,ggggyCESO
.lOENTIFY NON SGRP PROJECT OMgigppgy , 'INTERFERENCES
, DETERMINE UNIT 2 OUTAGE IMPACT 01APR97 ; U #.#"
RECEIVE NEW S/Gs AT SITE 08MAve7 ! 08M,AY
RESOLVE NON SGRP PROJECT 3N3ny3ygyINTERFERENCES
i START CRAFT MOBlu2ATION 01JUL97 01,JpL
' ! VERIFY PARTS PAPER & PLANNING ] ! | 20AUO |f COMPLETEo q
'
,
20AUG97i , i "i l,
I ALL DOCUMENTATION APPROVED BY FRG 20AUG97 1 20*fG |3
'20ASTART CRANE OUTSIDE CONSTRUCTION 20AUG97 j j,
! ;8EGIN SGRO 200CY97 i | 2MCT2,MCT:.
Executive Summary
Fabrication of the replacement steam generators continues in an excellent fashion. Thefinal closure welds are complete and post weld heat treatment is in progress. Theshipment of the steam generators has been advanced to April 21,1997. (The contractship date is June 1,1997) The replacement steam generators are expected to arrive
ionsite on May 10,1997. .
The decision to dispose of the OSGs has moved from decon and cut up, to burial. The4
main reason was due to the increased risks to FPL beyond February 1998 on a newprocess to dispose of OSGs. As the contractor was seeking a shared risk approach, thedecision was made in support of the direct burial cption.
SGRP guidelines to conduct readiness reviews were developed. A series of readinessreviews will be conducted throughout the preplanning phase, of which the first is aninternal readiness review, scheduled for December,1996.
An ALARA study was conducted which determined the effectiveness of the pipe-end fdecon. It was estimated that more than 100 man rem can be saved by performing pipe-end decon. Work continues with our main contractor, SGT, to integrate into the plant. !
h
Contract negotiations have begun with SGT to develop an incentive contract based onperformance and realistic, aggressive criteria. The current scheme which represents a370 man rem ALARA budget and 47 day critical path windwrdoes not reflect reality. ef
.
MMO |-9 /%C* John Tepley - Project Manager |
Page 1Ii
_ _ _ _ _ . . . . _ _ _ . _ _ . . _ . _ _ . _ . _ . - . _ . __ _ ____. . _.
,
i{.
! - Engineering Status: |4
!
B&W Engineering:-(Fabrication contractor) -
;'
Engineering reports are being completed by B&W FPL is in the review process. !FPL has issued the final record Certified Design Specification. !
;
4
i i
Mount Vernon Shops: (B&W Facilities) !The Upper and Lower sections of both replacement steam generators have been;
ij joined. The final closure welds are complete, and the first generator has i
i completed heat treating. The,second generator will complete heat treating in| December..
i SIG Delivery:#
Shipping of both replacement steam generators on a single barge is scheduled; for April 21,1997, with arrival on Site May 10,1997.
2 SGT Engineering: (Implementation contractor)Schedules are under development for the production effort needed to reconcile3
j engineering and licensing documents which will begin in 1997. An engineer fromDuke Engineering Services (DES) is now on Site full time.
:
{ Disposal:: The decision was made to dispose of the old steam generators. Two vendors bid* on the off-site disposal. The technical and commercial bid evaluations are
complete. Contract negotiation is in progress with the evaluated bidder, and Ii
award is anticipated in late December or early January. (See attached FRAGNET,
| in this report)i
| 10 CFR 50.59 Review:FPL contracted with NUS as the third party reviewer of the completed SGRP
2 50.59 evaluation. Their draft report was received and additional work wasidentified by NUS to meet current NRC interpretations. The revised text and
; rationale was discussed with NUS and others. The revised 50.59 is expected tocomply with NRC interpretations, and a PLA will not be required. The final NUS
|;*report is due in early December. (See attached FRAGNETin this report)
|'
,
| Accomplishments:; Final barge / shipping configuration received from B&W.-
; SGRP work scope conveyed to Fuels, Reactor Eng, l&C Eng, and-
Mechanical Eng..
i
! Hard Spots:
j Obtain a full time project engineer for the SIG Dispoa project.-
: Action: Tepley(AITS#69 - Due 1/15/97)Obtain and mobilize remaining authorized engineering staff- these willj -
j be contractors.^
Action: Tepley (AITS #69 - Due 1/15/97)i LD'
Ron Gross
3 Page 2
-e+= m-m y-en r-mW i+--w,, ,- ---Tr - -----g ,r- -,- - - - v--- - yw
.
. Contractor Status:.
B&W:~ ~
~'Clo' ure' seam welding is complete and' radiography " sat" on both St. Lucies-
units.- Hydrostatic test of secondary side of new S/Gs due in December for firstunit and January for the second. ,
SGT:
-The SGT critical path portion of the Point Beach outage was performed in25 days. Welding of the feed / steam lines' remains.
- Ramp up of SGT persorinel at St. Lucie is underway. Oneplanner / scheduler and one resident engineer are now on board.
|
***************************************************************************.********
Plant Construction Status:
Construction activities during November centered on reviewing Work Packag'esand assisting Maintenance on Polar Crane readiness issues, final planning forSGRP facilities move to the Plant North side, purchase requisitions, and theupgrade to Substation 10.
.
Accomplishments:- Provided the PR for a factory rep to review the polar crane maintenancehistory and provide recommendations, spare parts, and service for theUnit 1 SGRO.
- Negotiated agreement and schedule with Maintenance to exchangefacilities. Maintenance moves south, SGRP moves north. (A/TS # 112 due12/15/96, and AITS # 115 due 1/15/97) See attached FRA GNETin thisreport.
- Performed observation of SGT's SG transport and rigging capabilities atPoint Beach.
- Obtained valid requirements for electric driven air compressors fromProtection Services to support the " Clean Air Act" requirements. SGT willconsider electric compressors for their scope of work. (A/TS#172-Complete)
Hardspots:- Planning is underway with Power Delivery, Electrical Maintenance andProjects to finalize a design for needed improvements to Substation 10.Options will be presented to management during the December 11,1996Unit 1 Outage Meeting. Action: Gigele (AITS#149 - Overdue)
.
e
Page 3
_._ __________ _____..___ _._____
[.2 '
Quality Assurance / Control Status:,
|*
| Steam' generator fabrication continued, with the completion of two majormilestones. Both closing seams are now through the heat treat cycle. No4
; probl3ms were encountered during this stress relieving, and this completes thepressure boundary welding. The next major operation is the secondary side j,
hydrostatic test. A series of meetings was held with SGT QA Management, and a f
! plan was formalized to complete a review of the SGT Quality ExecutionProcedures (QEPs). This activity is now a Level 1. These documents form the
.cbasis 'or how SGT will conduct business at St. Lucie. 9
4 ,,'"
; Hard spots:- Clarification of which SGT documents must receive FRG review is needed.
! A recommendation from SGRP will be provided for St. Lucie Mgmt review| by 1131197. AITS # 209 - Due 1/31/97.1 - PSI UT results from B&W were shown to the JPNICSI UT department. The *
j Level Ill rejected the documentation because it did not meet his1 expectations for level of objective evidence. B&W states that the reports
meet the Code. Resolution is expected by 2/14/97. AITS#210- Due !
2/14/9 7.
Rick Weis N*******************************.**************************************************** ;
,
,
i
Project Controls Status:.
ii
Meetings with Operations Dept. and Work Control have resulted in an approach:
i for the contractor work packages that will not cross system boundaries or| modes in a single work package. With this Operations Dept. approvedi approach, we can now proceed with SGT to reconcile the work packages a final: time. PWO generation for work packages and associated testing is in progress in; anticipation of the 12/13/96 Plant Pre-Outage Milestone.
Accomplishments:3
4 - A draft of the Plant / contractor interface document has been written and isunder review.,
| - The SGRP Department training and indoctrination program was approvedand implemented.
- An SGRP guideline has been written to address how readiness reviews willj be conducted for the Steam Generator changeout.i
| Hardspots:! - A well defined ramp up and ramp down for SGRP, SGT, and associatedj craft must be developed and provided to the Plant by 2/1/97.
Action: Cowdrey (AITS #154 - Due 12/31/96)- Incorporate lessons learned by SGT at Point Beach in an effort to furtherreduce the SGR critical path. (Point Beach effort was accomplished in 25
;- days) Action: B. Gross (AITS #175- Due 1/31/97);k Chris Burton cXc
,
Page 4;
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-- , _.n,
-.-.-- -- ..- . - . - - . - - - - - _ - - - - .. . - . -
i
.. -
' Health Physics Status:,
*
Activity in November centered on the decision regarding RCS pipe end decon.---Discussions with other utilities and comparisons to St. Lucie <, i e accomplishe~d.~ ~
Internal discussions were conducted to identify the Outage Hr organizational, split between the SGR work and the remainder of outage work.! These decisions will support the further development of the overall HP Plan for
the replacement outagc. (i.evel 1 Project 101 supported by AITS # 131,132,133,,
134,135,136,211, & 212 - Due 3/1/97))I Accomplishments:) - Completed pipe end dg, con evaluation. Recommendation to perform decon3
at PSL accepted by management. Expected ManRem savings: >100- Defined the list of HP in'strumentation necessary for SGRP.
| - Held initial discussions with Plant HP organization on rad waste plans andj budget. More discussions will determine if the budget accurately reficcts| expected rad waste handling expenses.'
(AITS#135, Due -2/15/96)J
]" Hard spots: .
4
- Need final resolution of how HP shift management will be performed duringi the entire Unit i refueling outage. Although the SGR HP technicians and
the balance of outage HP technicians will be separate groups, we must.
! resolve whether there will be split supervision or a single on shiftj supervisor. SGRP project manager will resolve with HP Supervisor.
Kenny Payne '
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1
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. - _ _ _ ___ _ _ _ _ _ - _ _ . - __ -
-.
1
ACTION ITEM TRACKING | ;
s_ . _ _ _ . _ .. . . _ .__ _ .
...
pi al
!i a Deve oaec 10/96 SGRP ACTION ITEM DATABASE :I Items
!! = VllS/SGRP Join': 250 - :-
M Total itemsli en':Ure ,,oe,eeeee#i 200 -
i $ = Trac <s SG !P, SGT, items sim <
.
m m Opene Anc B&W Actions- 'So -
:@ Items Closed
H m 206 Items Tracked in ~~
!,00 . ........ ...;::- .
$y First Two Vlontas ' ... ' !
..
-
<.
|h 50 i, - I
@ m Wor < Control -
; !-
a Consicerino Similar's , ''
o ' '
di c September October iNovember j-
? System Month '
,
sww u:y :m. |-em jg cm g t
ee
!
-_______ -___ ____ _ _ - _ - _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - - _ _ _ _|
_
1.
ST. LUCIE UNIT NO.1'
.
SGRP BUDGET STATUS - O&M DOLLARSO iNOVEMBER 1996
_. ..
~
80,000 - -600.000 i
I
MBUDGET MONTH ,o 550,000
ei ACTUAL - MONTHr ,
- o - BUDGET - CUM ,o 500,000e--O-- ACTUAL - CUM ,
,' 450,00060,000
- 400,000'
350.000 f#
_},
I'
I40,000 - - - - -- -- - 300,0002
55 --
250,000C ,
200,000',
.
20,000 -- - 150,000
100,000
i,
# 50.000
1
'
0 -- - - - -
- --Oi
i : : : : : : : : : : a
I E e s i k ,e 1 i s s s 8w 5 4 s < m o = a
|
| !|,
(5000)CURR MONTH | YR-TO-DATE TOTAL TO-DATE YR END FCST j
BUDGET 543 i 5507 51.611 5550!
| ACT/FCST 57 5113 51.005 5160 ,
ACTIFCST VAR (536) (5394) (5606) (5390) | 1
1i
Explanation of Year-To-Date budget underrun: ($000) |
Proiect sucpert effens are cetow tne :evet estimated for tre 1996 bucget due ,
'' art: ally to enminabng the OSG Storage Facihty (Mausoieums andO
:efemng tee Main Steam Tres';e PCM untilt*e reofacement cutage (f394)'
i ($394)TOTAL exclained vanances
I, ' ' ' ' ' ' " ' ' ' ' "
. ouu...cowo ren - .4- - ,4.<a
7
|
._ - . - . _ . . . . _ - _ . .- ___. _. - __ . _ - - . . _ - _ _ _ _ . . - .
.
.
.
- ST. LUCIE UNIT NO.1SGRP BUDGET STATUS - CAPITAL DOLLARS*
NOVEMBER 1996
!
', 7,5 00,000 --- -- - - . _ _ _ _ _ _ _ _ _ . . . - 22.500.000
7,000.000_ _ .
" 20,500,000
6,500,000 --
o
fe 18,500,000
6,000,000,
i - o
i 5,500,000 ' -- 16,500.000i *i
o; 5,000,000 -' - r- -
14.500.000, ,
4,500,000 '-p
I '% 12,500,000 }3 4,000,000 - - - - m BUOGET . MONTH -- ,o'
- ic , =j i ACTUAL . MONTH ,o gi
,
i ; 3.500,000 - o - BUDGET - CUM o" 10.500.000 gI 5
- O- ACTUAL CUM3,000,000
- S= -
C ,- 2j 8,500,000 g,
2,500,000 p' -
' - 6,500,0002,000,000 ,' --
| ,o$ 1,500.000 ,e' - g - 4,500,000: ,e-
1.000.000 - - - '*" - - --- - - - -
'
a 2.500.000
500.000 r- - ~ - - - -
0 - - - -
I 5 9 9 1 % s 1 E & U ? 84 * U Z"_ __ E.. l_ _ l-. 2- '
1.500.000500,000
.
(5000),
*CURR MONTH YR.TO-DATE TOTAL TO-DATE YR-END FCST
BUDGET S1.078 513.366 574.607 S18.881ACT/FCST $484 57.824 567.343 58.570ACT/FCST VAR ($594) ($5.542) (57.264) (510.311)
Significant contnbutors to the Year-To-Date budget underrun: (5000)SGT - Revised payment senedule to reflect the SGRO senecuie enange (54.158)
. Deferred Blowoown Line anaivsis ($100)BWt - Negot:sted the enminat on of extra costs refated to Barge Transconation (SM 3)QA/CC . Recuced centractor suppen due cart:ady to enminating tne CSG-SF and
eternno the Main Steam Trestre PCM until the reeracemer.t eutage <$534)
TOTAL exclained vanances I ($5.04 5)
,,. ouw.scowone ue m mivin'^~" "* ' ' ' ' ' ' " "
Page 8
_ - - _ _ _ ___ _ _ _ _ _- -
- _- _ _ - - - . . . - .
f .
- - .
. ' escscas_
~~
se ava, son,,e an , % * ,
- e._ oso estantAt Lt VEL 2 Scut oult. . ,
--sposff 0*Dicomme ogy 9, ._ w ,,e,, 4, me m
| |,sen jCOMMERCIAL 840f I" , ,,e
. RE8iD OSGDISPOSAL .mczas -*I '' } #f. * * PNru2- ++oevue m - p- ~7"M-__._ '
: j I ,t
ao RECEIVE CSG DISPOSAL SIOS o noctes
| ' PERFORM COMMERCIALteoc''.reoc7
, , ,
3" ' EVALUATION H teocres v2soctas ,.'
I' f acci I !NEGOTIATE / AWARD ~si cme ICONTRACT 48 mocTes atDEcas, j | f,
f ENGINEERING EVALUATION &.
I ei am 27heAA | . !'' *a %YSiS SY CourR. = |M aas' '
,!2maaer '
: i i |i,
'' i % '
{sto ,ENGWEERING REVIEW BY FPL en t?me? I '
tonener i
EVALUATE i MODIFY SpePPtNG . iNti' aarse anhanaSADDLES at amtsasr amenmer I w
; se2 INCORPORATE PPL COhdhdB4(73 93 8APRBr .Jenf437
ses !007 REVIEW OF SUBMITTAL too mAPas7 naps? "
sao EQUIPMENT FABRICATION Fo asklumer maaperf!
,*CLEAR AREA & PROVIDE TEMP.
f| 522 i t i oioctonoctSERVICES '' ' "0C"' ' '' C"'
{ pr j ,
$as MOBILIZE AT SITE ao 'asocvsr } f 1** fmver ,
j REMOVE A S/G FROM i } f f|; * CONTAWMENT SY SGT o ignowr nonow *, , a . { j{ g
REMOVE 8 S/G FROM '
( 2cmov ^l {'88 I, CONTAINMENT BY SGT o ahow? ii
PREP A & B S/G's FOR,
2coi eDASPOSAL ,3''''"O*'' ' "D' C '' 20how ltof C'
w| |f! I ,
LOAD & SECURE A S/G TO'
!isoac z20ec | 'I
*, 2010 IgAngg s isotCs7 NEct?a
8
: . ,j gi ,
'. TRANSPORT A S/G TO !
.230sc iamm.I 1,
M88 ,
DISPOSAL SITE se 2aotter vtamami ;
| ,
,
PREP LOAO & SECURE 8 S/G,
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TRANSPORT S S/G 70 |
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ST. LUCIE UNIT 2PLANT AUX CONTROL BOARD ANNUNCIATOR LA & LB 6 AND 12
FLOW DIAGRAM REVIEW.
Annunciators LA & LB Annunciators are safety related. Thesubject windows 6 and 12 refer to Atmospheric Steam Dump Valves.-
The window engraving refers to "ISOL", which means the aormalisolate switch is in the " Isolate" position. In isolate thevalves position is controlled from the Hot Shutdown Centrol Panel(HSCP). The " OVERLOAD /CLOSE" engraving refers to a thermaloverload actuation and closure of the valve.
The annunciator symbol (diamond with an "A") is not shown on theflow diagram for the subject wind 5ws (2998-G-079 sheet 1) . Theflow diagram usually represents alarms directly associated withinstrumentation (PS, FIA, etc). The flow diagram stan lard STD-D-3.15 does not require items not essential to the process to beshown (STD-D-3.15 page 8).
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STANDARD STD-D-3.15^
Rev. 1- - --
NUCLEAR ENGINEERING DEPARTMENTST. LUCIE PLANT UNITS 1 & 2 Dm 08/94: FLOW DIAGRAMS
Page 1 of 32
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NUCLEAR ENGINEERING DEPARTMENTST. LUCIE PLANT UNITS 1 & 2 Date 08/94
FLOW DIAGRAMSPage 2 of 32
TABLE OF CONTENTS
PAGE
1.0 APPROVAL-
5. . . . . . . . . . . . . . . . . . . . . . .
2.0 SCOPE 5. . . . . . . . . . . . . . . . . . . . . . . .
3.0 PURPOSE 5. . . . . . . . . . . . . . . . . . . . . .
4.0 RESPONSIDILITIES 6. . . . . . . . . . . . . . . . . . .
5.0 BACKGROUND 6. . . . . . . . . . . . . . . . . . . . . .
6.0 DRAWING CONTENT 7. . . . . . . . . . . . . . . . . . .
6.1 HIERARCHY OF DRAWING RELAT'ONSHIP 7
6.2 CONTEXT 7. . . . . . . .
6.3 STIPULATIONS 8. . .
6.4 LIMITATIONS 8. .
6.5 FLOW DIAGRAM CONTENT B.
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NUCLEAR ENGINEERING DEPARTMENTST. LUCIE PLANT UNITS 1 & 2 Date 08/94 _
FLOW DIAGRAMSPage 3 of 32
_
TABLE OF CONTENTSPAGE
7.3 TITLE BLOCK DETAIL 16. . . . . . . . . . . . . . .
'
7.4 DRAWING REVISION BLOCK DETAIL 16. . . . . . .
7.5 GENERAL / SPECIFIC NOTES 16. . . . . . .
( A@ .7.6 REFERENCES '
17.. . . . . .
7.7 DRAWING NUMBERING FOR FLOW y 17. . . .v8.0 COMPUTER AIDED DESIGN & DRAFT D) 18. . . . . . .'
,m %. j,m- v 48.1 RECOMMENDED LAYOUT \ 19>
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8.2 LAYER CCINENTION ,^. L .c. .v 19.
|8.3 ATTRIBUTES [. ' O, V
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8.3.1 VAWE A IB S 1 21~ . , ). . . . .
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. 8.3.2 3QtHMN ;&~"/4CESSORY AT~RIBUTES 22.v),e. \
8. 3. 3/. INSTRUMENTAT.KsN ATTRIBUTES 22.
