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EGG-LOFT-5559 REV. 1

ESA L5-1/L8-2Project No. P394October 8, 1981

EXPERIMEllT SAFETY ANALYSIS (ESA) FOR LOFT TESTS

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RECEIVED

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U.S. Department of Energy_

Idaho Operations Office * Idaho National Engineering Laboratory

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This is an informal report intended for use as a preliminary or working document

Prepared for theU. S. Nuclear Regulatory CommissionUnder DOE Contract No. DE-AC07-76ID01570FIN. No. A6122

8203050491 811008PDR RES8203050491 PDR

. _ _ _ _ _ _ _ _ _ _ _ _ . . . . . . . . _ . . . . . . . _ - . . . . . _ - -----__----------_J_.

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EGrGio.no. ...

FORM ECEG 395'"" "''

INTERIM REPORT

Accession No.

Report No. EGG-LOFT-5559 Rev.1

Project No. P394Contract Program or Project Title:

LOFT Technical Support Division

Subject of this Document

Experiment Safety Analysis (ESA) for LOFT TestsLS-1 and L8-2

Type of Document:

Safety An'alysis

Author (s):

C. H. Cooper

Date of Document:

October 8, 1981

lResponsible NRC Individual and NRC Office or Division:

G. D. McPherson, Chief, LOFT Research Branch, Division of Reactor Safety Research,USNRC '

This document was prepared primarily for preliminary or internat use. it has not receivedfull revi 4 u and approval. Since there may be substantive changes, this document shouldnot be t onsidered final.

EG&G Idaho, Inc.Idaho Falls, Idaho 83401

Prepared for the-

U.S. Pluclear Regulatory Commissionand the U.S. Department of Er.ergy

Idaho Operations OfficeUnder contract No. EY-76-C-07-1570

NRC FIN No. A6122

INTERIM REPORT

-.- _____.__

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a .

EGG-LOFT-5559, Rev, 1

I

EXPERIMENT SAFETY ANALYSIS (ESA) FOR LOFT TESTS LS-1 AND L8-2

|

By

C. H. Cooper

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EXPERIMENT SAFETY ANALYSIS FOR LOFT TESTS L5-1 AND L8-2

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PREPARED BY: hd V f-['P/ C. H. Cooper

Author Date

REVIEWED BY: 'f_/5 -f( G. A. DinneenSafety Analysis and Date

Technical Specifications,

[[, f 3~~ / E. C. AndersonA ._r Systems ' Gat 6 ' .

'\M _%'N' M 7[f/#f T. F. Pointer

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;LOFT M nical Support Date '

Y 4!F/.N * m PRAC

Independent Review'7 7 Date

APPROVED BY: .lO [kM f//'/s/ L. P. Leach

6 LOFT Dirdcfor Datej

Authorized for release:'" 00E-10 APPROVAL

C. E. Williams ltr to R. W. Kiehn,CA 8. L. Freed

/ LOFT Configuration ControlDocument Control and Services Dated September 23, 1981

REVISION 1 APPROVALi

IDated October 8, 1981 ;

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iCONTENTSf

f 1. SCOPE ........................................................... 1

:

| 2. EASIL vX.aATING CONTROL DOCUMENTS ............................... 2

3. EXPERIMENT DESCRIPTION .......................................... .3

| 4. OPERATING PARAMETERS ............................................ 3i

!

5. EXPERIMENT ENVELOPE ............................................. 4

6. SAFETY ANALYSIS ................................................. 6

7. CONCLUSIONS ..................................................... 7

8. REFERENCES ...................................................... 8

FIGURES

:

1. PCS pressure calculation for "no ECCS" case ..................... 14

2. Vessel mixture level calculation ................................ 15

3. Hot spot clad temperature ....................................... 16

4 L5-1 Mode 8 LCO for high reactor power .......................... 17

5. L5-1 Mode 8 LC0 for low loop flow ............................... 18

6. Scaled LPIS-A flow rate for LS-1 analysis ....................... 19

7. Scaled HPIS ficwrate ............................................ 20

8. BST initial conditions .......................................... 21

TABLES

I1. L5-1 and L8-2 operating Mode 8 limiting conditions for.

,

| operation based on analysis bounds .............................. 9

2. LS-1 and L8-2 aperating Mode 8 safety limits based on |

| steady-state analysis .........................-3................ 101

3. 'L5-1 and L8-2 PPS trip setpoints--Mode 8 .....s 11 |,.................