. \DjONTINUATIONFLAGS23-
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Rev. 1- - ~ -
!NUCLEAR ENGINEERING DEPARTMENT i
ST. LUCIE PLANT UNITS 1 & 2 Date 08 / 94FLOW DIAGRAMS 1
Page 4 of 32 |
4 TABLE OF CONTENTS
PAGE
- ~ 8.7.4 EQUIPMENT & ACCESSORIES 27. ..
8.7.5 CODE BOUNDARY FLAGS 28
8.7.6 LINE NUMBERS 28.
8.7.7 CONTINUATION FLAGS 29
9.0 SYMBOLOGY 30. . . . . . . . . . . . . . . . . . . .
( 10.0 VALVE TRACKING SYSTEM 31. . . . . . . . . . . . . . . .1
11.0 REFERENCES4
31. . . . . . . . . . . . . . . . . . . . . .
12.0 RELATED DRAWINGS / DOCUMENTS 31. . . . . . . . . . . . . .
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' NUCLEAR ~ ENGINEERING DEPARTMENTST. LUCIE PLANT UNITS 1& 2 _ Date 08 / 94
FLOW DIAGRAMSPage 5 of 32
11.0 APPROVAL
Approved by: !Manager, C ,f ' tion Management
. <
. Approved by: IPSL PEG /iroject ManagerP
Prepared by:C165D Coordinator \''< A
VA.2.0 SCOPE m s ..m
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This standard applies to lkkagrams. Flow Diagramsshall be generated wiDrafting (CADD) for
~
e se-n.f Co utar Aided Design andie # D.%t Units 1 and 2.R
It specifies the da d 7 'of Flow Diagrams, the format'
( for their prese at a .th r content by examples of what |
should and shou h not % @ pented.,
|NS |T 6This standwidqh not\b!/y to " vendor flow diagrams * unlessredrawn by tdrida Powbc 4 L ght . '/en dor f1ow c3agrams are
'
defined a \;)obe drawings supplied by an equipment vendor inrespon @ M by,.a purchase order,
,
tv a written specification unntained within, orreferenc and which depict the processflow of,feand the instrumentation requ red :: Operate andmonitor the equipment being suppl:.ed by :ne /endor.
3.0 PORPOSE
The purpose f this standard s :: pr:c;de P.e ser w:thguidelines for the prepara::cn and or ma:ntenan:e cf the St.'ucie Flant F 10 ',. : :. 5 ; r ams wh.:n .: . f:e d ::ns stency cf.
.
appearance and prcm::e : cmp:ehens:On f p an; systemoperation. Ito drawing revisions wi 1 be in;;;ated solely asa result of this standard.
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Rev. 1NUCLEAR ENGINEERING DEPARTMENT
ST. LUCIE PLANT UNITS 1 & 2 Date 08/94FLOW DIAGRAMS
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!Page 6 of 32
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4.0 . RESPONSIBILITIES|
The Manager of Project Engineering (PEG) is accountable for,
|ensuring that this standard is implemented by all individuals |preparing and/or maintaining flow diagrams.-
The Manager, Configuration Management :s accountable for thetraining and self-assessment of conformance to this standardby the Plant Engineering Group (PEG)
The CADD Coordinator :s responsible for the upkeep andmaintenance of the Flow M agram Menu program.
.
5.0 BACKGROUND
To better . understand the Flow Diagrams, certain historicaldetails should be noted and their implications understood.
The Reactor Coolant, Chemical and Volume Control, Safety,
Injection, Spent Fuel Pool, Sampling, and Waste Management !Systems, together with selected components of the Main Steamand Feedwater Systems are collectively known as the NuclearSteam Supply System !NSSS), and were originally designed |
and/or supplied by Combustien Engineering (CE)
Most Balance of Plant (BOP) systems and components were withinthe EB7SCO (the Architect-Engineer or "A/E") scope of designand sup..ly . These systems include, but are not limited to theMain S eam, Condensate, Feedwater, Heater Drains and Vents,C;rculat:.ng and :ntake :coling Water, Component Cocling Waterand Contair. men: Sp ral Systems.
CE supplied certain ccmponents in the Ma:r Steam and FeedwaterSystems and ESASCC 2:re ::mponents :r the NSSS side.Therefore, certain CE style. valve numcers appear en the BOPside and likewise ESASCC style val /e nurters on the NSSS s:.de.
:: is therefore important to close'.y cbserve the type Of nameor number used as an a: d to determine the compcnent 's crigin,past hi s t o ry , and its significance to system cperation. Inceneral, the ecmponen: .urt e -- "e Flow magram shoulda -
tconfcrm 10 the component ag ;r the field and the equipment-
f data base 'Eass?Or:10
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Rev. 1- -~~ ~
NUCLEAR-~ ENGINEERING DEPARTMENT ~~ ~- ~
ST. LUCIE PLANT _ UNITS 1 & 2 Date 0 8/ 94FLOW DIAGRAMS
Page 7 of 32
6.0 DRAWING CONTENT
6.1 HIRRARCHY OF DRAWING RELATIONSHIP
Flow Diagrams contain design basis information for1 mechanical systems in the power pla ey also depict |
-
the lor. tion of instrumentation. Fo h e systems which-
are assv;iated with the steam to n te to f eedwater i
cycle, the Flow Diagrams are am ca ions of the Heat i
the @vfonceptual document.Balance Drawings. For other sy the Flow Diagram jmay be an expanded version
|. Other documents serve the purpose for other |'
disciplines. The Main ne L' Wiring Diagram is anexample. All other drawi essentially derived fromthem, or provide a detail to amplify the.ninformation shown. t 's t refore imperative thatinformation critic 1 - ation of the plant beillustrated on t
h I
{ 6.2 CONTEXT
Other mechs al (and discipline) drawings use the.
Flow Cia %Ws tpI4 ' asis and authority fcr the designe
and c'g Nexpres ) thereon. Once the Flow Diagramshavereeerigenerate %2e their draft form, other documents
'
foll (.The General Arrangement Crawings can be made
6@(g'ihons, required wall :hickness , material, insulationqc . the layout of equipment. A ?: ping Line List is
veilbped to specify size, design and operatingdcrequirements , nuclear saf ety :_ ass, and seismic categoryfor design Of the piping. A '/alve and Specialty Listprovides information relating to valves, strainers, !restriction orifices, and other appurtenances required toassure correct system function (Note that these " Lists'have since been integra:ed int: Fass?crt) '.Jsing these ,the Piping Plans are drawn to show the routing of pipingfrom :ne piece :f equipmen :c another. ?: ping:scretrics, scme .mes ir :cmcination with spool sheets,are used :: detala :he piping and s =plify installation.Eacn f these icwer _evel documents in turn provide
': in f o rma tion as feedback to the Flow C;agrams. For} example, the iscmetri: is the document upon which the! need for high point vents and low point drains becomesi apparent. This informaticr. 12 used 10 modify andj ccmplete the flow diagram, _ine, */ a i ce and specialty7 _is s, and ?;;;n; plans.If.,
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STANDARD STD-D-3.15.
__ . _ _ _ _ -_ - - - -
Rev. 1~ ' ~
NUCLEAR ENGINEERING DEPARTMENTST. LUCIE PLANT UNITS 1& 2 Date 08/94
FLOW DIAGRAMSPage 8 of 32
6.3 STIPULATIONS|The St. Lucie Plant Flow Diagrams are process flow
diagrams. Miscellaneous items such as pipe stubs,flanges, unions, etc, are<not essential to the process-
and are not required. These details are shown on othermechanical drawings.
.
Main process lines (when so depicted) are indicative ofthe main flow paths as criginally conceived and designed.These flow paths do not necessarily coincide with currentoperational practice or procedure.
Operating positions of valves are dependent upon plant|
, parameters or conditions, i.e., plant mode. Valvepositions are normally shown as if at power, i.e., Mode1. Obvious exceptions are those systems whi:h do notfunction at power, or are not mode dependent, e.g.,
;Secondary Side Wet Layup and Demineralized Water, which '
are shown in their functional positions.
6.4 LIMITATIONS
The limitation cf individual drawings is determined bythe functional boundaries of major operating systems.Major systems which cannot be shown :n their entiretyshall be logically divided for p'resentation on multiplesheets. Minor systems or subsystems may be grouped on" Miscellaneous Systems" drawings. Operat:.ng systems are_isted and enumerated cn the System Cod:.ng 'ndex andFassPer: f:r 5 . :_ucie 'Jn :s ' and 1 respe::;/e.y-
6.5 FLOW DIAGRAM CONTENT
The f cilcwing paragraphs summarize the general centent ofthe Flow Ciagrams. Each item :.s descr:hed :n detal; insecti:ns 6.6 through 7.7 respect cely
Equiprant :.nc luding , but not limited to, the reactor,'
a steam generatcrs, steam turbine, rendenser, pumps, heati exchangers, tanks, f;1:ers, strainers, icn excnangers,E etc. Ea:P ciere Of equ;; ment cha.. bs ;n:cuely5 identif;acle D'y ':~enz.ature i n d 'c r ".u ~.r e r.
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Rev. 1~ ' - -~
NUCLEAR ENGINEERING DEPARTMENTST. LUCIE PLANT UNITS 1 & 2 Date 08/ 94
FLOW DIAGRAMS 1
h Page 9 of 32 |
6.5 FLOW DIAGRAM CONTENT (Continued)
Piping (including tubing) used to convey process fluidbetween pieces of equipment. All new process pipinginstalled shall be identified with unique line numbers.
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Valves used to isolate equipme .strumentation,control or regulate flow ./> c _ssure, relieveoverpressure, or prevent backfl Q
Each valve shall be identhe4 y a unique number as; *
noted in Section 6.8. WValve closure and - k. y godes shall be shown as I
.
detailedinSectick6. \\.
\ c:0Instrumentation it mbitor and/or regulateprocess conditi c rument shall be identified
'
by a number i 'c ' ng th strument loop with which itis associat j
Instrunebtion,sb uld be limited to the root or-
sendi. p ts.hrurt. (E a '.evel transmitter) and itsprems '-c9nt ro'l'. d , ice .e.g. a level control valve),sor (he visual Td audible indication for processmoti(!;,pving (e.g. a level indicating controller with an i
d,9npbncia tor )Simplified electrical or pneumatic |
,
siynals connect the devices and demonstrate loop '
'rm a t i o n s hip s . Further details such as instrumentisolaticn valves, ven; and dra:.r valves on instrument '
tubing, five /alve manifcids, 5 :. gnal c ondi t :.cners ,
square roo: extractors, :.nt e g r a t o rs , etc are shown on j|the Instrument Installation Detai;s and the ControlWiring Diagrams and are unnecessary cn the FlowDiagrams.
I
iSystem zents, drains and pressure tes: :cnnections asrequ:. red e: her f or prc:ess :r "yiresta .: testing. For
,
add :icnal informati:r, see Se:::cn 6.10. !
; Hea or steam tracing for pr: cess temperature; maintenan:9..
i Piping and equipment ;nsulat :n is not shewn er the Flowj Diagrams.2
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STANDARD STD-D-3.15.
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NUCLEAR ENGINEERING DEPARTMENTST. LUCIE PLANT UNITS 1 & 2 Date 08/94
FLOW DIAG"AMSPege 10 of 32
6.5 FLOW DIAGRAM CONTENT (Continued)
The physical order of connections shall be observed when|
constructing the Flow Diagram. Vent lines should pointup, drain lines point down.-
Seismic category and quality group break points. SeeSection 6.11 for more information.
|
1Connection interface points with vendor supplied Iequipment.
Continuation references flags o other drawings. |
Continuation ref erences on Air Supply lines to primitiaeinstruments and valves.
|
|Record of revision. See section 7.4 :or cetails of i
.
\presentation.General notes. See section 7.5 for details ofpresentation.
Reference drawings. See section 7.6 for details ofpresentation.
6.6 EQUIPMENT IDENTIFICATION
Equipment names and numbers are logically assigned by,
unit and process function. . hen naming equipment or |assigning unique line, valve Or instrument nurters, due '
consideraticn should 'e given to the affect on plantr.=...t.,.. =.. ....
,- : . ,.-.. a .= .-..--a.. .,
,:-o.,..,., . . . , . . . . , . . . ,. . - . . . ..,ey . , g. .
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:orresponding ncmenclature and nurters fer botn 'ni t 1 )and Unit 2. However, variations do exist. |
Equipment is named f or its f un::::n A singular .tiece of.3.,,..c..... ,
m4 ,, ..=..,c .- . .. a.+.e. . --.= .2. - . . .ea ,. . . - . . . . . . . . g. -. . . .
name en the Flcw Ciagrams. Therefore the unit must hen. + . c e..=a wgg., ,. a. c . .n , . . ,g ... . ...- .a e -.; ,. -;y -. .a ..
. . = , . , . - , . . . .-. .e....=..
'
Examples: Deborating Ion ExchangerCondensate Storage Tanka
.:.
.. s .. ,. .. on.. .. .... =. n. a. e .; .= .., a .... .=.:..,.. . . - .;~,..,,... . , a . . = . . , , , , ,... y . . .g .y .. . , . . .. .
A .v p 5 . , v A.a .n , e. .s.e**w** 3 ..e....e. e..- .e o p y . .e. 4 . v. 1 ..e . .e. gy*+ - - ,. . .*6 . * ***. a.* *' * --.. - . -
{ A c. .c ,~ .e. 44 43 .- ..g n.e~...;..~..~ .z. . . . v g..
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STANDARD STD-D-3.154
Rev. 1~ ~~ ~~
NUCLEAR ~ ENGINEERING DEPARTMENT ~.
_ ST. LUCIE PLANT UNITS 1 & 2 Date 08 / 94FLOW DIAGRAMS
h Page 11 of 32
6.6 EQUIPMENT IDENTIFICATION (Continued)-
piece of equipment is added for flexible redundancy, the I
spare is usually designated "C."
Examples: Purification Ion Exchange & 1B'
Condensers 1A & 1BIntake Cooling Water s 1B & 1C
i 1,' Multiple, train dependant equipm f orming equivalent |
functions are given unit n mber, rain letter, and a |
numeric identifier. ;
Examples: Circulating Wa s 1A1, 1A2, 1B1, 1B2Condenser W ye 1A1, 1A2, 1B1, 1B2
i ,
Certain equipment 's g with the train letterafter the numeri n.4
|
Example: e ater ters SA & 5B |
( o6.7 PIPING LIH15hDENTUi'J
~,Q> "3.,, ,
~ Ine.n. user's shan bp.| assigned and maintained by JPN (or. .
-.
se sigpee,)). The :.orw-of ling./, numbers ise$lphred below.
)*,V#flI"'C # # #Lig- nu:riers are
-- -.". a T-->-Posed ;- ' 4 =-28 ' \a-
i
7meismic Category ." s ig
~the ?.cman numeralN" ukl01 ^wBER"I" is used as a
line si:e srs7tw Asentvprefix), , es, :ne - u st S;;r
"sys tem abbrev 13::,cn,SCd an ind1V1fuS1nurrber unique ::that _ine :. n that rigure FD. 02system. For in
': example see Figu:- FD.01.I
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STANDARD STD-D-3.15.
.._ . -- - - ---
3 - - ---NUCLEAR ENGINEERING DEPARTMENT l
ST. LUCIE PLANT UNITS 1 & 2 Date 08/94
p.g. 12 of 32 l
6.8 VALVE AND SPECIALTY IDENTIFICATION
Unique valve numbers shall be assigned and maintained inPassport. The standard forTn of valve numbers isexplained below.-
i-
Valves are numbered with a prefix, system number, andoperational number, written as a continuous string.
.
Examples: V08141 V 08 141 1
V392031 V 39 20311V09238 V 09 2380
Unit designation I
Prefix *System numcer*Operaticnal number *
* Passport identification fields ,li
The valve prefix "V" is most often used (indicates gate, !globe, or check valve) but may be any letter or lcombinat.cn as shown in Passport.
The next one or two digits indicate the process system!number. Refer to the System Coding Index for the|appropriate system number. 1
The fc110 wing three or four digits indicating them e v. a * . ^ . . a .' .. .~.. e - "... w .~ua--..".a. .r= .' ". a ....at :n " " . " " , s t e m. .-- - .~C . %. p ..e. .e. .e. k p y .. ;
ne ^ ^ Q s'. no.~. t., a. , . .. a .e...'~pr, e. y e.> a. . . a. .n.. y,.. - . - ,, e .. ..
2 1. .; .-. 'n~.= aA .e. . %. z. -' . 2. 2.. 2. : .e ~; ". . i. . , A m , e.n - . .-w . . ....v . .^-.W4. '
* v . . * m. . h p .e . 7.s...'.e.., . .c. ; *s '.=\..C3. .a. . 3. m
; w o
" .v 3 w ., p. ,s.,3 . w. .a r. .= . a. ..e. . .e ,., p , . c ,. - .a 2 .' . .e. s s .a. = . , a. . .w. o. . , rs ;.< ., . e *.. .. s- . .+w
number as part of .he valve nur-ber. The exception to- k. .' s .e . .a. . a. . e .r. * - ..=.'.a..= .ee. #.-.. . ^ , ..a " ..- . .e. b. w. v^.. * ". e
" a . . . . .... . .
Other u n :. t s drawings. r
a s en o. c . a . s .e. . . e ...e - . ....e4.- example, if unitcr
2'.s valvew a .r = ,*. ,. .e.e ,
.w,..vvc... ...a. Av.. ; h,,.o . . . .
4, &O- -
.G.. h e .1 e 4 * * ' n G. ; R. . si
. ..a
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p 2p.. . .e n. . . .'. . . . .=. .c c : . n .n . ..e. 1.,. A
.....~k.,.:.,.v. . .s.3 .' .' ..e .u pg w ... . . 7 .e. a .rmz -
.+ . w <a y* *4==
,; e .m . . . . .W. g. 21..g e. . t ~. ..b. e .y .e. . b. 4 4. y A. . ; . .e. . . . . 4 p...v g>v.gD. .. . .. . . . .. m . *
|...e . . . - ..
. .c .c . e.4*. : : .AAg ..e . .k . . . ; e .e . .;. * , ' ~ .": ..y... .e A. w z. . r.. .. .. . ... . . . . . . . . . . . , , ,R aa i n . e. A- e
.. . .. ;s - .z .e . ..v..n. . - - . . .J
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STANDARD STD-D-3.15.
Rev. 1- ~~ -~
NUCLEAT ENGINEERING DEPARTMENT_ ST. LUCIE PLANT UNITS 1 & 2 Date 08/94
"' * * ****FPL e e 13 > n
6.9 SPECIALTY VALVES AND EQUIPMENT ~
Certain specialty valves and equipment (strainers, etc),
are numbered with a prefix, a system number, and a one ortwo digit unique specialty number, separate with" hyphens.".-
-
Example: HCV-14-2AHCV - M - p[
| YPrefix * (s,
System number * .
Unique specialty number * * NgRedundant equipment lett --- y
Passport identifica Y ds*
When more than one a .. lty of a given type waspurchased and th 'q s ial' number did not have aredundant equi t ded, a three or four digit,,
unique number s ded. this case the original two'
i digit uniqu er 4 a d as the generic number.\,
Process cog 1 vah numbered to correlate with thea s soc:.a t = r'rgsif loop. Though, coordination with theEquips , a in\@ ort is required for numbering, thefalve." number,s wil> r.,e similar to specialty valves.
, ,
\wi^
Exsbqt M special circumstances, valve numcers will notbe assigned to valves associated with instrumentation-bey,ond the piping root talve.
6.10 VENT, DRAIN AND PRESSURE TEST CONNECTIONS
Illustration of vent, drain and pressure test connectionson the Flcw Diagrams ncrmal'y t e rm:.na t e s at the 'ast.
valve. Caps, blind f'.ances, r guick :cnnect ::uplingsare .:: regu; red, cu: .a . ce sh:wn f:r further detail.
Ali /ent, drain and pressure temperature PX or TX) testConnection /alves s h a l . l'e s n:Wr i n ~. n e Cicsed Posi:lon
g on Flow Clagrams.