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^ !.'miting conaitions for ini i3 tion of experiment ................ ,2

5. Sunmary of L5-1/L8-2 Mode 9 calculations ........................ 13.

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EXPEP:i'ENT SAFETY ANALYSIS (ESA) FOR LOFT TESTS LS-1 AND L8-2

1. SCOPE

This ESA assesses raaiological risks associated with performing thosespecific operations required to conduct the LS-1 and L8-2 experimentsdefined by the Experiment Operating Specification (E05), References 1 andla, and radiological risks associated with any operational occurrences andfaulted conditions during these experiments. This ESA is applicable tooperating Modes 8 and 9 which include:

1. Maneuvering in Mode 8 from Normal Power Operation conditions,Mode 7, to the LOCE preblowdown conditions;

2. Operating in Mode 8 at the LOCE preblowdown conditions whileperforming final preparations for the blowduwn; and

3 The normal test which is concluded when the following conditionsare met;

a. for LS-1, conducting LOCE Blowdown Operation, Mode 9, which

is concluded after LPIS flow initiation and core claddingtemperature returns to < saturation temperature and are

,

stable,

b. for L8-2, conducting LOCE Blowdown Operation, Mode 9, which

is concluded for test L8-2 after the PCPs are restarted andhave run for 10 minutes or if the LECS setpoint of 1300'Fhas been reached.

4. Conducting the recovery operation for both tests, Mode 9, whichis concluded when the primary coolant system (PCS) temperature isless than 200*F and the PCS is refilled. Thereafter, operationsto achieve plant recovery to cold shutdown, Mode 2, will be in

,

accordance with the P0M.

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risk 5 of equipment damage during the conduct of these experimentft

Was evaluated in Reference 2. The probability of Accumulator B being

available if required has been assessed in Reference 11 and this~ e hi14t y 1r"el is considered acceptable e', an unlikely event. Thus,with the special checks made prior to the conduct of L5-1, only

Accumulator "B" is considered available to protect the core to meet the

required damage criteria.

2. BASIC OPERATING CONTROL DOCUMENTS

1. LOFT Integral Test System Final Safety Analysis Report,Revision 1, Vnlumes I through 3, dated August 1977, Reference 3.

2. LOFT Technical Specification (LTS), Revision 5, dated October 8,

1979, Reference 4, including the following ORRs issued during the

interim: ORR-L-3072 and all other ORRs issued until the L5-1 andL8-2 experiments are completed.

3. R. P. Jordan, LOFT Experiment Operating Specification,~

Intermediate Break Test Series L5 Test LS-1, dated July 1981,i

Reference 1.*

4. D. B. Wood, LOFT Experiment Operating Specification, IntermediateBreak and Core Uncovery L8-2, October 1981, Reference la.

5. LOFT E0P LS-1, Reference 5. This document implements

requirements of the Experiment Operating Specifications and theTechnical Specificatioits. It sets forth all details pertainingto pre experiment plant operation, conduct of tae experiment,recovery frcm the experiment, and return of the plant tooperation in accordance with the Plant Operating Manual (P0M).

6. LOFT E0P L8-2, Referenc- Sa.

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3. EXPERIMENT DESCRIPTION

The LS-1 and L8-2 experiments are described in References 1 and la,and the trecific operatino methods for each experiment are given inReferences 5 and Sa.

Test L5-1 will simulate the rupture of a single 14-in. accumulatorline (one-of-four) in a commercial four-loop pressurized water reactor(PWR). The experiment is initiated by the opening of the broken loop coldleg QOBV. A rapid subcot. led blowdown occurs, immediately dropping the PCS

pressure to 1600 psia. The PCPs will be tripped at indication of reactorscram from low primary pressure. A scaled flow ECC (i.e., high and lowpressare injection, and accumulator injection) will be delivered to thesystem Scaled accumulator injection will be delayed until system pressurereaches 232 psia. The experiment will be terminated following core refloodand stabilization of the plant in a long term cooling mode. The intent ofthis test is to provide data to characterize system hydraulic response andcore thermal behavior for an intermediate break and to assess scaled ECCSperformance.

Test L8-2 is a repeat of test L5-1 with the following differences. Noscaled flow ECC other than HPIS will be delivered during the test. Both6ccumulators will be pressurized to >600 psia. After core uncovery hasstarted and a predetermined temperature rise has occurred, the PCPs will berestarted. This test will examine the effectiveness of this recoveryrestart procedure during an experiment in which the core is uncovered.

4. OPERATING PARAMETERS

Prior to initiating the blowdown, the final preblowdown conditionsrequired by tha EOS, References 1 and la, will be established. Thesesteady-state measured values and applicable tolerances are:

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Peactor Power, P (reduced from See Figure 4 ,

'

50 MW due to safety analyses)

Decay Heat Level 732 kW at 1000 sec

.

6 lbm/hr2.65 1 0.05 x 10P(C'> Mass Flow Rate, mVariable depending on SafetyAnalysis (see Figure 5)

Reactor Vessel Differential 52 + 3*F~

Temperature, aT

Reactor Inlet Temperature, Tc 534 + 2'F_

PCS Pressure, p 2156 + 15 psig

HPIS Injection Setpoint 1896 + 27 psig_

Accumulator A Liquid Volume 62.6 cu. ft (for L5-1).For L8-2 within normalTech. Specs

Accumulator A Injection Pressure 220 1 5 psig for L5-1,(600 psig for L8-2)

LPIS Pump Initiation Setpoint E36 + 8 psig

5. EXPERIMENT ENVELOPE

The operating envelope for the LS-1 and L8-2 experiment wasestablished by the application of analyses performed for RLD-1 Modes 6 and7. Reference 10 and by appropriate safety analyses for operating Modes 8

and 9. These analyses, reported in References 6 and 7, respectively,establish either the applicable Limiting Conditions for Operation (LCO),the Safety Limits (SL), and the PPS Trip Setpoints (PPS-TS) or the boundingconditions for the experiment. Tables 1 through 3 are the LCOs, SLs, andPPS-TSs for Mode 8; Table 4 gives the bounding conditions for Mode 9.Safety actions which mitigate consequences of the operational occurrencesare inherent in the safety analyses.

This ESA addresses radiological safety issues and establishes the

acceptability of associated risk by the following methodology:

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1. Specific Damage Criteria selected f rom the LOFT Technical

Specifications, Section 3/4.13, Reference 4, established themaximum allowable consequences for operational occurrence

cetegories as a function of operating mode.

2. Specific accidents listed in the LOFT FSAR, Reference 3, wereevaluated for appropriateness. If the analytical conditions of

the FSAR bounded the specific test maneuvering and LOCE

preblowdown conditions, acceptability was established and nofurther analyses were required. Otherwise, test specificanalyses were performed and results evaluated relative to theestablished Damage Criteria, Reference 6.

3. Operational occurrences and faulted conditions, Reference 7, werepostulated for the blowdown operation mode. Since these aretest-specific and, hence, have not been reported in the FSAR,each was either evaluated or analyzed. Results were comparedwith the established Damage Criteria.

4. Acceptability of radiological risk ussociated with Items 2 and 3was based upon satisfying relevant Damage Criteria; i.e., thecriteria are not exceeded.

As part of the experiment envelope for both tests, the PCP-MG PrimeMovers shall be tripped within 20 seconds after the test is initiated. If

a cladding temperature of 1200*F (indicated) for L5-1 and 1300*F(indicated) for L8-2 is attained, operator and automatic action will betaken to activate PPS-ECCS immediately (no operator delay time is assumed

due to redundant action).

For L8-2, if either PCP fails after the PCPs have been restarted,immediate reflood by at least one accumulator shall be initiated manually(nc delay is assumed as LECS temperature limit for PPS initiation is still

in effect).

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L8-2, witnin 10 minutes following pump restart, immediate refloodT-

by at least one accumulator shall be manually initiated.

Co cithe test if PCS pressure exceeds 333 psig (indicated) at165 sec after T , manually initiate PPS.

g

For either test if the LECS becomes inoperable (Loss of display onlyis not considered an inoperable condition), reflood by PPS shall De

initiated imediately.

For either test if both LECS display and PLSS display (loss of power

or signal) are lost (either may be lost but not both), innediate reflood byPPS shall be initiated.

Justification for these criteria are based upon results given inReference 7 and engineering judgement.

6. SAFETY ANALYSIS

The safety analysis for the L5-1 and L8-2 tests was performe? for

Modes 8 and 9. For Mode 8, the limiting accidents were used to establishthe allowable limits for steady state Mode 8 operation. These limits wereprimarily established from analysis of the following transients.

Limiting Control Rod Withdrawal Accident

Loss of Steam Load

One and Two Pump Rapid Coastdowns.

The LCOs, safety limits and trip setpoints based on analysis boundsare shown on Tables 1, 2, and 3.