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STANDARD STD-D-3.15,
___ _. _ _ . . _ _ _ . _ _ . . . . __ . _ _ . - . . - ~
Rn. 1-~~
NUCLEAR ENGINEERING DEPARTMENTST. LUCIE PLANT UNITS 1 & 2 Date 08/94
FLOW DIAGRAMS1
Page 14 of 32,
ii
6.11 SEISMIC CATEGORY I AND NUCLEAR SAFETY RELATED PIPING
Piping which is Seismic Category I and/or Quality GroupA, B, C, D shall be so noted. Seismic ca t ego.7 andQuality Group classification is assigned to each line in-
the Piping Line List in accordance with the function ofthat line.
|
The method of indicating Seismic Category I is the Romannume ra l " I " . The Quality Group class is indicated by theletters "A", "B", "C", or "D" respectively referring toASME code Classes 1, ^ , 3 and ncn-nuclear saf ety related.All are enclosed within a square as shown on the FlowDiagram - Legend of Symbols.
Piping which is seismically supported' solely to preventdamage to other critical equipment is not designatedSeismic Category I nor is it spec: ally noted on the FlowDiagram.
Seismic and safety class breaks are made at normallyclosed er fail closed (cr to safe position) valves orcomponents. Although the absolute point of a class break:.s at the valve seat, the valve Or component is alwaysassociated in its entirety with the line of highersafety class.
The seismic and safety class breaks for trim piping(system /ents, drains, pressure test points, et:; areconsidered to Occur at the end of the last barrier
.crma113 :losed talve, :ap, :r b ' '. n d flange, shown On.
the F1:w ::agra. and ~.ay r. : te ; r. d; : s t e d . : f ,0 :Sp crblind lange is shCWL, One .s '0; requ ree to ee :n.
place. If, however, One ;s shown :n the Flow Diagram.then :: :s to be considered a res;;n Baseline, and theclass break Occurs at the tap, Or blind flange, ,unlessC;herWise ir.d1Cated.
6.12 VALVE CLOSURE AND LOCKING MODES
R /alves shall be sh wn Oper r :1: Sed as requ. red f;r4
"g norma OEera 1Cr . 3 */ e s ei n l C." are T.O. r** a l . V nrCttle.
'
, .= . o. . .e...,e : .e -,.
. . .. . m .e ,%..,._... .- ..2..-=e..- .. ...=e... . . . , .
s. . .2
g -.e .. . . p. .e.
$ '
o e. z.e. e. - - y = . 2. .~e% . .
:.ae *
e : ..ay e. ,;;, v.. . . v. e .c ... . . .e.
4 A.-.r.. ....e
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STANDARD STD-D-3.15.
Rev. 1- ~ ~ ~ ~ ~ ~~'
NUCLEAF ENGINEERING'' DEPARTMENT ~~ - ~~~''-
ST. LUCIE PLANT UNITS 1 & 2 Date 08/94PLOW DIAGRAMS
Page 15 of 32
6.12 VALVE CLOSURE AND LOCKING MODES (Continued)
An example of this is the Safety Injection System whichis shown aligned for emergency core cooling in the eventof reactor coolant system depressurization, but does notexperience flow during normal power o - tion. Symbology-
s h a 1 1differentiate ^
Vt h e, g gg
differencebetween' locksphysically $?y \/ M ~located on A mgmgthe valve and wr(}those in the 'm <control room. aasra tocAD COSD
S "NNSee figureA00vFD.02 for an a FC |LC/C|
example. M i t #,;A-462 ) 7[-
Valves sha V2187I be indic d hJ 9
as 1 (,.
open' w trAlocke d )d (Q)~ as a .. s Pigute FD.02whent .D e \A i c,B$ h e ,' g
nlocks are necessary for nuclear or personnel
da f dct/ . Valves locked administratively for equipmentseqcrity and Other similar purpcses are not to beaddressed on the Flow Clagrams.
|!
7.O DRAWING FORMAT !
7.1 DRAWING LAYOUT
Equipment shall be arranged er the Fl w Diagram in amanner which emu _a:es physi:al _aycu as much as ispra :::al. e;her so arranged, the drawing shall becr ented sucr :ha: ':c r t 'r _s a: :ne ::p cr :: the left of
: the drawing. If a physical .aycut is not prac : cal,{ equipment shall 'c e arranged such :na: ilow begins at ;I equipment in the upper left corner cf the drawing,i cnt nu;ng from left :: righ:, r if a : rcuit us flow,j :n a Cl:ckWise dire :: r.7-
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STANDARD STD-D-3.15 l<
1
_ . _ __ ._ ___ _ - gew. y - - - - _
|NUCLEAR ENGINEERING DEPARTMENT |
ST. LUCIE PLANT UNITS 1 & 2 Date 08/94 ||
FLOW DIAGRAMS |
Page 16 of 3211
7.2 DRAWING SIZE
Drawing size shall be in accordance with the |
Administrative Procedure, General Drawing Procedure JPN- |AP 4.8 as applicable to Flow Diagrams.|
-
St. Lucie Plant Flow Diagrams shall be of uniform size, |30" x 42", commonly known as "G" size, which is denoted '
by the letter "G" in the drawing number. See attachment"A" for an example of Flow diagram format. |
Example: 8770-G-081 D70 2 - vel I
I tDrawing number pref:.x|
Letter size of drawing,
Sequential drawing number |
7.3 TITLE BLOCK DETAIL
Title block detail shall be in accordance with theAdministrative Procedure, General Drawing Procedure JPN-AP 4. e as applicable to Flow Diagrams . The two or threeline :::le shal. state :he drawing type ( :. . e . FLOWD!AGRAM) and the applicable system.
Example: FLOW DIAGRAMHEATER DRAIN & VENT
SYSTEM
7.4 DRAWING REVISION BLOCK DETAIL
Revision block detail shall be in accordance with theAdministrative Prc:edure, General :rawing Fr:cedure JPN-AP 4.6 as applicable :: Flcw :agrams . See attacnment "A"f or 10ca::.cn Of rev .sicn bic:k :n F;;w : .agrar f:rmat.
1
: 7.5 GENERAL / SPECIFIC NOTES1
r
l fj General Specifi: .0:e5 shall ce in a;;;rdance x;;h theE Adminis t rat ive Prc:edure , General Drawin: Frocedure JPN-I AP 4.E as app 11:able :: Flow : agrar.s ' _res a t : ?. :hmen ti ' A '- f:r _::st:.:r :f .::ss :r F 12., :;5;rar f:rra:a
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STANDARD STD-D-3.154
Rev. 1-- ~' ~~
~ NUCLEAR ENGINEERING DEPARTMENTST. LUCIE PLANT UNITS 1& 2 Date 08/94 _
FLOW DIAGRAMSPage 17 of 32
7.6 REFERENCES -
References shall be in accordance with the AdministrativeProcedure, General Drawing Procedure JPN-AP 4.8 asapplicable to Flow Diagrams. See attachment "A" forlocation of references on Flow Diag ormat.--
.
7.7 DRAWING NUMBERING FOR FLOW DIAy
All drawing numbers shall be ssi d in accordance withFPL Administrative Proce e JPN-AP-4.6, NuclearEngineering Department D awin' umbering Procedure forSt. Lucie Units 1 & 2.
O ''v' ,1St. Lucie Unit 1 Flow la ams N numbe re d " 8 7 7 0 -G . . . " .
St. Lucie Unit 2 D. rpms ar umbered " 2 9 9 8 -G . . . " .
All NSSS Flow 'a s ha een grouped into the " . . . . -'
G-078" ser' I a ig sheet number assignedk correlates ot sys m mber of the operating system,
e.g., th mica M ume Control System, System 2,.s :.n thg . t ( ep ser:es, ano the Waste Management,IS y s t e,m - 6 ' i s in\ whd I" Sheet 160" series. (The sheet
. nAnumcer is the la% v three digits of the original CEdrawihq,.r.umbe r , and has been retained for continuity.)Q y'
BbP Q'ers "emyst Flow Diagrams have been assigned drawing
nuhb .-G-079" and above. "nlike the " .-G-078".
seFEes, these drawing nurters .n no way carrelate to thesystem number. However, the systems have been groupedinto sheets of a drawing nurter. For example, all steamsystems (Main, Extraction, and Auxiliary Steam and AirEvacuation Systems) are shown on multiple sheets ofdrawing number "G-07 9 " , and the Feedwa:er and :ndensateSystems are shown on the "0-;8:" series.
Steam Generator Slowdown Trea: men: Fact.;;y 53BTF) FlowDiagrams are numbered "3509-G .. and consistent with"
,
other SCP systems, the drawin; number d:es no: 0;rrelate: to tne system._'
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STD-D-3.15 i
. _ . _ _ _ . . . . - -
NUCLEAR ENGINEERING DEPARTMENTST. LUCIE PLANT UNITS 1& 2 0'" 08/94 |
PaEn,Page i g of 32
FLOW DIAGRAMS
8.0 COMPUTER AIDED DRAFTING l
Nuclear Engineering has developed a customized AutoCAD basedi
Flow Diagram Program for St. Lucie Units 1 & 2. The program I
contains symbols identifying various components / equipment"
(asan integral part of the process flow system line work, notes, '
tables, etc. as defined in this standard.
Input consists of placement and manipulation of symbols, linework and text for use in AutoC.C. Output consists of a Flow
iDiagram drawing and sorted, printable component report ofattached attributes.
St. Lucie's unit 1 & 2 flow diagrams have been drawn usingComputer A:.ded Design & Draf ting (C.C D) to ensure consistencyand standard symbology. New flow diagrams and revisions to '
exi s t. ing f1cw diagrams shall be completed using the AutoCADbased Flow Ciagram program. NO MANUAL drawings cr revisions'of Flow diagrams shall be accepted.
M M M M CONTA!NWENT 90VNORY J4R *0if (COLOR. BLUE)
maamme a summe a summes a mamam SUILO:N; OJiiiNE JyER *a:f (COLOR. uACENTA)
WAIN PROCESS LINE JTR '# (00 LOR. OREEN)
SECONDARY FROCESS LINE LAER 'S' (COLOR CYAN)
- |NS'RUMENT L:NE >4R " ' (COLOR YELLCW)
E.E: R: a 5::w .:sE >sa :r (00;0R. E;)----------
^
1 ^
1 RAD!ATION SIGML LAYER 'S' (COLOR. CYAN). ,
- Di TRACED > i; ''' (00 LOR E a0*), , , . (#AT ~RACINC FUN 07:0W)
- 97 'RA0E0 s iR ~~~ '0OLOR SL.0*;+ + + + (-EA' ':AO:N: as00sE:)
- = 2 - :AD:..AW '.2:NO .AER '' (00LCR YE L;*)
,, . , - a' ;NELMATIC S:0W LAIR ''' ( 0 LOR ELLO*)'
.t!
j D"AUS* CR OR SCREEN 34R D* (00aR uA;ENu)------- - -- ---_ ._.
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STANDARD STD-D-3.15 ;*
\
Rw. 1 I'' - ~ ~ ~
NUCLEAR TIGINEERING DEPARTMENT ~ ~ ~ ~ '-~
|ST. LUCIE PLANT UNITS 1 & 2 Date 08/94
FLOW DIAGRAMS IPage 19 of 32
|
8.1 RECOMMENDED LAYOUT
Place major equipment in their appropriate locationfirst. Draw pipe, according to the flow hierarchy (main,secondary, instrument etc. ) connecting the equipment . Seefigure FD.03 for Q )
--
complete list of g' 3, i,,
line hierarchy for ve l
flow diagrams. . ,/),608 |
. ss. '\V
,
Avoid crossing oneline with another,
i1/8' GAPwhere possible. % (__When lines have to
p g\, icross one another,
.j Igfollow the flow ,
hierarchy for Q '
determination A~ Nwhich line M D Q |break. The 1' t
'
bc broken 11 Mi have a 1/ ga n
Ieach si f ti1%unbroken . 'e S#~ Ng
_ussr,
ficur m f 4 f 'ck..- ~
de A e N%Figure FD.04
p b'.8.2 LAYEkiCONVENTION
All drawings shall contain the layer convention setup inthis standard. All entities inserted into the drawingsusing the Flow diagram program correctly will be placed.
on the appropriate layer.
There are twc exceptions :: the above statement : t ext notcontained n a symbol attribute and miscellaneousequipment. All free ferr text snal_ be pu: cn the layer"0" zerc) Miscel.aneous equ;pment w;__ ce manuallydrawn cn the layer "E" : Equipment) ~f a tag number issupplied, the user will insert the block containing the
: attribute information for equipment. The block isi located at " 2 4 - E " e n t he T.enu t a b le f or the Ficw DiagramI Program. Figure FD-05 lists all the standard menui program layers tha: shall be :entained ;r ea:P file.t.O
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STANDARD STD-D-3.15.
._ ._. _. __ _. _
_ _ _ _ _ _ _ . -
NUCLEAR ENGINEERING DEPARTMENTST. LUCIE PLANT UNITS 1 & 2 Date 08/94
FLOW DIAGRAMS
MMP ' MCol.oR: DESCRINTIOW ""YENTrrES"SHOWNUNR?NAMEi .. . w- .c.. 'byg
O White Zero All non. intelligent components,
and text.
BD Magenta Building Outline All Building Outlines.
CB Blue Containment Containment BoundaryBoundary outline.
E Cyan Equipment All equipment
EA Magenta Hidden Line Exhaust Air or Screens.GRID White Coordinates Drawing Coor. Grid
1 Yellow Instrument All Instr., tubing, signals, instr.valves and instr. text.
ID Red Instr. Dotted Electrical signal line work
P Green Prirnary Main flow piping and valves
HEV White Revision Revision clouds
S Cyan Secondary Secondary flow piping andvalves.
NSR White Sticker Nuclear Safety Related
T White Tags Valve and equipment tagnumbers
f White Vellum Flow Diagram format.V
Figure FD-058.3 ATTRIBUTES
All valves, equipment, instruments certain,
accessories, the fi w diagram format andcontinuation flags have attributes a ~ ached. Aftereach is inserted in;0 the drawing, the user will be.rrompted :: enter the appr:gr:Ste informaticn.
.n -
4 ce:::cris 8.3.1 through 8.3.5 . s: -he attributesj 20r va ves. equipmen:, :nstrumen 3, f;0W diacram<- - -- - - - . ~ = - :... .......... __agg [ g s p g - ; ; ,. g , .,g,, - -.. _;
_
' e5 ,[ [g,j ;"f. - ,2 - :3.....:....- . . -
****** *** * * - * *e Av -e ef"a sF~CO s, see crawing 2,;9-3-;~3 Shgg ,;;;
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-
STANDARD STD-D-3.15
Rev. 1- - - - -
NUCLEAR ~ ENGINEERING DEPARTMENTST. LUCIE PLANT UNITS 1 & 2 Date 08 / 94
i FLOW DIAGRAMS
% Peg. 21 of 32 j' ,
-
8.3.1 VALVE ATTRIBUTES
When valves are inserted, prompts must beanswered to complete attribute processing.See figure FD.06 for a complete list ofvalve attributes.-
/) .ATTRIBUTE PROMPT h EXAMPLE
^ VTag Number NQisg V09235
Locked Mode h le LC or LONV/
Failed ModeQ N / V4ibie FC -
k )thenSeismic I,
Ge[kbgx. HidMn 212A
tdgTk Hidden VL E,
( h Grofh) Hidden A. B. C or Dk \N //NNValve CB>rd.v' Hidden C3,, %
_
\ t
m' \,Y,; }'- \^ ' ,,
. Figure Fd.06.
$ %
C' The only valve attributes with defaults are|p ^ ;
Component type and Sub-type fields. The it\,) Component type shall always be the code
,
4 -' value "VL." The Sub-type code value shallbe set for the type of valve that is being
; inserted into the drawing. For example, aBall valve will have the /alue "A" and aCheck valve will have the value "C." Peferto Passport for a ::mplete 'is: of Sub-type::ce :a.ues.
There are two c;;ua:::ns wnen the 5;.b-type'
: ode /alue shal. :hange f:r valves. Thefirst ;s when adding a valve accessory oroperator to a Cate /alve. -n this situation.,
t there shall be no 'calue for the Sub-type.i The second situation :s wnen adding a| Solenoid Operator :: ar; calve type. The!, S ub - :v. . e cal e 2n51. 5..;5v.s 'e "SV."r.
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STANDARD STD-D-3.15.
. _ . . . . - - - _ - - - - - - - - -
3 - -- -NUCLEAR ENGINEERING DEPARTMENT
ST. LUCIE PLANT UNITS 1 & 2 cate 08/94 :
FLOW DIAGRAMS '
Page 22 of 32
8.3.2 EQUTPMENT & ACCESSORY ATTRIBUTES!
When equipment or accessory blocks areinserted, prompts must be answered to j-
complete attribute processing. See figure|FD.07 for a complete list of equipment'
attributes.
l
ATTRIBUTE DISPLAY EXAMPLEPROMPT
Description line 1 Visible Condenser
Description line 2 Visible 2A
Tag Number Hidden CNDSR 2A
Seismic Hidden I.
1
Quality Group Hidden A. B, C or D
Figute FD.07
8.3.3 INSTRUMENTATION ATTRIBUTES
Xhen instrument blocks are inserted, prcmptsmust ce answered tc complete attributeprocessing. All attributes are visible. Seefigure FD.08 for a ::mplete _tst of:nstrument attr:butes.
ATTRIBUTE PROMPT EXAMPLE
Panel or Rack Number 202B
Function Tl
System Number 09
Identification Number SA2
g Switch Position PB
j Temporary Flow Element T-
3
h Fi7ure Fr.09+
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STANDARD STD-D-3.15.
Rev, 1'- ' ' ~ ~
~ NUCLEAR ENGINEERING DEPARTMENT- ~~~ -
ST. LUCIE PLANT UNITS 1& 2 Date 08/94FLOW DIAGRAMS
Page 23 of 32
8.3.3 INSTRUMENTATION ATTRIBUTES (Continued)
When inserting instrumentation, hyphe'snshall be removed from the three fieldswithin the symbol that makeup the channelnumber. If the suffix is to long for-
the third field, it ma rtially placedon the second fiel S number). Inthis situation pl . h hen between thesystem and suffix n' See figure FD.09'for examples.
YCOeTCT lhCO@TCT JAGIRWENTT TAC
PX FX-PJ 4
09 09 09-2 09-8A.M 8
P. 3 9 PR 1rRbg (i g ,g ,gi,
9 9 d '9 d '9- / \\
r%r% 1 r51v i 1(
k j j k@ j k@ j k@~ .s ' ^ _s
\p;> ' n
sVjp~J Figure FD.09
iO ,%BW 4 CONTINUATIONS FLAGS:, (, '
-.
'. When Continuat;0n lags 5re inserted, {j-
prompts must ce answerec to complete,
attribute proces sing. See figure FD.10 forexamples. :nstrument Air Continuation flagsshall not have the System number attribute. ,
1
ATTRIBUTE PROMPT EXAMPLE
Desenptsn Cont.
To or From Dwg No 2998 G-080 SH 2A
System No. RC j'
.
j Dwg Coordinates (E-7) |'
1
) Figure FD.10~n
C -
;
e.
.
.
. .
STANDARD STD-D-3.15,
._ .._ _ _ .. - . - -
3- - - - -
NUCLEAR ENGINEERING DEPARTMENTST. LUCIE PLANT UNITS 1 & 2 Date 08/94
FLOW DIAGRAMS
h Page 24 of 32
8.3.5 FLOW DIAGRAM FORMAT ATTRIBUTES
When Flow Diagram formats are inserted,prompts shall be answered to completeattribute processing.-
,. . I
" ATTRIBUTE EXAMPLE -_
Dwg No. 2998-G-080
SheetNo. 2A
Revision 0
FPL Florida Power & Light Company
Plant St. Lucie Plant
installation-Unit 1983-890 MWe Extension - Und 2
Title 1 Flow Diagram__
Title 2 Feedwater & condensate
Tale 3 System
Scale None
Date 1/12/94
Discipline Mech
Drafter (Name of Drafter)
Checker (Name of Checker)
Respon Eng Org Plant Engineenng Group
NSR1 Nuclear (Nuclear Safety Related Box)
NSR2 Safety Related (Nuclear Safety Related Box)
Cadd File No USM00001 (Assigned by FPL)
Upper Dwg No 2998 G 080 (Upper left corner of Dwg)
Upper Sheet No Sheet 2 (Upper Left corner of Dwg)
(z F1gure Fd.1:
hi
!-so
;
!.-- -.. --
i
l.
'
!-
STANDARD STD-D-3.15 !c,
Rev. 1~~ ~ ' - -
' NUCLEAR ~ ENGINEERING DEPARTMENT,
!
_ ST. LUCIE PIANT UNITS 1 & 2 Date 08/94 |
FLOW DIAGRAMS I
Page 25 ot 32
8.4 ATTRIBUTE REPORTING -
I
l
Provisions have been made for the extraction of the 1attribute data to the system data report file for hard icapy printing of customized reports. |
To create a customized report, ed t "Reptemp.txt"using any of the attributes li d sections 8.3.1through 8.3.4. Then run the L t ne " Report" fromthe AutoCAD command line. The (.TXT file) can beloaded into either dBase E For additional.
information on extracting at 'E e information, referto the AutoCAD Reference Manu
! 8.5 TEXT STYLE
The default te 's .a . d andard" (Font name,Flow.shx). Text i inches, with a width f actor.
of 0.8 inches
k Use the te st "L e (f ont name, Large.shx) for all
Equipmenq, &.p/p;4ccri etail Titles and ContainmentSoundary -desc o n Text height is .125 inches, witha wid@fdcitor of w } inches.
5s- .z
All / shall be typed in Upper Case. The onlyv
e#Mhgt h will be abbreviations that are normally shown ' i
ih )qwer 'case. For example, the word Hydrogen IonOcg entrator is abbreviated as "pH."
Text should be placed herinentally on the drawing. Textthat is placed vertically, shall be rotated 90 degreeswith the text facing to the left of the drawing. Forexample, all valves placed on vertical lines will havethe talve number and modes rotated 90 degreesautomatically by the Lisp routine. With the exception ofthe valve numbers and modes, rc:ating text verticallyshould be avoided.
The Ficw Clagram fcrmat has a mix ure of tne text styles': " Roman 5" and "RomanD." The forma: shall not be exploded
i, :: change r alter the f:rmat.z:Is7
$
b
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5m
.
STANDARD STD-D-3.15.
. . . . - . - . - - - _ _ _ _ - - _ - _ - -
3-
NUCLEAR ENGINEERING DEPARTMENTST. LUCIE PLANT UNITS 1 & 2 Date 08/94
FLOW DIAGRAMSPage 26 of 32
8.6 REVISIONS
Flow Diagrams are maintained in as-built condition,therefore, revisions will be required based on variouschange documents.--
-
All revisions shall be back circled using the"Rcloud.lsp" routine. The LISP routine will prompt the.user to sketch a line counter clock wise around therevised portion of the drawing. The routine will thendraw arcs on the layer "Rev" in place of the sketch line.
8.7 INSERTION OF SYMBOLS
All symbols shall be inserted into the drawing by meansof the Flow Diagram programs"s menu tablet . Most symbolsare inserted using the LISP routine "FFIN.lsp." TheFPIN.lsp is programmed to insert the symbol on thecorrect layer. Those symbols that are inserted into thedrawing using AutoCAD's " Insert" command have the layerpreset. For additional information see section 8.2,Layer Convention.
8.7.1 GRID AND SNAP
All Flow Diagram CADD files shall have theGrid set to 0.;25 n:hes and the Snap set to0.0625 :nches. All f les shall be drawn andrev sed w :h the G::d and Snap se: :n
|
|8.7.2 VALVES & ACCESSORIES
All valves shall be inserted en either a. se:Ondary r nstrur.en _ r. c . The:........
"FPIN.lsp" r o u t :.n e .:.. place the talve on -he::rre:: .ayer and 'reak the _ r. e , ncecinserted.
|
[ The 1_s; rout.ne w ._ reduce ne 21:e af the |} /alve a::Ord:r.; :D :nr . .ne ar.c ayer tha: the jz ca _ te .2 _nsert r a _ ces sre r; aced :r !i F r : r.a r . ._r.es a: 1 . '. ' , S e r :r.d a ry _ _ r. e s =~ ^ i
3 I,,,
i
1 !i i
f l
7.'
E
B-
_ . , _ _ _ _ _ - . _ _ . _ _ . _ . . _ . - - -
?*
*
STANDARD STD-D-3.15t
~
R ev. 1- - ~~ ~~
NUCLEAR ~ ENGINEERING DEPARTMENT_ ST. LUCIE PLANT UNITS 1 & 2 Date 08 / 94
% { page 2 7 of 32
8.7.2 VALVES & ACCESSORIES (Continued)-
reduction of 75% and Instrument lines (beyondthe root valve) at a reduction of 50%.Valves may show two diff types of mode,
-
Locked or Failed. E s a separate-
attribute field and 1 t around thevalve. Valves that s locked closedor open at the contr om shall be shown- with a box drawn roun he attribute and a"/C" after the abb i on " LO " o r " LC . " Seefigure FD.02 f an ample,
The "FPIN. P q 1 e shall set the correctrotation f val as. The rotation shallbe dete i y - rotation of the linepicke
O O, Al al ad essories have their origin
i p set 4 e enter of the valve symbol.\. 1 ve a es ries and operators have theirin pein t to the center of all valvem
*)cgMotor a W SolenoidIr
Operators shall be shown 1
.\ // with a circle leading to the valve. The.
_4." circle shall have either an "M" or "S" to,
jdesignate motor or solenoid operator. See<
ifigure FD.02 for examp]e. '_.
8.7.3 _If TRUMENTATION & ACCESSORIES
All instruments and accessories are set to thelayer ":" after being :nser:ed :nto thedrawing. Ir.st rumer.:s wi n brea k the .:.ne theyare being atta:ned ::. T ". e Orig;r point ofall instrumen:s Sr.: accessories _s set to therenter Of ne .nstrument symbcl
Ie, .~
tg 8.7.4 EQUIFMENT & ACCESSORIESe
1 All equipment :s set ;; the _ayer "E" after. ,
reing i r.s e r : O in!- . r.e Or 3w; r.; .
5Ei%E
5,
1
~
|-)
.
STANDARD STD-D-3.15 {.
_ _ . __ _- - -- -. -
3 - - - - - -
NUCLEAR ENGINEERING DEPARTMENT |ST. LUCIE PLANT UNITS 1 & 2 Date 08/94 iFLOW DIAGRAMS
h Page 28 of 32
8.7.4 EQUIPMENT & ACCESSORIES (Continued) j
The origin point shall differ for each piece.of equipment. Only certain pieces of equipmentbreak the line that they are placed on. For
-
those symbols that do no break the line they-
are placed on, use the AutoCAD command" Break."
Certain pieces of equipment may need to bescaled after being inserted into the drawing.For this reason, attribute information hasnot been attached to all the equipmentsymbols. Equipment that requires adescription or tag number after being scaled
|shall have the appropriate bl'ock inserted f rom|the Tag section of the menu tablet. See '
attachment *B" for example of menu tablet.
All equipment accessories are placed on thelayer "0" once inserted into the drawing. Allorigin points are set to the center of thesymbols. All symbols will break the line that
|they are placed On, except for those symbols '
that are normally placed at the end of a line.
8.7.5 CODE BOUNDARY FLAGS
All Code Soundary Flags are placed on the.ayer ":" after reing inserted nte thedr5 Wing. T".e Cri?;T 901n: .s set 2.1 inchesfrCm the hCttCm of the sym.Ocl.
When PCssible the CCde EOundary Flags should'
be placed on the top of the valve symools,leaving the valve tag number : entered underthe valve symbcl.
8.7.6 LINE NUMBERSft>
A '. . :ne numcers are placed :n the layer "0".
! :: f : 9 r rein; ; T. s E r ' 9 5 _.-*.1 *"9 :1 f..i n g . T ",. e- .
a e - oe o e a w e Y w e .* * 6 4
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3
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-
STANDARD STD-D-3.15.
Rn. 1- ~ ~ ~- ~ ~
NUCLEAR ~ ENGINEERING DEPARTMENTST. LUCIE PLANT UNITS 1 & 2 Dat, 08/94
FLOW DIAGRAMSPage 29 of 32
8.7.6 LINE NUMBERS (Continued)
All line numbers shall be placed on a line.Line numbers shall not have leaders pointingto the line they represent. The LISP routineis set to break the line each end of the-
symbol. If the line n not placed ona line the LISP routin i omb.
N Y/8.7.7 CONTINUATION FLAG V,
Continuations from p e drawing to anothershall have con 6hq uanon flags at the beginningand end of -ene 'ne, f or each drawing. Thecontinuati ~7 gs mai have a description lineand syste aQ the location of thecontin o . co inuation flags shallhave -
i d sheet nt.mber and drawing
?p% C'hcoo n of drawing the pipe continues
'
'*p- .~ .~,
r- ) *f cwilarlw nAc10 Miawxt Air twxmW <L
,'
,__
(2775-N85 SH.2A2 |'
"I,. ,, ,
Nf E/P} |\
_ . .
F, ; 9021 j,
')i\ I I: e ! ,
! E770-G-085 Sw.2 57' <;:''-4
- t
Tsw M!haEWT AIR 4ArincCOVTio11M /2A: |
'70 LCV-11-;ES(2998-C-081 SH.1 (G16) {
p WFM/ C%71UTIM /2AC
,-12[ -]N.- ~ .,
2935-:-250 E' .20'-
|,
,
/ ' 5) i ji
! 'v/ i
j | FEEDWATER PJVP 28; Lz
5 Fi;;r.:re FD.1:
5 1'
!
E |5 >;
5: !~ 1
b:1
_ _
1
1
STANDARD STD-D-3.15 |,
_ . . _ _ _ _ _ _ _ . _ . _ _ _ _ . _ _ _ _ -
Rev. 1--
.
NUCLEAR ENGINEERING DEPARTMENT |
ST. LUCIE PLANT UNITS 1 & 2 Date 08/94FLOW DIAGRAMS
|
Page 3 0 of 32 |
|8.7.7 CONTINUATION FLAGS (Continued) l
Continuation flags for Instrument Aircontinuations shall have two separate flagsthat show the continuation to and from the
-
drawing "g-085." Continuation flags thatcontinue to the Instrument Air drawing fromanother drawing shall only have the InstrumentAir drawing and sheet number and drawing gridcoordinates. Flags that are on the InstrumentAir drawing a'n d continue to another drawingshall have a description, drawing and sheetnumber and drawing grid coordinates.
Pumps that have necming f1ow from anothersystem shall have a continuation showing thesystem, drawing and sheet number and drawingcoordinates. See figure FD.12 f or examples ofall continuation flags.
9.O SYMBOLOGY
|
Flow diagrams shall depict equipment, ;;;;ng, valves,1,'
' instruments, etc by the use of standard symbology int accordance with the Flow Diagram - Legend of Symbols, drawing2998-G-076 Shee 100. |
|
< 1
In addition :: the Legend of Symcc.s, :ne Au:cCA: based menu |
program's tablet nenu >;:.11 :cn t a ir- S._ syr2clogy used fordrawing and revising the It. Lacte un : . i : f':w c:agrams. !
;
.
) .efer :c at:achmen: "5" fcr ar examp.e :f m=nu tablet.si
The symbol legend wi.1 cnly be shown en drewing 2996-G-078Sheet. 100. Syrbols that ure used repeatedly wi.. " ave an i
',
.
AutoCAD block created w:.th ne apprcpriate at:ributes. The: CADD Coc"* -=*' #~ ""~'=a- r 7--ca - ="=~ -= -=er- ='"'e' for the maintenance :f ex.s. ng Ficw ::agrar syrrc'.s and the
creat.cn cf .=w syrr; . Syric.s are .c: :: be exploded for'i;ering their appearanze cr Cha"g ng a: r:bu:G nicrma :cn bycesigners or drafters.
ok e
-
:.
|t
2e
542.e
E
.B_ _ . , ._n . _ _ . - - . . . . _ - - - ~ - - "
9
-
STANDARD STD-D-3.15.
Rev. 1- - -
NUCLEAR-ENGINEERING DEPARTMENT- ~ ~ ~-
ST. LUCIE PLANT UNITS 1 & 2 Date 08/94FLOW DIAGRAMS
Page 31 of 32
10.0 VALVE COORDINATE SYSTEM
All valves shall be tracked by the coordinate system on thedrawing. This information will be up loaded to Passport forreferencing.
..
,
11.0 REFERENCES A N '/(h,'2 V
The following documents are referen't , /Merein and containinformation necessary to the pre atioo'of Flow Diagrams.
SystemCodinggndeI.-@'8770-A-001.L-1)
ss A2998-A-001 System Cod:.nrIndG.' kPSL-2 ).
8770-B-053 Valve OpAr ( l D. t.
r Index (PSL-1)e. L
Valve %\ xich^(humberIndex2998-B-057A- (PSL-2)
~ s'
8770-G-078 F iagY egend of Symbols. s
l ;
eet ( 00 ) PSL-1) |
- '% ;s2393-G-378 NM Czaghm - Legend of Symbols._
.
,m h., Sheet 100 (FSL-::,
!
,-s.. .c. ..
\.d)s12.O RELAT M RAWYNGS/ DOCUMENTS |
i
i
Changes N de to Flow h agrams T.a y affect the followingdrawings / documents wh. h T.ust be reviewed and evaluated for:.mpa c t .
System Coding Index.
'laive C; era: 10 na l ' u-t e r : n de:-
General Arrangemen: Tra...n :.
F:.ging :rawings.
g Large Ecre F ping Isometr;;5.
! Small Ecre Piping :sometr; s.
i
j Instru.ent :nt:a..i ::r :sta: s.
s82
%E
5*
i
I
%
.
STANDARD STD-D-3.15*
-- . . . . . ..- - _ . . - . -_
3. --
NUCLEAR ENGINEERING DEPARTMENTST. LUCIE PLANT UNITS 1& 2 Date 08/94
FLOW DIAGRAMS
i
12.0 RELATED DRAWINGS / DOCUMENTS (Continued) ||Control Wiring Diagrams '*
Safe Shutdown Analysis~
. <
Essential Equipment List+
Equipment Data Base (Passport).
Updated Final' Safety Analysis Report.
Plant Techn cal Specificaticns: .
Plant Operating Preceduresj .
FPL Nuclear Division Configuration Management Manual.
)
.
e .
%-
ii
3
k
$e:;E
3m
_ _
.,
-_ -- . - ~ - - - - . . - - . - - - . . . . . . - . -. - . .- .--- -.-.
9 P..
,
';!i e-
*
A
I - 205 W a ei t e ''anagemen t and Chenical and Volume Control System) -
2De Fnsin cred bafet. Feat.7as Systems-
.
fThe heating ventilatit. control board ( P/( E ) and plant auxiliary boards arefree standing ve-ti:,C. 'a n a r d.s with contrn; sw i t c h e e, , indiccting and record-'
.ng display in:::i umer a : ion on the front <! tne boards. For a discussion |of plant heatt: ventilatinu and air coaditioning systems see Section 9.4, !
2
The Plant Auxilier) 0 ;rol heard in one ranti section of heating-Venti-i lating and Planc Au;;il ' aries Control Bocro. On the safety sections of the'
board (SA and Sh reet;.a), two salc ty-re: utec redundant annunciator LA and)
LB and atmospherac steeri dump controls are located. Tne atmospheric steamdump controls at o duplicated here an a t ackup to the controls located on RTG
;board 202 cud ".' Hot 25ut down pane l . The tafety section is separated from j
the non-sa fety - c t s : sf the plant uexiitary control board in accordancewith Regulatorv Gntre 1.75 (b1) (refer ta FSAk Tabic 7.5-1).
The hot shurdcwn ?'nel is a free standic wnt; cal board .it. cesaroiswitches sad indicati;g .iisplay instrumentation on the f ront of the board.For a discussion of en ergency shutdown f rom out side the control room seeSubr etion 7.4.1.5.
The display instrurnent switches and indicating lights are functionally,
grouped on the boards and identified with nameplates for each component.The safety related display instrumentation located on each of the abovementioned boards are listed in Table 7.5-1,
b) Annunciators
The annunciator vindows are located on the upper vertical portionof the RTGB and ifVCB and are functionally grouped and f orm non-safety display nits.
The annunciator ,sindows on each board are associated with thesystems havi., instrumentation and/or controls on that same board.
The annunciator initiating circuits, generated by the Class IEdevicee are connected to the annunciator logic through isolation. de-vices.
Safety related ununciator window display units are provided on theplant auxiliary board with 16 windows for channel SA and 16 windowsfor channel SB. Table 7.5-3 lis,ts the safety related windows. -
e.. Audible alarms, together with visual displays, alert the operator ofdepartures from normal operating conditions, such as trips, by-passes, overrid is of-WaTety signals or ment faults. The
*
gable <.7-1. FW, M V '' M Wd W{earrangem Je L-af .ununcigtor windows is s own n igure li ted in.
' * * t* s
7.5.1. Bypass en? Inoperab e Status Indications,,Bypass and inoperabir iatus indication for EFF and ESF support systemsare located on the ?O6 MTCB. The bypass and inoperable status system is _-
-_ _ . . _ ___,_ __._ _ .. _
7.5-5 -
.
I
. - - . . - ~. . _ . _- . . - . - - .- _.
!i
i I; % TABLE 7.5-3
[ J\FETY RELATED ANWUNCIATOP WINDOWS;
Windo'w1 - No. Actuatinc Device
j LA-1 Intake Structure Water Level - Low LS-21-5ALA-2 Safeguard Pump Room B Sump Hi-Hi Level LS-06-41LA-3 Diesel oil Storage Tank 2A Low Level LS-17-10A-
-- LA-4 Lube Water Supply Strainers High Differential PDIS-21-25-1A14
Pressure 1A2LA-5 Spare '.
[ LA-6 Atmos Stm Dump I sol Valves MV-08-15, (74,33)1621 I
MV-08-17 Motor Overload Valves closed (74,33)1623
LA-7 Condensate Storage Tank Low - Low Level LIS-12-11j LA-8 Safeguard Pump Raom A Sump Hi/Hi-Hi Level -LS-05-1A j
s LA-9 Diesel Oil Day 'Ienks 2A1, 2A2,. Low - Low Level LS-17-552A/553A *
* '
-J.S-14-1ALA-10 Component Cooling Water Surge TankCompartment F Low Level
;4
LA-11 Spare |,
] LA-12 Atmos Stm Dump' Valves MV-08-18A/IBB (74)1623,SS-1626-3 !
! Hotor Overload CS isolate (74)1628,55-1628-31
| LA-13 Condensate Stora,e Tank Low Level LIS-12-11 || LA-14 Fuel Pool High/L:w Level, High Temp LS-4420,TIA-4420' LA-15 Containment Pres. Transmitter I-SE-07-5A,-5C,-5E
Sensing Line A Isolationd
1 LA-16 Spare
$ |l
'
LB-1 Intake Structure Water Level - Low LS-21-5B--
j LB-2 Safeguard Pump R.som A Sump Hi-Hi Level LS-06-40
! LB-3 Diesel Oil Stora;e Tank 2B Low Level LS-17-10B
| y LB-4 Lube Water Supply Strainers High Differential PDIS-21-25-1B1,j Pressure 182j LB-5 Spare
i LB-6 Atmos Stm Dump Irol Valves MV-08-14, (74,33)1622
MV-08-16 Mote. Overload Valves closed (74,33)1624*
| LB-7 Condensate Storage Tank Low - Low Level LS-12-8
| LB-8 Safeguard Pump P.oom B Sump Hi/Hi-Hi Level , M -1B .s? LB-9 Diesel Oil Day Tanks 2B1, 2B2, Low - Low Level LS-17-552B/553B ~> q| LB-10 Component Coolin" Water Surge Tank M2 16-15,L5-10-5 '
Compartment B Le; Level, High Level,
i LB-11 Spare' LB-12 Atmos Stm Dump valves MV-Op-19A/19B (74)1625,SS-1625-3 ..
] Motor overload CS Isolate (74)1627,SS-1627-3
i LB-13 Condensate storage Tank Low Level LIs-12-115
| LB-14 Fuel Pool High/ Law Level, High Temp LS-4421,TIA-4421
! LB-15 Containment PresJ Transmitter I-SE-07-5B,-SD,-5FSensing Line B I,olation*
,
LB-16 Spare,
3
,
4
4
N \ N Y\ h (, Q k!Q\i ff . f -*
\ _ _-
'" i 7.5-38 pnendment No. 7 (4/92)I f\
N\|\ Y Y Y ( \ ( )
.