For Mode 9, off-nominal initial conditions were used and the PCPs weretripped immediately after reactor scram in the analysis. Failure of allscaled ECCS (System A) was also assumed. The pressure and transient core

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mixture level was based upon the RELAP4 analysis for which the curves are

d wa on Figures 1 and 2 (Reference 7). These predictions were used in aFRAP calculation to determine at what temperature PPS-ECCS must be

initiatM to prevent core damage criteria from being exceeded. Asmentioned above, the most conservative pressure and core level results,Figures 1 and 2, were used in the FRAP analysis, resulting in Figure 3. A

summary of the analysis results is shown in Table 5. Thus, the temperaturefor manual and LECS action can be conservatively set at 1200*F (indicated)for L5-1 and 1300'F (indicated) for L8-2 if the actual test pressure doesnot exceed the worse case pressure curve from the RELAP-5 Analyses. The 1

LCOs for the initiation of the experiment are shown on Table 4

In the case of pump failure after restart in L8-2, an analysis wasmade to determine PPS requirements, see Reference 7. The results are shown

in Table 5.

Potential radiological dosages for a rupture of the ASME codedblowdown piping upstream of the Blowdown Suppression Tank is bounded by theL2-3 analyses, Reference 8. This event is classified as a Limited Faultand, as such, Damage Criteria D appliet (i.e., complete core melt--FSAR MHArelease limits). A postulated release from the Blowdown Suppression Tankrupture disc and relief valve is classified as an " anticipated" event

during Mode 9 and, as such, must meet Damage Criteria C) (i.e.,ERDAM 0524 at the one mile fence). This event is also bounded by L2-3

analyses.

7. CONCLUSIONS;

This ESA and the detailed safety analyses, reported in References 6and 7, show that the LOFT reactor can be operated safely in compliance withthe Damage Criteria in the LOFT Technical Specifications, Reference 4,during the conduct of the LS-1 and L8-2 tests (Modes 8 and 9).

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8. REFERENCES

1. R. P. Jordan, LOFT Experiment Operating Specification IntermediateBreak Test Series L5 Test L5-1, July 1981.

la. D. B. Wood, EGG LOFT 5544, LOFT Experiment Operating Specification,Core Uncovery/0egraded Core Cooling Test, L8-2, October 1981.

2. R. A. Yorg, Failure Mode Effects and Consequence Analysis on the LOFTLS-1/L8-2 Intermediate Break Tests, LTR LO-18-81-172, Rev.1,

1 October 8,1981.

3. LOFT Integral Test System Final Safety Analysis Report, Revision 1,IVolumes 1 through 3, ( August 1977).

4. J. C. Stachew (ed), LOFT Technical Specifications, Revision 5,October 8, 1979.

5. LOFT E0P (LS-1), Nuclear Experiment LS-1, Intermediate Break Test.

Sa. LOFT E0P (L8-2), Nuclear Experiment L8-2, Intermediate Break Test withCore Uncovery Test.

6. J. E. Fisher, LOFT LS-1 Mode 8 Safety Analysis, LTR LO-08-81-180,(September 1981) and DRR-L-5448, J. E. Fisher (September 1981).

7. S. A. Atkinson, et al., Safety Analysis for the L5-1 and L8-2 LOCETests, LTR LO-08-81-179, Rev.1 (October 6,1981).

8. Experiment Safety Analysis (ESA) for LOFT Nuclear Test Series L3-1,Apri l 25,1979,

9. D. G. Satterwhite, Shutdown Reactivity Analysis for Modes 2 Through 7,LTR-lll-97 ( Augus t 21, 1979).

10. S. A. Atkinson, W. R. Carpenter, and D. G. Satterwhite, LOFT ReloadCore-1 Modes 6 and 7 Safety Analysis, LTR-LO-08-79-137, (November 5,1979).

11. S. Z. Bruske, LOFT Accumulator B Unavailability for the L5-1/L8-2Tes t , L TR LO-19-81-07 7, September 1981.

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TABLE 1. LS-1 AND L8-2 OPERATING MODE 8 LINITING CONDITIONS FOR OPERATIONBASED ON ANALYSIS BOUNDSa,b(Source: Table 1, Reference 6)

..

Reactor Pnwer (High) See Figure 4

Loop Flow (Low) see Figure 5

Hot Leg Temperature 1591 F

PCS Pressure (High) 12257 psiac(Reactor Outlet)

PCS Pressure (Low) ->2081 psiac(Reactor Outlet)

Control Rod Position 51 to 57 inchesindicated withdrawn

dBoron Ccncentration in the PCS >500 ppm,

Steam Flow Control Valve SFCV stroke time shall beStroke Time within 10 to 40 s

Measured Peak-To-Core Average Power Ratio 12.562

a. All values are true values except CRA position which is indicated.

b. The shutdown reactivity by LTR 111-97, Reference 9, must be adhered tofor operations in Modes 2 through 4 to prevent criticality following anunlikely occurrence of a steam line rupture accident or a single rodejection accident.

c. For conservatism, the high pressure channel uses 1 atm. = 13 psia, andthe low pressure channel uses I atm. = 12 psia.

d. At this concentration criticality will not occur when all control rodsare bottomed, PCS at 2250 psig, and system at 68'F, Reference 9.