.- - - - - .. - -_=_. - . - . - . - _. _ _ _ _ - - _ _ . - -. - - _- ._ _ _
~
'
|COMPLETE PCMs FOR ICW *
|
pcm unit bcm_supplemeni_ ._ _
pcm_ title ,__ __
76117 01 00 SNUBBERS FOR BARTON D/P INSTRUMENTS ON ICW SYSTEMSTRAINERS. _
77229 01 . 00 REPLACEMENT OF VENTS AND DRAINS ON ICW HEADERS WORKED ON AN
77232 01 00 ICW PUMP IND LUBE WATER MdDiFIC TidU I3EI 5-7'' ~
77321 01 00 INS A13. FITTINGS ON ICW PUMP PRESSURE G UGES [ | |' ~ ~
78339 01 00 SPARE ICW PUMP REPAIRS I '
78414 01 00 REPAIR ICW DRAINS, VENTS AND INSTRUMENTATION PIPING RUNS REA __
78415 01 00 ICW FLOW ORIFICE "B" TRAIN BFI 5-6 '~ ~
78433 01 00 ICW SER INER BODY MATERIAL CHANGE BFI 5-7__ __ _.
;
79523 01 00 ADD CURBlN AT ICW PUMPS, CST DOORWAYS AND SEAL CST PIPE TUNN
79534 01 00 BACKFLUSH LINE (ICW/CCW) STRAINER REA-SLN-56
__ _ _ f'
79552 01 00 ICW/TCW PIPING REPAIR BFI 5-8
79573 01 00 ICW NON-ESSENTIAL HEADER VACUUM BREAKERS |79615 01 00 ICW LUBE WATER - PHASE Il-VI REA-SLN-19 BFI 5-7
80069 01 00 ICW PRESSURE TAPS BFI 5-8 ;_ _ _ __ _
80083 01 00 FLOW MEASUREMENT OF OBCW-ICW BFI 5-8 _ __y_ |
.
80128 01 00 ICW CHLORINATION SYSTEM REA-SLN-424 BFI 5-8 |_ _ _
80128 01 02 lCW CHLORINATION SYSTEM REA-SLN-424 BFI 5-8_ _.
80128 01 03 ICW CHLORINATION SYSTEM REA-SLN-424 BFI 5-8_ _ _ _ . _ _
80128 01 01 ICW CHLORINATION SYSTEM REA-SLN-424 BFI 5-8_ _ _ _
81051 01 00 ADDITIONAL OF VACUUM BREAKERS BASED ON ICW FLOW BALANCE TEST_ _ .
81104 01 00 REPLACEMENT OF DRAINS IN ICW SYSTEM REA-SLN-153BFI 5-6
81104 01 02 REPLACEMENT OF DRAINS IN ICW SYSTEM REA-SLN-153BFI 5-6 i
81104 01 01 REPLACUMEbT OF DRAINS IN ICW SYSTEM REA-SLU-153BFI 5-6 f82065 01 00 ICW LW RESTRAINT MODIFICATIONS REA-SLN-19 BFI 5-7
82122 01 00 ICW PUMP SHAFT MATERIAL CHANGE REA-SLN-464
82122 01 01 ICW P5P 5 HAFT MATERIAL CHANGE REA-SLN-46[~~
83001 01 00 I REPAIR CdBUTTERFLY VALVE 51-SU-2i2I1 BFI 5-9~~ ~
. ,
Page 1
A
_ _ __._ - -_ _ . _ - - - . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ - . . . _ - _ _ _ _ - _ _ _ - _ - _ _ _ _ - - - __ . .-
. .. _ _ _ ___ _. _. _ _ _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ . . . ..
. -
COMPL ETE PCMs FOR ICW .
,
i
'
:83001 01 01 REPAIR ICW BUTTERFLY VALVE #I-SB-21211 BFI 5-9 .
83272 - 01 00 ICW PUMP LUBE WATER STRAINER REA-SLN-530'
83305 02 . 00 ICW PUMP MISSILU SHlELD REINFORCEMUNT REA-SLN-618 BFI 127- |__
83343 02 00 ICW PUMP BEARING MATERIAL CHANGE REA-SLN-608 BFI 5-12__ _
833d8 W 00 ICW PUMP IMPELLER MATERIAL CHANGE REA-SLN-608 BFI 5-14 i t'
83374 .,1 00 APPENDIX R ICW PUMPS CURBS REA-SLN-105 BFI 54-10_ _
8338' 01 00 ICW/TCW STRAINER REPLACEMENT REA-SLN-660_
83385 01 01 ICW/TCW STRAINER REPLACEMENT REA-SLij-660 |_
84031 02 00 ICW PUMP MISSILE SHIELD LADDERS REA-SLN-618 BF1126-13 BF ' *
_
84178 02 01 ICW PIPE ACCESS MODIFICATION REA-SLN-84_77 BR 5-9 !
84178 02 00 ICW PIPE ACCESS MODIRCATION REA-SLN-84-77 BFI 5-9 ';
84223 02 00 ICW PUMP INTERNAL COATING REA-SLN-608 l !
84223 02 01 ICW PUMP INTERNAL COATING REA-SLN-608 | I_ _
I-84229 02 00 2A ICW PUMP DISCHARGE SPOOL PIECE REA-SLN-85-135 BFI 5-9 i
84231 02 00 ICW PUMP 2C WIRING MODlf lCATION ;'
__ _
!85008 01 00 ICW SYSTEM ORIFICES UPGRADE s ;_
85009 02 00 ICW SYSTEM ORIFlCES :_ _ _ _ _
'
85017 01 01 ICW PUMP LUBE WATER STRAlNER REPLACEMENT_ _ .
'85017 01 00 ICW PUMP LUBE WATER STRAINER REPLACEMENT. _ _ ._
85017 01 01 ICW PUMP LUBE WATER STRAINER REPLACEMENT
85017 01 02 ICW PUMP LUBE WATER STRAINER REPLACEMENT ,_ _ _ , _ _ _
85017 01 00 ICW PUMP LUBE WATER STRAINER REPLACEMENT_ _ _
85017 01 01 ICW PUMP LUBE WATER STRAINER REPLACEMENT ;__ _ _
85017 01 02 ICW PUMP LUBE WATER STRAINER REPLACEMENT |_
85017 01 02 ICW PUMP LUBE WATER STRAINER REPLACEMENT_ _ _ _ _
;
85017 01 00 ICW PUMP LUBE WATER STRAINER REPLACEMENT |
85018 02 02 ICW PUMP LUB5 WATER STRAINEFi REPLACEMEN ~'~
85018 02 01 ICW PUMP LUBE WATER STRAINER REPLACEMENT,
Page 2.
b
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__
. -
. COMPLETE PCMs FOR ICW -
:
I- t
85018 02 00 ICW PUMP LUBE WATER STRAINER REPLACEMENT
85018 02 00 ICW PU PIUBE WATER STRAINER RUPLAChMENT f85018 02 ~ 01 ICW PUMP LUBE WATER STRAINER REPLACEMENT 1
~
85018 02 02 ICW PU i.UBE WATER STRAINER REPLACEMENT
85018 02 00 IUW PUMPIUBE WATER STRAINER REPLACEMENT'
,
85018 02 01 ICW PUME LUBE WATER STRAINO3 REPLACEMENT |
85018 02 02 IUW PUM5 LUBE WATER STRAINER REPLACEMENT -,
PROTECTIVE COATINGS FOR INTEiiNAL ICW PUMPUOLkMNS i~
85082 01 00
85085 02 02 ICW PtjMP EXPANSION JOINT REPLACEMENT !
~ ~-
ICW PUMP EXPANSION JOINh REPLACEMENT85085 02 01
85085 02 00 ICW PUMP EXPANSION JOINT REPLACEMENT _ j_
__.
85089 01 01 ICW ISOLATION VALVE REPLACEMENT HEA-SLN-663/85-135 ;_ . __
85089 01 00 ICW ISOLATION VALVE REPLACEMENT REA-SLN-663/85-135 .
85166 01 00 ICW RESTRAINT MODIFICATION REA-SLN-663
85184 01 00 ICW PIPING INSPECTION PROCEDURE
85185 01 GO PSL-1 ICW DISCHARGE PIPE ZING ANODES REA-SLN-85-187~
f~ ~
85204 01 00 ICW BACKUPIUBEEATER BACKFLOW PREVENTOR REPLACEMENT_ _
86047 02 00 MISCELLANEOUS ICW MODIFICATIONS_. |_
86124 02 00 ICW LUBEWATER FLOWRATOR MODIFICATION _ j
86146 01 00 ICW MISCELLANEOUS SYSTEM MODIFICATIONS _86148 01 00 ICW BUTTERFLY VALVEREPLACEMENT , ,
87043 02 00 ICW PUMIESELF LUBRICATIUN MUUlFICATION | 'f87043 02 01 ICW PUMP SELF LUBRICATION MODIFICATION !
MISbELLANEOUS ICW SYSTEM MOblhlCATibNS'
87083 02 00
87134 01 00 ICW LUBE WATER STRAINER REPLACEMENT l-SS-21-12
88015 01 00 ICW LUBE WATER PIPE RESTRAINTS MODIFICATIONS [,
ICW PUMP MISSILE BARRIER MODIFICATIONS f88016 01 00~
88048 02 OU DWG & INST LIST dURR. FOR GEN PROT RELAX FOR ICWUMP Iif
!
Page 3 i:
_ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ . _ _ . _ . _ _ _ _ _ . _ . _ _ . _ _ _ _ , - - - - _ - - - . _ _ _ - --_--
c -
fCOMPLETE PCMs FOR ICW
,
88055 01 00 ICW & CW PUMP PACKING REPLACMENT DEEP|
88056 02 00 ICW & CW PUMP PACKING REPLACEMENT DEEP ,
88071 02 00 ICW LUBE WATER PRESSURE INDICATING SWITCH. DEEP. I
ICW PRESSURE INDICATOR UPGRIDE88122 01 00
88123 02 00 ICW PRESSURE INDICATOR UPGRADE
88178 01 00 ICW LUBE WATER FLANGE REPLACEMENT NCR 6652-2163M_ _
88228 02 00 ICW '2B' PUMP DISCHARGE ISOLATION VALVE REPLACEMENT
88247 02 00 ICW PUMP COUPLING, SPLIT RING ASSEMBLY _
88271 02 00 ICW LUBE WATER STRAINER |-SS-21-3A1 COVER REPAIR_ _ _ _
88311 02 00 ICW SYSTEM PRESSURE TRANSMITTER PT-21-8A SPOOL PIECE
88315 02 00 ICW FLOW DIAGRAM DRAWING DISCREPANCIES _89010 02 00 ICW STRAINER UE PRESSURE SWITCH REMOVAL
89035 02 00 ICW PIPING AND RESTRAINTS TO FIS 21-9B_ _ _
89035 02 00 ICW PIPING AND RESTRAINTS TO FIS 21-9B .
89035 02 01 ICW PIPING AND RESTRAINTS TO FIS 21-9B
89035 02 01 ICW PIPING AND RESTRAINTS TO FIS 21-9B y89048 02 00 2B ICW PUMP COLUN SEIMIC RESTRAINTS
89052 02 00 ICW-CHECK VALVE 21-V21208 FLAPPER PLATE H1NGE REPAIR_
89127 01 00 REPLACEMENT 4" ICW BUTTERFLY VALVE (1-SB-21188)__
89249 01 01 REPLACEMENT OF ICW/CW STRAINER MESH_ _
89249 01 00 REPLACEMENT OF ICW/CW STRAINEF1 MESH_
_
89252 01 00 ICW LUBE WATER STRAINER CABLE REPLACEMENT_ __
89260 02 00 lCW SYSTEM ISOLATION VALVE RELINING_
89380 01 00 ICW,CCW, SMALL BALL VALVES WITH CONTROMATICS j
89382 01 00 ICW STRAINER BACKWASH ARM MATERIAL CHANGE._ . _
89383 02 00 ICW LUBE WATER COUPLING INSTALLATION (NCR 2-303)
90041 01 00 REPLACEMENT OF ICW BALL VALVES |_
90041 01 01 REPLACEMENT OF ICW BALL VALVES
Page 4
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - - _ _ _ _ _ - _ _ _ _ - - _ - _ _ _ _ _
_ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ _ . .. . _ _ _ . . _ _ ._ .-
.. .
COMPLETE PCMs FOR ICW -
'
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90041 01 02 REPLACEMENT OF ICW BALL VALVES_ _ _
90041 01 00 REPLACEMENT OF ICW BALL VALVES'
90041 01 . 01 REPLACEMENT OF ICW BALL VALVES'
90041 01 02 RUPI.ACEMENT OF ICW BAL[ VALVES I
90044 01 , 00 [ ~RbMOVAL OF ICW VALVE SH-21374 f j
90051 01 00 CHANGE IN MATERIAL FOR ICW CHECK VALVE !'
90060 01 00 ICW PUMP 1C DISCHARGE ISOLATION VALVE REPLACEMENT [_
90129 02 00 REPAIR OF VERTICAL CONDUlTS AT INTAKE, CCW, AND ICW i'
90129 02 01 REPAIR OF VERTICAL CONDUlTS AT INTAKE, CCW, AND ICW|_
90129 02 00 REPA@ OF VERTICAL CONDUlTS AT lNTAKE, CCW, AND ICW j_
90129 02 01 REPAIR OF VERTICAL CONDUlTS AT INTAKE, CCW, AND ICW j_
90133 02 09 ICW PUMP BUILDING ROOF HANDRAILS t_
,.
90141 02 00 ICW LUBEWATER COUPLING INSTALLATlON j |.
!
90157 02 00 RPELACEMENT OF TI-21-12 A& B ICW
90178 02 00 ICW PUMPS 2B & 2C SELF LUBRICAilNG MODIFICATION [
90178 02 01 ICW PUMPS 2B & 2C SELF LUBRICATlNG MODIFICATIONS f_ _
90178 02 02 ICW PUMPS 2B & 2C SELF LUBRICATING MODIFICATION <
_ _ _ , i
90178 02 00 ICW PUMPS 2B & 2C SELF LUBRICATING MODIFICATION 1
l90178 02 01 ICW PUMPS 2B & 2C SELF LUBRICATING MODIFICATION__ _ ;
90178 02 02 ICW PUMPS 2B & 2C SELF LUBRICATING MODIFICATION
90178 02 00 ICW PUMPS 2B & 2C SELF LUBRICATING MODIFlCATION_ __
90178 02- 01 ICW PUMPS 28 8. 2C SELF LUBRICATING MODIFICATION j__ _
90178 02 02 ICW PUMPS 28 & 2C SELF LUBRICATING MODIFICATION
90213 02 00 CW & ICW PUMP PACKING REPLACEMENT l
90227 01 00 MONEL 400 MATERIAL AS SUBSTITUTE IN CW/lCW PIPE SYS. !
90241 01 00 CW AND ICW PUMP PACKING REPLACEMENT i
90273 02 00 MONEL 400 MATERIAL SUBSTITUTE FOR ICW/CW PIPING SYSTEM - !90280 01' 00 ALTERNATE ICW & CCW PUMP DISCHARGE CHECK VALVES .f
%. I !--
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Page 5 !
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. _ _ . . . _ . _ . _ _ _ . . . . _ . _ _ _ _ . . . . _ . _ . _ _ _ _ _ - _ _ _ - . _ _ . _ _ _ _ _ _ _ _ _ . _ . - _ _ . _ . _ _ _ _ . _ _ _ _ . . _ _ . _ _ _ . . _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ . . _ _ . _ _ _ _ _ _ . _ . _ _ _ _ _ _ . . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _
. _ .. .. _ ._. _. ___. _ _ ._ __ _ _ _ _ _ _ __ _ _ _ _ _ . _ . _ _ .
-
. .
COMPLETE PCMs FOR ICW -.
.
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90284 01 00 ICW LW-42 RESTRAINT REPLACEMENT .
'
90325 02 00 USE OF TITE-SEAL GASKET SEALING COMPOUND IN ICW APPLICATICT43__ ,
90327 02 . 00 2A ICW MOTOR LOWER END SHIELD REPAIR_ _
'
90327 02 01 2A ICW MOTOR LOWER END SHIELD REPAIR
2 h MUTOR LOWER END SHIELD REPAIR90327 02 02 i
90327 02 00 2A ICW MOTOR LOWER END SHIELD REPAIR
90327 02 01 2A ICW MOTOR LOWER END SHIELD REPAIR.
90327 02- 02 2A ICW MOTOR LOWER END SHIELD REPAIR !
90327 02 00 2A ICW MOTOR LOWER END SHIELD REPAIR *
_
90327 02 01 2A ICW MOTOR LOWER END SHIELD REPAIR |_
90327 02 02 2A ICW MOTOR LOWER END SHIELD REPAIR j_
90355 02 00 ICW PUMP MOTOR LEAD TERMINAL LUGS I ,
90426 G1 00 HARD CAFID EVALUATION M&S 008-56996-7(ICW STRAINER) f91030 01 00 ICW STRAINER SUPPORT REPAlR [
91030 01 01 ICW STRAINER SUPPORT REPAIR_
91030 01 00 ICW STRAINER SUPPORT REPAIR
91030 01 01 ICW STRAINER SUPPORT REPAIR
91078 01 00 ICW PUMP COLUMN PROTECTIVE COATING |
.. _
91177 02 00 ICW & CCW VALVE TAG DISCREPANCIES .
ICW F UMP DISCHARGE CHEbi[ VALVE [ {591238 01 00
91285 01 00 ICW PUMP MOTOR STATOR MATERlALS UPGRADE |__ __
91285 01 01 ICW PUMP MOTOR STATOR MATERIALS UPGRADE !_ _ _
91285 01 00 ICW PUMP MOTOR STATOR MATERIALS UPGRADE
91285 01 01 ICW PUMP MOTUIE STATOR UIATERIALS UPGRADE~
91439 01 00 ICW SYSTEM FLOW ENHANC5MEIUT~~ ~
91494 01 00 ICW/TCW ORIFICE PLATE MOblUICATION (S0-21-2A&2B). . _ .... --. . .--.
92002 02 00 1CW PRESSURE TRANSMITTER PT-21-8A REPLACEMENT j_ .
92036 01 00 CCW HX & ICW PIPING DRAINS :
I
Page 6 [!
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.- .- .- .. - . - - - . ..- - - .- - -
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COMPLETE PCMs FOR ICW -
i
92037 02 00 CCW HX & ICW PIPING DRAINS .
_ _
92078 01 00 ICW PT-218A,88 INSTALLATIONt
92128 02 . 00 ICW PUMP COLUMN & DISCHARGE HEAD PROTECTIVE COATING I
92246 01 00 1B ICW MOTOR BEARING HOUSING & JOURNAL REPAIR j
92268 02 00 ICW LUBE W TER PIPING REMOVAL & CW LUBE WAT5R RENOVATION~ '
'
92341 01 00 ICW l.IIBE W TUR PIPING REMOVAL & CW LUBE WATER RENOVATION~
.
93035 02 00 ICW DISCHARGE HE DER LOW PRESSURE LARM SETPOINT CHANGE' -
93047 01 00 ICW DISCHARGE HEADER LOW PRESSUR5 ALARM S5TPOINT CHANGE ,
93061 01 00 REPAIR OF 1C ICW PUMP PEDESTAL
93662 02 00 ICW PUMP PARTS MATERIAL CHANGE
93074 01 00 REPAIR 1B ICW PUMP PEDESTAL._
93084 01 00 DRAIN CONNECTION FOR ICW SUPPLY TO |B' TCW HT EXCHANGER_
93163 02 00 2B ICW PUMP MOTOR HOL' SING & JOURNAL REPAIR i
__ _
93182 01 00 ICW/CCW PUMP CONTROL CIRCUlTS PULL-TO-LOCK SWITCHES_ .
93182 01 01 ICW/CCW PUMP CONTROL CIRCUITS PULL-TO-LOCK SWITCHES
93182 01 00 ICW/CCW PUMP CONTROL CIRCUlTS PULL-TO-LOCK SWITCHES
93182 01 01 ICW/CCW PUMP CONTROL CIRCUlTS PULL-TO-LOCK SWITCHES j'
_
93183 02 00 ICW/CCW PUMP CONTROL CIRCUlTS PULL-TO-LOCK SWITCHES
93196 02 00 2A CCW HEX ICW OUTLET FIS-21-9A SENSING LINES_
_ .
94036 02 00 ICW PRESSURE TRANSMITTER PT-21-8B INSTRUMENT PIPING ,
' ~ ~~ ~
S4069 01 00 ICW lSTRijMUNT TION IMPULS5 LIN5 MATERIAL CHANGE i I
'
94093 02 00 GW/ICW INSTRUMENTATION IMPULSE LINE PRODUCT & MATL CHANGE!94121 01 00 ICW VENT DRAIN & INSTRUMENT BRANCH
_.
'_ _ _
94141 01 00 ICW/CCW LOADING RELAYS
94148 02 00 MODIFY 3Y RELAYS IN AB BUS FOR ICW/CCW 2C PUMPS
95051 02 00 IC ICW/CCW MAN / AUTO SWITCH ALARM <
_ . _ _ _
95129 02 00 TCW STRAINER ICW PIPE ACCESS ADDITION OF SLIP ON FLANGES'
_
,
Page 7
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Page 1:,*,
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! CALCULATION COVER SMEET,
J
Calculation Not PSL-1FSN-96-001i
i
i Title: Containment Atmosehere Particulate Monitor Resconse to RCS1 Leakage During Normal Plant Operation
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No. Description By Date Chkd Date Appr Date
REVISIONS
Form 92A, Rev 6/;4,
e Page 11
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LIST _OF_. EFFECTIVE _PAGES*
|alculation No.3 PSL-1FSN-96-001 Rev.: 0
.'itles Containment Atmesphere Particulate Monitor Response to RCS
_ Leakage During Normal Plant Operation
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Page Section Rev. Page Section Rev.
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1 02 03 04 05 06 07' O
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Form 82B, Rev 6/s4 i< 34'
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' Calculation No. PSL 1FSN-96-Qfl_ Revision 0 Sheet No. 1.
1. PURPOSE / SCOPE
Condition Report (CR) 96-2228 was written to document a need tovalidate the design of the Unit 1 and 2 particulate and gaseousradiation monitors since design basis information was notavailable. The CR raised questions with- respect to thefollowing aspects.of system design and operation:
- the use of 10% of scale change as an indication of a 1 gpmincrease in RCS leakage-(as described in the UFSAR);
tha requirement for isokinetic sample flow;-
the current practice of setting the alarm at 2 times-
background; and
the detector response time associated with detecting a 1-
gpm increase in reactor coolant system (RCS) leakage.
The purpose of this calculation- is to address the above listeditems as they pertain to the design and operation of RE-26 31,the containment particulate radiation monitor.
2. REFERENCES
2.1 Memo from D.H. Faulkner (Chemistry) to Chris Wasik(Engineering), Subject: Normal Unit 1 Reactor Coolant Rb-88 and Xe-133 Values, 9/26/96.
2.2 St. Lucie Unit 1 Updated Final Safety Analysis Report,through amendment 14, Table 6.2-9.
.2 . 3 - St. Lucie Unit 1 Updated Final Safety. Analysis Report, |through amendment 14, Table 6.3-6. I
2.4 9770-7178, Victoreen Process Radiation Monitoring System,Rev. 12.
2.5 Record of Telecon between Chris Wasik (FPL Engineering) j
and George Buck (Victoreen), 9/27/96. ||
2.6 Chart of the Nuclides, Knolls Atomic Power Laboratory, ;
'
Ninth Edition.
ANSI N13.1-1969, American National Standard Guide to.2.7 -
ISampling Airborne Radioactive Materials in NuclearFacilities, February 19, 1969.
_ _ __ ._ __ _
4
.
Calculation No. PS L- 1 FSN - 9 6 - 0 01 Revision 0 Sheet No. 2*
i,
2.8 8770-5835, Rev. 1, Isokinetic Nozzle for Containment|
Atmosphere Sample.
! 2.9 Memo from Russ Cox (Chemistry) to Chris Wasik(Engineering), Subject: Rb-88 Micron Size, 9/27/96.
2.10 Nuclear Reactor Engineering, Third Edition, Samuel| Glasstone and Alexander Sesonske, Van Nostrand Reinhold
Company, 1981, Chapter 2.
2.11 1-IMP-26.14, Containment Process Monitor CalibrationInstruction Instrument and, Control Procedure St. LucieUnit 1, Instrument Calibration Report Data Sheet 2,Calibration Certificate for Channel 31, 7/5/96.
.
3. METHODOLOGY
3.1 The portion of this calculation addressing the use of a 10%scale change to indicate RCS leakage and the isokineticsample flow rate consists of an analytical review of the
|relative facts'and does not involve any formal calculations.
3.2 The remaining portion of this calculation addresses theability of the particulate monitor to detect and alarm upona 1 gpm increase in RCS leakage during normal plant operatingconditions, including the validity of setting the alarm pointat 2 times background.
|
The calculation was performed using an Excel spreadsheetwhich considered the RCS leakage event in discrete one minuteintervals. The Excel spreadsheet does the following for eachinterval:j
1. calculates the total activity of Rb-88 (uCi) incontainment based on a given RCS leak rate and a givenRCS Rb-88 concentration (uCi/cc);
2. calculates the containment Rb-88 concentration (uCi/cc)based on the results of #1 above, factoring in theradioactive decay associated with an assumed 14 minute
! delay for containment atmosphere mixing;|
! 3. calculates the particulate monitor filter activity (uCi)based on the results of #2 above; and
'
4. calculates the particulate monitor detector reading (cpm):
based on the results of #3 above, factoring inradioactive decay of Rb-88 deposited on the filter as itmoves from the sample stream to the detector.
.
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Calculation No. PSL-1FSN-96-001 Revision 0 Sheet No. 3 ;, ,
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4. Assumptienn/ Bases,
1
4.1 All dynamic events are assumed to occur in one minute ,,
; intervals; this includes RCS leakage into containment, )containment atmospheric mixing, particulate sample deposition ;,
'onto the filter media, filter motion, radioactive decay, and! detector indication.k
| 4.2 The only isotope considered in this evaluation shall be: Rubidium-88 (Rb-88). Rb-88 has been identified by the
Chemistry department as the isotope which dominates detector,
; response due to its high beta energy. No other isotopesj shall be considered to affect the detector.i
! 4.3 The RCS Rb-88 activity is. assumed to be 0.136 uCi/cc. This: value is based on an average of the RCS sample Rb-88
activities provided by Chemistry (reference 2.2).
j 4.4 The RCS leakage rate is assumed to be 1.0 gpm.e
{ 4.5 The Rb- 8 8 . activity is assumed to be uniformly dispersedthroughout the containment volume after a period of 14.
minutes. This value represents the time for the containmentj cooling system, operating at 180,000 cfm (reference 2.2), to; provide one complete turnover of the containment free volume
_
2j of 2.5E+6 ft (reference 2.3).'
|
!>'
4.6 All Rb-88 present in the RCS leakage is assumed to be,
released to the containment atmosphere since, at normal RCS1 temperature and pressure, any leakage would be flashed to
steam. !,
; 4.7 100% of the Rb-88 sampled by the monitor is captured on the! filter paper. The affects of other isotopes shall be1 ignored.
! 4.8 Rb-88 is assumed to be unif ormly deposited .on the filter
|media.
i
j 4.9 The sample flow rate is 3.5 cfm based on observed flow in the !
j field and discussions with the system engineer.,
!
j 4.10 Filter paper speed is 1 inch per hour (reference 2.4).1
i 4.11 The filter paper is assumed to move immediately from the areaexposed to the sample stream to the area monitored by the| .
i detector. This is based on dimensional information provided; by the manufacturer (reference 2.5).
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,Calculation No. PSL-1ESR u.nn1_ Revision _0_. Sheet No. _ i__
4.12 The filter width exposed to the sample stream is 1 inch(reference 2.4). Since the filter speed is 1 inch per hour,this width contains 60 one minute segments.
4.13 The width of the filter in front of the detector '4.e.,detector width) is 2 inches (reference 2.4). Since thefilter speed is 1 inch per hour, this width conta ns 120 oneminute segments.
s
4.14 Detector sensitivity to Rb-88 is assumed to be 2.3 times thesensitivity to Cs-137 which is used as a test source(reference 2.5). Detector sensitivity is 5.48E+12 cpm /uCi/ccof Cs-137 and is 1.26E+13 cpm /uCi/cc of Rb-88 at a sampleflow rate of 8.5 cfm (reference 2.5). Taking a ratio allowsus to establish that 1 uCi of Rb-88 will provide 2.3 timesmore cpm than 1 uCi of Cs-137.
4.15 The normal particulate monitor reading is assumed to be 400cpm based on discussions with cognizant personnel andpersonal observation in the contrcl room.
4.16 The radioactive half-life of Rb-88 is assumed to be 18minutes and the radioactive half-life of Cs-137 is assumedto be 30 years (reference 2.6).
5. CALCULATION
5.1 Use of a 10% Change in_IndicatiCn
Section 5.2.4 of the UFSAR describes using a 10% deviationin the normal reading of the monitor as an indication of astep increase in RCS leakage from 0.1 to 1.0 gpm. Table 5.2-11 notes that it would conservatively take 18.1 hours for a10% change to be observed. Since no original design basiscalculations are available, it is not clear exactly what wasconsidered as the normal meter indication and how the 18.1hours was calculated. It should also be noted that theoriginal plant design considered normal operations with 0.1%failed fuel (UFSAR Table 11.1-1). Since today's fuelperformance is much better, containment activity levels arecorrespondingly lower. 'With the containment particulatemonitor fluctuating between 300 and 500 cpm under normaloperating conditions as observed in the control room, it isdifficu'lt to detect a 30 to 50 cpm increase as an indicationof increased RCS leakage.
The current plant practice is to set the alarm point at 2times the background level. Preliminary calculationsperformed by Engineering and Chemistry have demonstrated theadequacy of this practice in providing an acceptable
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l Calculation No. _PS L - 1 FSR.-3.5. _0 01_ Revision 0 Sheet No. 5 i.
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!indication-of RCS leakage. The calculation discussed belowi. provides. formal documentation of the acceptability of the usej
! of 2 times background versus using a 10% meter change as anindication of RCS leakage. A UFSAR change will be provided !
via a safety evaluation as a part of the response to CR 96- 1
2228..
',| |
! 5.2 Isokinetic Samnlino_-
Sectio'n 5.2.4.5 of the UFSAR describes the sampling system|
as taking an isokinetic sample of air from the containmentcooling system ductwork. An isokinetic sample is one in'
which the sample velocity (entering the sample line) is
identical to the velocity of the airstream, being sampled(reference 2,7). The purpose of isokinetic sampling is to
. obtain a representative particulate sample. Section 4.2.2.3||
of the ref erence 2.7 standard notes that when the sample|
velocity is at a much lower velocity than the streamvelocity, larger particles will be preferentially collected.'
Likewise, when the sample velocity is greater than the streamvelocity, smaller particles will be preferentially collected.The standard goes on to note:
| The degree to which the fractionation occurs is a function of particle
j size, density, particle size distribution and the difference between theisokinetic velocity and the anisokinetic velocity employed. Except invery unusual situations. particles smaller than an aerodynamicdiameter of about five microns are able to follow the streamlines of theair, and the fractionation error is not great. ;
.
The reference 2.8 drawing requires a sample pump flow rate |
of 4.0 cfm. Actual normal flow is 3.5 cfm. Thus the i
anisokinetic sample velocity is smaller than the isokinetic )
velocity by a factor of 0.875. Appendix C of the reference2.7 standard shows that for.a probe inlet velocity to duct |
velocity ratio of 0.9, the ratio of the observedconcentration to actual concentration is 1.00 for a particle !
diameter of 4um. This ratio increases slightly as particlediameter increases (resulting in a disproportionate amount |
i
of larger particles being drawn in to the sample). Since thediameter of the Rb-88 particulates is expectec'. to be < 4um(reference 2.9), it is concluded that the anisokinetic samplerate of 3.5 cfm does not impact the ability to obtain arepresentative sample and is therefore acceptable. A UFSAR
ofchange will be provided via a safety evaluation as a partthe response to CR 96-2228.
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Calculation No. PSL-1FSN-96-001 Revision 0 Sheet No. 6~
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5.3 Particulate Monitor Response to RCS Leakage
The Attachment 1 Excel spreadsheet printout provides theresults of the calculation. The sections below provide theformulas used in the spreadsheet.
5.3.1 The rate of Rb-88 leaked to containment atmosphere for each1 minute interval is calculated as follows:
.
'
Rate = (RCS Rb-88 Concentration) x (RCS Leak Rate)
Rate = (0.136 uCi/cc) x (1.0 gpm) x (3785 cc/ gal)
Rate = 515 uCi/ mini
!
5.3.2 The total curie content (activi ty ) - of Rb-88 in the I
containment atmosphere for each 1 minute interval is
calculated as follows:
Activrty = (Rate of Rb-88 Leakage) + (Activity from Previous interval) x (1 Min. Decay Factor)
The Decay Factor is calculated using the standard radioactivedecay formula (reference 2.10) and the 18 minute half-lifeof'Rb-88 as follows:
Decayed Value = (Original Value).x (e* )
Where: L = 0 693 = 0 693 = 0.0385 min" |i
half life 18 min
t = 1 minute ,*1
Thus:
Decayed Value = (Original Value) x (0.9622)
I
Substituting back in to the original equation:.
Rb-88 ActMty (uCi) = (515 uCi) + (ActMty from Previous interval) x (0.9622)
i-
.
_ _ ~ . ~ . . .-----.-.._.. ___--___ - _ _- - _-. .. ._
.
.
Calculation No. PSL-1FSN-96-001 Revision 0 Sheet No. 7-
5.3.3 Allowing a 14 minute delay to allow for containmentatmosphere mixing, -the concentration of Rb-88 in the
containment for any given interval is calculated as follows:
Rb-88 Conc. (uCi/cc) = (Rb-88 Actmtv) x (14 Min. Decay Factor)(Containment Volume)*
Where: Containment Volume = 70800000000 ccDecay Factor = 0.5833 (calculated as in 5.3.2 above)
5.3.4 The total Rb-88 activity present on any given filter segmen't j
is calculated as follows: !
Actmty (uCi) = (New Actmty Deposited) + (Actmty from Previous Interval) x (1 Min. Decay Factor)
Where: New Actmty Deposrted (uCi) = (Sample Flow Rate) x (Rb-88 Conc.)
New Activity Deposited (uCi) = (3 5 cfm) x (28320cc/ft ) x (Rb-88 Conc )3
60|
5.3.5 The conversion factor (CF) for converting filter activity(uci) into a detector count rate (cpm) is calculated asfollows using data from^the last calibration (reference 2.11) |
and the test source original curie content (provided by |
Chemistry):
Source No. WC-25 (Cs.137) .Original Cune Content = 9.846 uCi on 3,15/85Detector Calibration of 7/5/96 (corrected for background) = 29072 cpm
To calculate the cpm per uCi conversion factor, we need tofirst determine the curie content of the test source as ofthe 7/5/96 instrument calibration. This is done by using thedecay equation of Section 5.3.2:
Curie Content = (9.846 uCi) x (e")
.
Where: L= 0.693 = 6.324E-05 days"
(30 yr) x (365.25 d/yr)
i
t = 4130 days (3/15/85 to 7/5/96)
. . ._ _ _ _ ~ . - .. _ _ . . _ .m __ . . _ _ . . . _ . _ _ - _ _ _ _ . . _ _ . _ _ . _ - _ _ _ . . . . .
i <
0
Calculation No. ,_PSL-1FSN-96-001 Revision O Sheet No. 9,
Therefore:Curie Content = (9.846 uCi) x (ess324ea4m ) = 7 583 uCi
,
Knowing the curie content and the detector response, we cannow calculate the conversion factor (CF) :
i
CF= 29072 com = 3834 com/uCi7.583 uCi
5.3.6 The detector indication is calculated as follows:
)Indication = (Sum of Filter Segment ActMtiesin Front of Detector) k (Conversion Factor)
Where the filter. segment activity is calculated per Section5.3.4 and the conversion factor used is 3834 cpm /uci fromSection 5.3.5.
6. RESULTS
6.1 The use of a 10% of indication change in detector reading asan indication of a step change in RCS leakage from 0.1 to 1.0gpm is difficult given the current operating environment withimproved fuel performance.
6.2 Anisokinetic (as opposed to isokinetic) sampling of thecontainment atmosphere via the containment radiationmonitoring system is acceptable since the particle sizes andsystem velocity are such that there is no appreciableinfluence on the sample.
6.3 With a normal count rate of 300-500 cpm, and a monitor ALERTsetpoint at twice background (approx. 800 cpm), themonitoring system is capable of indicating a 1.0 gpm increasein RCS leakage within about 70 minutes. This is well withinthe licensed basis for system response (18.1 hours).
,
Note: the ability of the monitor to detect and alarmincreasing RCS leakage is a function of both the RCS leakrate to containment atmosphere and the activity levels in theRCS. Under clean RCS conditions the ability of the monitorto detect RCS leakage is diminished.
Sendsra.J IbsuNs su y*
-' '
UNIT 1 CONTAINMENT PARTICULATE MONITOR
~ RC3 Rb-88 Conc. 1.36E-01 uCi/cc#tv. O--
RCS Leak Rate 1.00 gpm_
Activity into RCB 515 uCi/ mink , j 'I Y \
' 14 MIN DELAY : DETECT 6R f .
IRCB RCB Rb-88 NEW READING
|TIME ACTIVITY CONC. TIME CHANGE
(min) (uCi) (uCi/cc) (min) (com)
0 0~
0.00E+00 14 0
1 515 4.24E 09 15 0
2 1010 8.32E-09 16 0
3 1487 1.22E 08 17 0 ,
1
1.60E-08 18 14 1945 ~"'1.97E-08 19 15 2386
6 2811 2.32E-08 20 ~27 3219 2.65E-08 21 3
48 3613 2 9,8E-08 22_,
10 4355_
3.29E-08 23 69 39913.59E-08 24 8
3 88E-08 25 1011 4705~ " 4 715E-08'~ 26 10
~
12 50425366 4.42E-08 27 1613 .
1914 5678 4.68E-08 28 -
15 5978 4.93E-08 29 23
16 6267 5.16E-08 30 27
17 6545 5.39E-08 31 32~
18 6812 5.61 E-08 32 7719 7069 5.82E-08 33 42
..2 . __ _ _ . 7 1 6 03.E 0 ,_ ,_,._34 _ _ _ _
~ ' ~ 783 6.41E 08 -~ 36 ~~ 30'
72223 8005 6.59E-08 37 67
24 8217 6.77E-08 38 74
25 8421 6.94E-08 39 81
26 8618 7.10E-08 40 89
7.26E 08 41 9727 8807- 7.41 E-08 42 10528 8988~ 7.55E-08 43 113 j29 9163
30 9332 7.69E-08 44 122 |
31 ,9494 7.82E-08 45 131
32 9650 7.95E-08 46 140
8.07E-08 47 15033 9800~ 8.19E-08 48 16034 9944
35 10083 8.31 E-08 49 170
36 10217 8.42E-08 50 180
37 10345 8.52E-08 51 190 f38 10469 8.62E-08 52 200'
39 10588 8.72E-08 53 211
40 10702 8.82E-08 54 222
41 10813 8.91 E-08 55 233 :
42 10919 9.00E-08 56 244
43 11021 9.08E-08 57 255
44 11119 9.16E 08 58 26659 27745 11213 9 24E-08~60 28846 ~~~i1364 9 31 E' 08
,
__ - . _ _ _ _ _ _ _ _ . _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ .
I
Nka~si 1*
Ipu.ma-y-oos , hs G
' 'j /3e Z/Ij: 47 11392 9.39E-08 61 300I
'
48 11476 9.45E-08 62 31149 11557 9.525-08 63 322
'
; 50 11635 9.59E-08 64 33451 11710 9.65E-08 65 34552 11782 9.71 E-08 66 357
: 53 11851 9.76E-08 67 36854 11918 9.82E-08 68 380 -
] 55 11982 9.87E-08 69 391:
L 56 12044 9.92E-08 70 4033
57 12104 9.97E-08 71 41458 12161 1.00E-07 72 425,
59 12216 1.01 E-07 73 437f 60 12269 1.01 E-07 74 448
61 12320 1.02E-07 75 459'.
| 62 12369 1 02E-07_ 76 470t 63 12416 1.02E-07 77 481; 64 12462 1.03E-07 78 4923 65 12505 1.03E-07 79 503| 66 12547 1.03E 07 80 514; 67 12588 1.04E-07 81 525i 68 12627 1.04E-07 82 535'5 69 12664 1.04E-07 83 54C
70 12700 1.05E-07 84 556'
71 12735 1.05E-07 85 566f 72 '2768 105E-07 86 576__.