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lidLE P. LS-1 AND L8-2 OPERATING MODE 8 SAFETY LIMITS BASED ON>

STEADY-STATE ANALYSIS(Source: Table 2, Reference 6)

Param2ter Safety Limit

Reactor Powerfor 2.356 < P/A < 2.562 (151.02 - 40.602 P/A) MWfor P/A < 2.356 - 55.4 MW

Cold Leg Temperature 556'F

PCS Loop Flow 0.89 x Figure 5 value

High PCS Pie.;sure 2400 psia(ReactorOutlet)

Low PCS Pressure 2000 psiaa(Reactor Outlet)

a. No specific low pressure limit established; 2000 psia is lower boundfor the LOFT DN8 data.

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TABLE 3. LS-1 AND L8-2 PPS TRIP SETP0INTS--MODE 8(Source: Table 3, Reference 6)

Nominal Worst TimeCase Case Constant

Setpoint Trippoint (s)

High Reactor Power (MW) 147.12 - 149.12 - 0.25For 2.356 < P/A < 2.562 40.602 * (P/A) 40.602 - (P/A)For P/A < 2.356 51.5 53.5

High Hot Leg Temperature <593 <597 18

(*F)

PCS Loop Flow (Mlbm/hr) 1.5Power >40 MW 0.04673P* 0.04621P*-0.175Power 740 MW l.869 1.673

High Pressure (psia) <2282 <2340 1.0(psig) <2269 <2327

Low Pressure (psia) >2058 >2000 1.0(psig) >2046 >1988

Reflood Assist Bypass <5 <10 0.1Valve (percentopen)

P = nominal reactor power (MW).*

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TfBLE I, LIMITING CONDITIONS FOR INITIATION OF EXPERIMENT(Source: Table 1, Reference 7)

EOS/FSARa

I'arameter Analysis LCOs Reference Values

1 5 MW 50 MWb52Power

bFlow >2.39 Mlbm/hr 2.65 Mlbm/hr

TH 1598 F 591*F

MLHR 117.3 kW/ft 16 kW/ft

AT 52*F 52*F

bPCS pressure (high) 2257 psia 2156 psig

Accumulator B (PPS) c>588gsig 600 psigPressure 86 to 114 ft3c98 f tWater volume

Temperature Ambient Ambiente

Accumulator A(scaled)

600 psi c(LS-1)(L8-2)Pressure >588psig(L8-2) 220 psi

Water volume 62.6 ft above standpipe (L5-1) i

Temperature Ambientc

HPIS A (Scaled) dFlow rate See Figure 7 See Figure 4 of Reference 1Temperature Ambient

LPIS A (Scaled)Flow Rate See Figure 6Temperature Ambient

BST See Figure 8

a. True values.

b. See Section 4 for tolerances.

c. FSAR values.

d. Used in as-planned analysis. l'

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SUMMARY OF L5-1/L8-2 MODE 9 CALCULATIONS (Reference 7)' i.f ' : ' ..

Assumed PPS PCS Pressure Resulting LECS Reflood InitialReflood Capability Assumption T/C Setpoint Level

L5-1

1, 220 psig ACC-A Worse Case >l200 F Lower plenum

LPIS-A Pressure Curve sl/2 fullHPIS-A (WCPC)

2. 220 psig ACC-A WCFC + 20 psi s1200'f Lower plenumsl/P fullLPIS-A

HPIS-A

3. 220 psig ACC-A WCPC + 50 psi Does not lower plenum

LPIS-A meet DC s1/2 fullHPIS-A

4. 600 psia ACC-B WCPC + 50 psi 1300'F Lower plenum |$1/2 full

5. 320 psig ACC-A WCPC + 50 psi 1100*F Lower plenum$1/2 fullLPIS-A

HPIS-A

L8-2

1. 600 psia ACC-A WCPC + 50 psi >1300*F Empty vessel

LPIS-AHPIS-A

(PCS pumps cause effective cooling followed by pump trip)

2. 600 psia ACC-A WCPC + 50 psi >1300*F Empty vessel

LPIS-AHPIS-A

(PCSpumpsnoteffective)

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Figure 2. Vessel mixture level calculation

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