73 1*B00 1.05E-07 87 586t
74 128;1 1.06E-07 88 59575 12861 1.06E 07 89 60576 12890 1.06E-07 90 61477 12917 '1.06E 07 91 623 1
78 12944 ~ 1I)TE-07 92 633 l
79 12969 107E-07 93 64180 12994 1.07E-07 94 65081 13017 1.07E-07 95 65982 13040 1.07E-07 96 66783 13062 1.08E-07 97 67584 13083 1.08E-07 98 68485 13103 1.08E-07 99 69186 13123 1.08E-07 100 69987 13141 1.08E 07 101 70788 13159 1.08E-07 102 71489 13177 1.09E-07 103 72290 13193 1.09E-07 104 72591 13209 1.09E-07 105. 73692 13225 1.09E 07 106 743
-
93 13240 1.09E-07 107 74994 13254 1.09E-07 108 75695 13268 1.09E-07 109 76296 13281 1.09E-07 110 768
|
- - . - - - _ = . _ - _ . _ .__
!
' AHartna d 1-
PsL- 1/td 96-002, //tv.
kje 3 'I [
97 13294 ~~ 1.10E-07 111 775
98 13306 1.10E 07 112 781 |
100 13329-~
1.10E-07 113 786 ;99 133181 10E-07 114 792 i
101 13340 1.10E-07 115 798 !
102 13351 1.10E-07 116 803 i
103 13361 1.10E 07 117 808 j
104 13370 ~ 1.10E-07 118 813 |
105 13380 1.10E-07 119 818 j
106 13389 1.10E-07 120 823-
107 13397 1.10E-07 121 828
108 13406 1.10E-07 122 833 j'
109 13414 1.11E-07 - 123 837
110 13422 1.11E-07 124 842
-f111 13429 1.11 E-07 125 846
1.11 E-07 126 850 1112 13436- 1.11 E-07 127 854113 13443
114 13450 1.11 E-07 128 858
115 13456 1.11E 07 129 862
116 13462 1.11 E-07 130 866 ;
117 13468 1.11E 07 131 870
118 13474 1.11E-07 132 873
119 13479 1.11 E-07 133 877 !
120 13484 1.11 E-07 134 880
121 13489 1.11 E-07 135 883 |122 13494 1.11 E-07 136 887
~~ 123 13499 1.11E-07 137 890 !
124 13503 1.11 E-07 138 893 {
125 13508 1.11E 07 139 896 )
126 13512 1.11 E-07 140 898
1.11 E-07 141 90112713516 ~ ~~ ~1.11 E-07142 904128 13520 |
129 13524 1.11 E-07 143 907 |
130 13527 1.11 E-07 144 909
131 13531 1.11 E-07 145 912
132 13534 1.12E-07 146 914
133 13537 1.12E-07 147 916
134 13540 1.12E-07 148 918
135 13543 1.12E-07 149 (12 1 |
136 13546 1.12E-07 150 923
137 13549 1.12E-07 151 925
138 13551 1.12E-07 152 927
139 13554 1.12E-07 153 929
140 13556 1.12E-07 154 931
141 13558 1.12E 07 155 932'
142 13561 1.12E 07 156 934
143 13563 1.12E 07 157 936
144 13565 1.12E 07 158 937
145 13567 1.12E 07 159 939|1
146 13569 1.12E-07 160 941,
,
. . . . . - . - . - . . -- .. . . _ . _ . _ . . . _ . .-- -, . . . ~ . _ - . - . - . . . . . . - . . . ~ . _ . . . . - - . .
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147 13571 1.12E-07 161 942 |
| 148 13573 1.12E-07 162 943
149 13574 1.12E-07 163 945 ;
150 ! 13576 1.12E-07 164 946 |
151 13578 1.12E-07 165 947 I
l152 i 13579 1.12E-07 166 949
153 13581 1.12E-07 167 950 |
154 t 13582 1.12E-07 168 951
155 i 13583 1.12E-07 169 952
156 13585 1.12E-07 170 953
157 13586 1.12E-07 171 954
158 i 13587 1.12E-07 172 955
159 13588 1.12E-07 173 956
160 i 13589 1.12E 07 174 957T161 13590 1.12E-07 175 958
162 13591 1.12E 07 176 959
163 13592 1.12E-07 177 960
164 13593 1.12E-07 178 961
165 13594 1.12E-07 179 962
166 13595 1.12E-07 180 962|
.
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-~ ._ _: _. ._ _ __ _ . - - :_ . . _ . . . _ . . _ _ _ _ .__._____.:__,
_ CONTAINMENT ACTIVITY INCREASE -
- (1.0 GPM LEAK)_. 14000 - _
_ ._
_ _
12000 -.
-. .
_ _
10000 - i
-
_ 8 8000 - _
>_ .- _
EU,6000-
-
- _
_ __;
_ l_ 4000 .
- _
- 2000 -- _
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S~ $ R $ 8 R 8 8 R 4 8 2 8 2. 0y,,, ,,,8 ~- - ~
_- -
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_ _ _ _ _ . _ _ . (. - _ _ _ .___ - __ _ _ ._
.- - _ - - . - __ _ - . -. .. . - - _ _ . . - .
~
- COUNT RATE INCREASE _ - - - l
--
(1.0 GPM LEAK)~
j_ 900 - _ ;
___ _..
800-
- -
_. -
_ 600 - .
- -
'
O
~~* 400 ---
_. -
|_ 300 - _1
_ _ 1,
_ N
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- s oo - -
;_ _
M emuu
' - - $ R $ 8 C 3 8 R 4 S $ 8-- - - - - -
TIME (MIN)
i.
|
AL% 4 2 4 NL- WM- U-col 4 |
Pcge 2': |,
TO: Chris Wasik DATE: 9/26/96
FROM: D.H. Faulkner DEPT: CHEMISTRY
SUBJECT: Normal Unit 1 Reactor Coolant Rb-88 and Xe-133 Valuesi
|
UNIT 1 REACTOR COOLANT SAMPLE ANALYSIS !|
Activity reported in uCi/cc. | |!
SAMPLE DATERIME RB-88 XE-133
-26-SEP-1996 09:05 1.98E-01 2.86E-03
24-SEP-1996 09:05 1.75E-01 - 2.47E-03
22-SEP-1996 00:50 1.78E-01 2.72E-03
12-SEP-1996 08:48 6.51E-02 1.64E-03
10-SEP-1996 06:50 5.46E-02 1.29E-03 |'8-SEP-199614:10 1.01E-01 1.39E-03
6-SEP-1996 08:45 6.70E-02 1.48E-03
5-SEP-1996 08:30 4.22E-02 1.16E-03 j
31-AUG-1996 22:20 2.57E-03 3.45E-03 |
31-AUG-1996 01:50 1.62E-01 2.65E-03 j
27-AUG-1996 02:20 1.10E-01 2.09E-03 |
25-AUG-1996 00:50 1.1IE-01 2.03E-03 |
23-AUG-199610:20 1.80E-01 2.87E-03
21-AUG-1996 09:45 1.48E-01 3.33E-03
20-AUG-199610:25 1.26E-01 2.92E-03
18-AUG-1996 01:40 1.72E-01 2.37E-03 |17-AUG-1996 01:30 3.24E-01 2.55E-03 )16-AUG.1996 08:45 2.38E-01 3.29E-03 j
These values represent typical activity levels for this time in core life and with littleor no fuelleakage.
If you have any questions or r.eed more data, please contact me. i
|Thanks, |
|'
Dave FaulknerChemistry Supervisor
.
||l
_. . _ ~ . -.. - =-_ _ - . .- - - . _ .- .- - . ..
1
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: A L L~ ~J 3 }'RECORD OF TELECON .
\P S L- 2 f 5 ^J % C)O 1, K''
Date: 9/27/96:
i Ij Participants: Chris Wasik - FPL Engineering
| George Buck - Victoreen (216-248-9300)i
jNotes:
iGeorge called me back to provide some information requested during a phone call earlier today.During that earlier call I had requested some information about our containment particulate !
radiatian monitor. Specifically I had requested dimensional information about relative positions of |a
| the sample inlet line and the detector chamber. I had also asked about detector sensitivities to Cs-137 and Rb-88."
,
During this conversation George provided the following information:;4
The centerline to centerline distance between the sample inlet line'and the detector i-
:
i chamber, as projected onto the filter paper, is approximately 1.33 inches. This dimension'
was obtained by projecting the centerlines onto the filter paper, which moves in an arcbetween the sample inlet and the detector, then calculating the distance of the arc drawn;
between the two points.
: - Based on the original design filter media and an assumed flow of 8.5 cfm. the following; are the detector sensitivities for Rb-88 and Cs-137 :
I
L!
| Rb-88 126E+13 cpm /uCi/cc)
1 Cs-137 5.48E+12 cpm /uCi/cc;, i,
j 1 commmd on the dimensions, observing that the sample inlet point on the filter paper i
essentialiy n:ust be immediately adjacent to the detector's area of measurement since the 133;
inches is less than the combined radial distances of the two (1.50 in.) George agreedI
,
4
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O- -
,
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,
4
-
4
a
4
.. m ,__.___.__..____.._m.____-. _ . , _ _ . _ _ _ . . _ . _ _ _ _ _ . . _ _ _ _ _ . . _ . _ _ _ ._ ._ _
.
t k Wu l wa. d WAuthor: Russ Cox at USFPL800
*Date: 9/27/96 1:38 PM pg . j rpj. 76 00] ,Priority: Normal,
; TO: Chris Wasik /}g , j ./ j_i TO: Dave Faulkner ,
Subject: Rb-88 micron size in the containment+
.................................... Message Contents. -------- ------ - --------- --- -
'
Chris,
iThere are two viable St. Lucie production's of RB 88 '
1) direction fission, particle size indeterminate since it's tiedup with fuel mass.
2) decay from it's parent noble gas Kr-88, particle size = atom
| size
I believe you can throw out Case 1 and assume RCS concentrationsj maintained within Tech Spec allowable i.e., < DEQ LCO Limits. ji
For Case 2) We have some observations from 0.45 micron FILTERINGj of RCS water at Steady State Conditions:1
Influent to'O.45um filter: Rb 88 0.148 uCi/ml=
Retained on 0.45um filter: Rb-88 = zero suggesting < 0.45um,
.
The filtered water did not even show any Rb-88, which seems toindicate that the Rb 88 is sucked right up the filtering apparatuspump suction (does not collect with the filtered water).
,
The fact that we can see Rb 88 on the Containment Monitor Filter*
is probably due to atmospheric Kr-88 decay to Rb-88 (as a free4
atomic sized charged particle) where the filter paper can collect'
1 it. (Rb 88 particles collect on hair and other static fibers of| clothing). We have analyed Containment Monitor Particulate filters1 and found nothing but Rb-88 etc. So you can assume < 4 um per your
question. Russ'
I
J
_
i
1
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i
._ . _ . _ . . . . .. . _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . . . _ _ _ . . . _ . _ . _ _ . . _ _ _ _ . _ . . - . . __ _ . ..__..__.q!
.,
%
.
I
4
o4
: CONTAINMENT ACTIVITY INCREASE,. - (1.0 GPM LEAK)
---
14000_
__
i 1:000 ,_ . .
_.
1-
10000 +-
1 _, __
j - 1 8000 _
; __ g1
. s_ . 5 6000
,-
-...
- 4000 - -
!' _ _ _
2000
._
I-
0 1--- : . --- ---- -- :~~~
-
__ SRRWSSR8889RRSS8R88$9R89kkR8bh _---------- noun uu
TIME (MIN)._.
_
ev oss vi me- - ee 'M u m . w
,
-- |
COUNT RATE INCREASE(1.0 GPM LEAK)
.1000
_ |
900 l1
800~
700
. - - 600 - --'
E_
- g 500 + -
.-. . _ .
* _ . -t.e
300 -_
|
-
200 +- '
.__ ,.__
100 4 ~
__
- 0 - -- - - - - - - - -
SRNRWWWS$88RR888888998084908888RR8 _
\|. - - - - - - -----------
TIME (MIN)'~
. . . .. _ _ _
eh.gP m4
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J- ,_. . _ .
. . . _ _ __ _ _ - _ _ _ . _ . ._- _. _ .. _ ___ . . _ . _ . . _ . _ - . .m__. __ _ . _ _ _ .
4
%
4 UNIT 1 CONTAINMENT PAR TICULATE MONITORj <
RCC Rb-88 Conc. 1.37E-01 uCycc, __,_ RCS Leak _ Rate 1.00 gpm
, Activity into _RC_B 519 uCi/ min.
__
'14 MIN DELAY ~ 'D5TECTOW~
. ..RCB RC8 Rb-88 NEW READING
.
- .- g- (min) (uCi) (uCi/cc) (min) (cpm)
0 0 0.00E+00 14 0j 1 519 4.27E-09 15 0:
2 1017 8.38E-09 16 Oi3 1498 1.23E-08 17 0
~
! 4 1960 1.61E-08 18 1
5i 6~
2404 1.98E-08 19 1
5832~ 2.33E-08' 20" ~~~
"' 2~* 7 3243 2.67E-08 21 3I 8 3639 3.00E-08 22 4l 9 4626 ~ 3.31 E-08 23- ~~
~ - '
~ ~
616 238f~ 3'.61 E-08 2T~~
~'~~
8
| 11 4739 3.90E-08 25 1012 5079 4.18E-08 26 10;13 5405 4.45E-08 27 16i14~ ~ 5725~ 4.71 E-08 '28 19
~~
15 6022 4.96E-08 29 23!16 6313 5.20E-08 30 27117 6593 5.43E-08 31 321
~ 18 6862 5.65E-08 32 37! 4
19' ~ 7121 ~ 'ST5E-08 33 . 42! ~
~
l20 7371 6.07E-08 3_4 ] _ _ __48j ),
21 . 7611 6.272-08 35| . 541 |' *
60! j22 7841 6.46E-08 36 i' '
23 8064 6.64E-08 37 ! 67!,
24 8277 6.82E-08 38 , 741 {25' 84'85 6.99E-08 39~ 821
'
26 8681_. 7.15E-08 ._ 0 89r {427_ _, , 8871 7.31E-08 41 971 l
28 9054-
7.46E-08 42 . 106)' ' ' ~
29 '9231 7.60E-08 43 ~314I~
|
~30 9400 7.74E 08~
12314431 9564 7.88E-08 45 132'i
~ 52 ' ~ 9721~ ~ ~
'8.605 ~68 ~ 46 1411~
33 9872 8.13E 08 47 1511 |
34 10017 8.25E 08 48 . 1611 {'
35 10157 8.36E-08 49 1711 i
36 10292 ~ 8.47E-08 - 50 1811 !37 10421 8.58E-08 51 i 191! l38 10546 8.68E-08 52 2021.
'
39 1'd656 8.78E-08 53 "i13i 1' '~
40 10781 8.88E-08 54 223!41 10892 8.97E-08 55 234i42 10999 9.06E-08 56 245!,
~~
43 . 11102 9.14E-08 57 256i44 11201 9.22E-08
~~ is-~ ~~
58 2681
~ ' ~ 46"~
11556 9.30E-08 59~[~ Yf9I~11587 ' ~ ~ 9 38E-08 760? " " *?"I290L
~~
~
- . -- .. -_ ~_ _ .. _ - ,
AI
1
47 11475 9 45E-08 61 30248 11560 9 52E-08 62 313 !#
49 11642 9.59E-08 63 32.5 '50 11720 9 65E-08 64 336'
51 11796 9.71 E-08 65~ ~ ~ ~ - ~ ~5f8~~52 1186853 11935
~9.77E-08 66 359933E-08 _, 67~ ~ ~ ~ 375I !
54 12006 9.89E-08 68 38355 12070 9.94E-08 69 394156 12133 9.99E-08 70 406t
i
57 12193 1.00E-07 71 417-i58 12250 1.01 E-07 72 428:{59 12306 1.01E-07 73 440)
60 12359 1.02E-07 74 451!61 12411 1.02E-07 75 462:
; 62 12460 1.03E-07 76 474'i~~65' i5T0F 1.'03E-07 77 ' 485l
; 64 12553 ~ 1.03E-67 ~f8-~ 496;~
!'
65 12597 1.04E-07 79 507'66 12640 1.04E-07 80 51867 12680 1.04E-07 81 528:68 12720 1.05E-07 82 539,;#
69 12757 1.05E-07 83 549'70 12794 1.05E-07 84 560i
i71 12829 1.06E-07 85 5701 1~~ ~ ~~
72' 12862 1.06EJ07 86 5801
'
- 73 12895 1.06E-07 87 590i74 12926 | 1.06E-07 88 6001,
75 _.12956 . _1.07E .07 89 _ _609j_ 76 12985_,
,
1.07E-07 90 61912i
77 13012 1.07E-07 91 [~6'25I78 13039 _;
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,
9 Attachmznt 2 toPC/M 035194 !
< 4
' Revhlon 01 Page 1 of 8
i
I TTM s779-717e| PAos 23
REY. 08l
i CQILtlininent EIS.C.is s , Motil(Qr-Channels 31 and 32
!The containment Process Monitor consists of two subsystens-
! t particulate-gas systes and the iodine system. The iodine', syst does not incorporate monitoring equipsent, however, e
iodine 11ter may easily be removed for radio-assay.
| The i ne system consists,of a 904361 isokinet nossle, a M f t. A C f. ,
!s44-34 charc cartridge filter holder, a 844-24 ou panel, a
j e44-2 pumping e sa and a 904592 slave pump c 01 panel. The U'TN I
preceding items ar ted in a 844-5-50 enc ure. Also ygp |
associated with the ine system is a 9047 master pump control,, g,panel mounted in the cabinet "sa.
;
I The iodine system pump n be e rated from either the RMPmaster control panel or the en a slave control panel. Thepump control panels are inter 1 to prevent pump operation withd
either power switch'0FF. A er 0 ight, an PUMP ON light and aFIDW ALARM light complete e panel.
3
The particulate system is monitor and consists of at
! 904632 isokinetic n sle, a 841-1 continuous ter sampler, an841-3/3 gas samp , two 843-20 beta scintillat detectors, a844-3 check so e, a 844-20 check source, a 844-2 flow panel, a
; 844-1 pumpi system, two solenoid operated purge co el valves,
and a 9045 slave pump control panel mounted in the 84 5-502
enclosu along with the iodine system components. Also ociatedwith a particulate-gas systen are two 842-10 ratemeter rea uta es and a 904590 naster pump control panel sounted in the i
<- inet "B".
The prti-"hte-pr ey*= sample flows through both thecontinuous f11ter sampler where the particulate material is removedand monitored and the gas sampler where the remaining gaseousportion of the sample is monitored. Both samplers use betascintillation detectors. the detector outputs are routed to thecorresponding ratemeter readout nodule located in cabinet "B" of
the RMP.
The readout modules process the incoming detector signalinformation to provide visual panel meter readouts; 0-10mV recorderoutputs feeding the corresponding recorder inputs; computer outputsselectable to 50mV, IV or SV; rail Alarm indications and outputsconsisting of NO contacts on the normally energized Tail relaysgoing to normally energized 3 POT Tail alarm transfer relays; Highalarm indications and outputs tonsisting of No contacts on thenormally de-energized High t '' .m transfer relay going to normallyde-energized 2PDT High alors transfer relays and High-High alarm ,
indications and outputs identical to the High alarms. The EMDRAC-
viring diagram listed in T=ble 1 (Tab K) shows unused contacts onthe alarm transfer relays sn yh .:sn be customer assigned within thecontact ratings.
- - -- - - - -
.
*J
Attachment 2 to; PC/M 0351941' Revision 0.
Pege 2 of 8
:
1 VTW 4770-7174: EACH M8MP,S Phos 2+: Rsv. Se
! EAtH|
--The p:tiedet: ;10 system pung can be operated from eitherthe RMp master contro anel or the enclosure slave control panelexcept for the moving f11ter controls located on the master control;panel only. The p 7 controls are interlocked to prevent pump
:
icperation with either power switch 0FF. Operating controls on the
islave panel are power OFF/0W switch, white POWER ON indicator,motor START /STOP switch, red MOTOR ON indicator, amber FIAN FAULTindicator, amber FILTER TEAR / FILTER ADVANCE indicator /pushbutton,,
i
!and PURGE pushbutton. The master panel in additior,to ?4e previous
icontrols has a PROGRAM /0FF/ MANUAL selector switch ( chrulling themoving filter advance mechanism.. .
1 The Filter Tear alarm will actuate if the mving filteri3 separates or if the filter media is exhausted. The Flow Fault
alarm will actuate if the sample flow is restricted (high vacuum)| or if the sampling system should leak (low vacuum).'
t The iodine collecting charcoal cartridge any be removed froai the sampling system by stopping the pump, releasing the quicP=
connect fitting at the filter holder and unscrewing the fili.or!; A pre-filter of MV-70 or similar material should be|holder top.e
l placed so as to prevent particulate material free entering andcontaminating the charcoal cartridge. Both filters should be ,
'
changed at the same time and care should be used to preventij possible spread of radioactive material from the removed filters.j ::h::h th: :::;1: 01= :t af ter each filter 9n: tr E r:j y t:1 :; :: tier :t S ef= - The-4-low-4:eit e!!! ertrete if -
-sy etes C le; .et; vesies-sece-th:.. . : ;f;s;
f The purge pushbutton closes a normally open solenoid valve andi opens a normally closed solenoid valve to isoitte the gas sampler
from the sample line and admit air to purge the sample volume. Thei pump must be operating during air purge. If purging does not! sufficiently decontaminate the gas sampler a liquid decontaminantii may be used. stop the pump and isolate the sampler by closing the
sampler inlet and outlet valves. Open the solution inlet valve andfill the sampler with solution. Allow the solution to remain in:
! the sampler per sanufacturer instructions and drain by opening thesolution drain valve.i
2 CAUTIONi1
The decontamination solution may contain radio-:
I active saterial and should be drained under thesupervision of Health Physics personnel.
jFlush the saspler at least 10 times with water. Return all
valves to the operating position before restarting the pump.a
I ----rha.JQpple flew r ate should be set to e cfm using the u-
j -
-% an flowp 3 s s va lv e vnTTY9:+ wcxinQh e v 5 cuus g auge friew rst 14- exed following any system. e%M7pM:j. :orrection chart,
m et sensitivity is m :' an flewhs
i<
,
1
.- ___ _. _ . - _ ._.
_ . - .- . _ _ . -. - . .- _.
.
Attachment 2 toPC/M Q35194
,
Rettsion 0Page 3 of 8
Insert A
MRe Containment Process Monitor System consists a sample stream which supplies t the cabinet components.
||
The cabinet components consist of particulatep monitodog equipment and an i ne n!ter. De lod!ae filter'
does not incorporate any monitoring equipment, howev'er, the 844-34 charcoal cartridge filter holder may beeastly removed for radio-assay. Grab samples asay also be obtained from the sample stream by the use et valvesand quick disconnects.
!
De system consists of a 90431 Isoklaetle nonle, a 8411 costlanoes filter sampler, am 8413/3 gas sarapler, two843-20 beta scintillatlos detectors, a 844 3 check source, a 844 20 check source, a 844 24 flow panel, two solenoidoperated purge control valves, a slave pump control panel, and redundant pumping systesas. Also associated
!i
with the system are two 84110 ratemeter resdont modules and a maaster pump control panel mounted la the|RMP cabinet 'B'. There is a spare supply piping line with a 904321sokinetle noule Installed. ;
|
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i
|
- _ _ - . _ - . _ . - . -.
.
i' * \ttachment 2 to
l't'/>l 6.5! 194Resision 0
- page 4 or n
VIH B770 7178PAGE 30REY.08<
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VIM 8770 7176:
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CONTAINMENT Proct 55 MONITOR - SCHEMATIC DIAGRAM; 1
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Attschment 2 tsi
PC/M 035194-. .
| Revision 0j Page 5 of 8
52
YTH8770 7178PAGE 3o
! REV.08i CONTAINMENT PROCESS HONITOR - SCHEM ATIC DIAGRAM
tios.eI?>C mogrtg
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Attachment 2 toi
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Facahry . PSL __ UnitiPC/M No. 035 194
,
Attachment No. 3
Revision No. O,
Page- t of 3
TOTAL _EOUIPMENT DATA _ BAS.EE]IANGE PACKAGE COVER SHEET
Description of Change:
!
Change Containment Air Monitor Enclosure Pumps " Iodine" and "Chan. 31/32" to "1" and "2" !
IBasis for Change:
IThe iodine pump and the particulate gas pump are used as parallel redundant pumps.
;
References:
PCM 035-194
Ensimraing
Prepared by Date Y~O~#fVenfied by 3 / Date # - / 9- f/
I
Approved by _%scipline Supv/ Lead Engine r)Date V'
e
Ccnftstitatwn_MaDattmsni
Reviewed by:. .. Date:
S
Data Entry by: Date:__. _
Data Entry Venfied by- _._ Date:
For instructiens. see QI 2.81
JPN Form 53. Rev 10/92
TOTAL EQUIPMENT DATA HASE CHANGE FORM.
FACILITY PSL UNTT I PCM NO._035194 REV. O
COMPONENT TAG NO. CNTMT AIR.MNTR_ ENCL ATTACHMENT 3 SUPPL. 0'
ASSOCIATE COMPONENT PP MIPmQi)1/32 PAGE 2 OF 3
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COMPONENT TAG NO.. CNThiT. AIR MNTR ENCL ..__ ATTA CHM ENT__3__SUPPI, 9___,
ASSOC 1Alli COMPONENT PP MIA.CNIMLJODINE PAGE 3 OF 3 I
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PC/M 035-194Revision 0.
Page 1 of 6
MINOR ENGINEERING PACKAGE (MEP)PLANT PSL UNIT I PC/M NUM B E R _0).5- t M SUPPL 0
ORIGINATING DOCUMENT _NJR 81-835 EXPIR ATION DATE _12/31/94PC/M CLASSIFICATION SR _X.X_ QR NNS ADMINTITLE CONTAINMENT RARIATION PROCEES }]O,N.ITOR CONFIGURATION CONFLICTS
,,d.ND MINOR ENILAN.CIMENT _MODIFKATLQNS_
A DDITION A L R EQUIREM ENTS/ INSTR UCTIONS YES NO
AS. BUILDING TO COMMENCE UPON 1%SUANCE OF P ACKAGE?,_ _K
THIS PACKAGE HAS TIIE POTENTIAL TO SIGNIFICANTLY XIMPACT PERSONNEL RADIATION F.XPOSURE (me Qi 3.13K
_
IF YES, JPN FORM 72 IS REQUIRED.
10CFR50 59 SCREENING YES HO
1) DOES UfE CHANGE REPRESENT A CilANGE TO THEFACILITY AS DESCRIBED IN THE SAR?
2) DOES THE CHANGE REPRESENT A CilANGE TO,,,,,, X
PROCEDURES AS DESCRIBED IN THE SAR? _ X,,,,3) IS THE CHANGE ASSOCIATED WITH A TTST OR
__
EXPERIMENT NOT DESCRIBED IN THE SAR? X4) COULD THE CHANGE AFFECT NUCl. EAR SAFETY IN
__,,,
A WAY NOT PREVIOUSLY EVALUATED IN THE SAR? X5) DOES THE CHANGE REQUIRE A CHANGE TO THE
,,__
TECHNICAL SPECIFICATIONS? X
**OTI: IF THE ANSWER TO ANY OF THE AllOVE ISOT!* *1 V 6tFEN(NG Qt FSTIONS IS YES, DIE MEP CANNOT BE t' SED
REVIEWI APPROY A L:. , . -
,
_
IVTERFACE TYPEiGROUP - PREPARfD VERIFIED APPROVED FPL APPROVED *
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INPUT REVIE N/AW
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a
.
PC/M 035-194Revision 0,
Page 2 of 6
EF91E%FAI.E9 JMU7.I_CAU.9R
The purpose of this Minor Engineering Package is to correct conflictingconfiguration information for the Containment Radiation Process Monitor.Reference 1 documents the conflicting configuration information between thevendor technical manual (VTM) and r.he field condition, and is furtherdiscussed below.
The VTM schematic diagram (8770-7178, page 30 - see Attachment 2) shows theContainment Radiation Procece Monitor as two parallel subsystems / trains;the iodine system and the particulate-gas system, each with their own inletisokinetic nozzle, supply piping, process components (the iodine charcoalfilter in one train, the particulate filter sampler and gas sampler in theother train), pump, and discharge piping. The two pumpa' flow capabilitiesare 5 CFM and 10 CFM, for the iodine and particulate-gas trainsrespectively. The vendors intent for operation of the two trains is toestablish flows of 4 CFM and 8 CFM, by throttling open each pump'srecirculation valve.
The original design considered the pumps' flow rates (4 CFM and 8 CFM) toestablish isokinetic conditions.(match flow velocities) between the ringduct and the inlet to the sample streams. Nozzles for each sample streamare located at the ring duct, with appropriately sized orifices to achieveisokinetic conditions. This ensures that the weights of the radioactiveparticles do not become a factor in obtaining a representative sample.The field condition uses one train of the supply piping to feed theContainment Radiation Process Monitor components. The complete flow pathto the system process components is: one isokinetic nozzle, one train ofsupply piping, the iodine and particulate-gas process components arrangedin series, and then two parallel pumps (each having their own dischargepiping). This configuration gives the system more flexibility since onepump can now act as an installed spare. Note that this description
iresembles the post PCM 066-181 configuration (Ref. 4), which failed toupdate the vendor technical manual. Therefore, the changes to show onesystem train are considered administrative changes. Also Figure 12.2-1 ofReference 2 (PSL-1 FSAR) agrees with the above described field conditionfor the Containment Radiation Process Monitor components flow path.
Also noted in the NCR disposition was that the original system pumps werereplaced with the General Atomic pumps from the Unit 2 radiation monitors.
i
These pumps are 1/2 horsepower with a maximum flow capacity of Iapproximately 4 CFM and no recitculation flow path to fine control the |pumps' flow. The particulate filter still indicates trend changes in '
act .try. however with lower flew rues and a fixed filter paper speed. .
will ^id activir.y levels icwer han :n::: ally, and be less sensitive torans; art :hanges. The current -urpl line being used to supply the
precesa ~onitor ::mponents has -'e :->inetic nozzle sized for B CFM,. .
r.e>er since the pumps are net - C .e to supply this flow rate. 3cubisc<:netic ::~.iiti:n ' sample'e 21 ::ty is less than the sampled
,
airstream's /el:: ty) is producad. !
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PC/M 035-194Revision 0#
' ,
Page 3 of 6a
Per ANSI N13.1 (Sampling Airborne Radioactive Materials in NuclearFacilities) Section 4.2.2.3 " Particle Size Fractionation due to
; Anisokinetic Sampling", when air drawn through a collector in the stream is'
at a lower velocity than the stream velocity (subisokinetic), preferentialcollection of larger particles will occur. This will cause the observed;
J concentration of particles in the sample to be greater than the actual"
concentration in the duct. This increase in the concentration tends tooffset the decrease caused by the lower flow rate, and totally offset whenthe limit on particle size becomes very large. Therefore the subisokineticcondition has a minimal effect on the particulate filter monitor.
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The iodine charcoal filter and the gaseous monitor have fixed volume {chambers and therefore, the only affect a change in the volumetric flowrate can have on the gaseous monitor is on its time response delay.Accuracy is unaffected. In addition, these componenets are associated witn
; gas analysis, and a subisokinetic condition affects preferential; particulate concentrations, therefore the lower flow rate has no adverse! affect.
Based on the above, replacement of the pumps and deletion of therecirculation flow paths are acceptable for St. Lucie Unit 1 applications.The two isokinetic nozzles however will be swapped, such that the 4 CFKnozzle will supply the Containment Process Monitor components. )
'
Also noted was that the other isokinetic nozzle and supply piping train iscurrently setup to support obtaining grab samples. This is accomplished by
s
using quick disconnects and valving to the suction of either pump. This ;enhancement allows the Chemistry Department easier access to grab samples. '
Grab sample connections will be included in this MEP as a permanent,
modification, however they will be relocated into the main sampling stream..,
4 This would elimir. ate the need for a large purge if a grab sample is-desired ito supplement tha normal indication. The second supply piping train willbe labeled as spare. Or.her administrative and minor configuration.
>
differences (i.e., documenting the instrumentation used) will also be Iupdated.
1
The containment particulate and gaseous activity process monitors areincluded in the plant Technical Specifications (T/S's 3.3.3.1 and 3.4.6.1Per T/S Table 3.3-6, these monitors are required to provide indicationduring modes 1 through 4. Action statements require as a minimum, daily
j grab samples when either method is not available.a
The Containment Radiation Process Monitor's design basis is to provide a~
continuous indication in the control room of the particulate and gaseousradioactivity levels for the containment atmosphere. This is shown on theCWD's (8770-B-327 sheets 449 & 4501, which show the circuits to be notnuclear safety related. The circuits provide alarm and indication only.
4
and perform no automatic controlling functions, however they are used toi satisfy T.echnical Specifications. Based en the above, this package is
classyfiedascualityRelated.
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PC/M 035-194Revision 0Page 4 of 6 t
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; C911QIdisJ,ct!
Although the Containment Radiation Process Monitor is discussed in the SAR.'
FSAR section 12.2.4.1, this modification is not to the level of detailprovided in the SAR and results in no degradation, either directly orindirectly, to any safety functions required for analyzed accidents, anddoes not increase any radiological hazards. An FSAR Change Package will beincluded to update Figure 12.2-1, however these changes are considered! acceptable since the equipment will functionally operate as currentlystated in the FSAR.
3
2THER AFF1QIED R9CUMENTS b.
! !
QQSMM2D1 Reference Paragraph /Page or!Attach Revised Paces I
FSAR Figure 12.2-1 (See Attach. 1),
i TEDBi See' Attachment 31
S P E C I AI,_J](JI3qQTJ9]iS \ IME L EMENT A T,I_QN,_R EQ QIE EMENTS
1. Coordinate all work with Operations to obtain appropriate clearances.1
2. Perform or verify performed that the configuration of the Containment.
Process Monitor matches that of the Attachment 2 'After" sketch.l
3. Swap the isokinetic nozzles such that the 904631 is used to supply thesample train, and 904632 is used en the spare containment supply line.
4. Remove pages 252 through 259 ITab G) of I/M 8770-7178 and insert new*
pump information sheets of Attachment 2 (pages 5, 6, & 8).
: 5. Re-title the following EMDPAC irawings:' a) 3770-5834 " Isokinetic N u:le Mount. Locaticns for Cont.-
Atmosp."b) 8770-5835 - " Isokinetic Noz:le for Cont. Atmosp. - Sample",
c) 9770-5838 " Isokinetic No::le for Cont. Atmosp. - Spare"-
i
EQA.T MODIFICATION TESTING
Verify preper cperation of the Ocntainment Process Moniter by perf orming'
Reference 5.,
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PC/M 035-194i
Revision 07, * Page 5 of 6 -
Elf.EEKE.11.
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1. Non-conformance Report #1-835.2. St. Lucie Unit No. 1 FSAR Amendment 12,,
i1
3 3. St. Lucie Unit No. 1 Technical Specifications Amendment 125.i~
4, PCM 066-181, " Containment Radiation Monitor Upgrade. Unit 1".i
,,
5. Chemistry Procedure 1-C-67, " Calibration of the Containment Process|Monitor".
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{ 6. Drawing Change Tracking System, Package Information Tracking System [; and Active Safety Evaluation' databases, accessed March 31, 1994.;
hT. TAR M RTA '
Attachments NumberNun _Asr QatcIAE t on/T.i tle oLP.agn ;
1 FSAR Change Package 2 ;
i
2 VTM Update Package 8
3 TEDB Change Package 3 ;
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4
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PC/M 035-194Revision 0
-Page 6 of 6
REAWINGS(1) ALL AFTECTED (2) (3) MEP(4)
Eg/M DRAWING & REX QESSRIEIIQ)I.LTJTl R 11 TJ2dff DRAWINGS M E REY
JPN-035-194.001 0 CWD I 8770-B-327 4 Y 0Cheet 450
JPN-035-194.002 0 P&ID '4 9770-G 092 20 Y 0Fheetl
JFN-035-194.003 0 Inst. Detail I 977C-B-231 6 N OD.e e t 26-4
JPN 035-194.004 0 Inst. Detail ! 0770-B-231 2 N 0Sheet D
J7N 035-194.005 0 ENDRAC I 8770-5834 0 N 0
Set Special Instruction Number 5
'RNDOR MANUALS(2) MEP(-
&V3T LOGML4Et!1.lGt4PEB BEY Vf ND).R /f0VI MEEI 11 REMARKS BEM
9*70-7178 11 Victorean/Frecess Radiation I Update O
Monttoring System per Attach.No. 2 &special Inst.Number 3.
i 1 >DISCli'LIN E: C = CIVIL. E = ELECT; I = l&C; M ' MECH, N = NUCLEAR'(2) REVISION of afTected drawing vendor manual. Indicate New" if the drawingwendor manual is being created. The engineer isaccountable for reserving the new drawingivendor mantial number.thPRIORITY Indicate Yes or No if SRD fx PSL. Indicate 1 iPOD). 2 (CRDI. 3 (MDL 4 (ED). or 5 (other) for f'TN(JiMEP REVISION under which last drawing change was rnide.
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Attachment 1 ]PC/M No. J 5-194,
i
Revision -- 0 .
Page 1 of 2
FSAR._(.1%9GE_PA(grf (FCP).
.
P 1 a nt .3.L_Lu.c i.S_._.__ . ___ __ _ _ _ Unit 1
|__ _
FSAR PA$f3 ATTA(HED:
None 1J
ESAR FlGJ)RES ATTACHES:!iFigure 12.2-1 l
COMM_@TS:
N/A
Y~I2' W 9 k Y b~-~--- 4bf/h'
Frepared by/Date: ber,ified by/Date: ' '
YU/fY.
Agpfoved by/Date: '
j
Notes:!
1, All affected FSAR pages and tables are to be marked up and attached. If !additional space is required. then additional pages should be provided. New jinformation for inclusion in the FSAR shall also be provided.
2. The new or marked up pages are to be legible and of suf f1cient quality to bemicrofilmed . .
!3. If a figure is provided elsewtiere in the design package, then it need not be
duplicated in the FCP. However, a note should be provided in the commentsec*.'on referring to its location in the cackage. This also applies to newrauings whicn snould be added ': **e F$AR If a figure revisicn is to be
' - e 255R f gu.e witn a uccle arounc + c'uced in : s :'. * en i 7,
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j l il e'w hi s s's il lIN&tDI OUT SIDE
CONT AINMf NT CON T AINME N TWp gy.gqq {,
i<
hy:Sion 0 !ISOKINE78C NdZZLE hGC3C A0P04432;
1
ISOKINE 7 | 1" #ALL VALVE 8S AMPL E R l PIPING BY PUNCH ASER (ALL OTHER 3/4 VALVES)
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904530 a'T. PNL. / _ IODINE CHARCOAL
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g w/SELF LOCKg DISCONN ECT,
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RETURN-
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BY # A$$ IISOLATION r0
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s|5413/3 SAMPL M| (INLET _j g W/3" Pbr I'
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904589 ..jy -- i 843-29 $ DET. ' (A _ j BY-PASSONT.ML.1 - A 1 ISOLATION
A5-8wLp Ig SOLUTION~ ~
d L'; pg g i L. _ __ ._ _ _ __ _. , | DRAIN,
L i- '
'f A ( 6 5 0 I~ / 845-5 50 t aciowr. ' Ts_1-_ _ . -~
Arrray. * 2-- - 6 --
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FLORIDA POWER & LIGHT COMP AST. LUC'E PL ANT UNIT 1
CONT AINMENT R ADI ATICNMONITORING SYSTEM
FIGURE 12.2.1
_ _ . _ -- . . _ _ . ., .- _ _ _ . _ _ . . _ . _ . _ . _ _ .
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Facility PSL Unit 2- PC,'M-or DCR No, --PCM-100-294 _.- .- _ _ _ . _ . . - _ _ . _ . _ . _ - __ _ __. . - - -- -
Attachment No. N/ARevision No . N/A
Page 1 of 2
TOTAL EOUIPMENT DATA BASE CHANGE PACKAGE COVER SHEET ||
I
Description of Change: INCORPORATION OF SET-POINT LIST DATA TO TEDB'
FOR PCM 109-294
Basis for Change: PCM 109-294 ATTACHMENT 1
References:
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l
Engineering .r e m , , ,,, , ' ' ~ '' -,
. v'
Prepared by SEE PCM 109-204 Date
lVerified by SEE PCM 109-294 Date I
l
Approved by SEE PCM 109-204 Date(Discipline Supv/ Lead Engineer)
DRAWING UPDATE
Reviewed by: Date:
Data Entry bv: J'f. O 7 m - Date: $ -7 45Data Entry Verified by: Date: /// hf i- -
a /
.
'or instructions, see 013.6
JPN Form $15 'v12/94
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