supplemental reload licensing submittal for reload 3.' s2 gg gg gg gg gg r,gg,grg rg mg gg 50 9 99m

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  • NE DO-24204s

    79NEU10 CLA3S

    JULY 197

    ' : n :n - :x :K : y:._ usLq' J -4

    SUPPLEMENTAL RELOAD E LICENSING SUBMITTAL FOR ,

    PEACH BOTTOM ATOMIC POWER STATION ,. UNIT 3, RELOAD NO. 3 i

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  • NE:0-2 4 203A ' 9N E D10 3 Class !

    July 1979

    SUF?LEMENTAL RELCAD LICEN3ING SUEMITTAL FOR

    ?EACH BOTTCM ATOMIC PCWER STATICN UNIT 3 RELOAD 3

    '

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    Prepared by 4[ ; Approved: '\ ', '- s, .7 A. M. Erv in R . O . E ru;;ge , "anager

    Operating Licenses II

    NUCLE AR E',E AGY 90;ECTS CIVISION * GENE R AL E LECT AIC CC*AP ANY SAN ;CSE, CA LIFO RNI A 95125

    GENER AL $ ELECTRIC

    / 1

  • E D0-24 204 A

    :.v.?O?'" ANT NO'":CE PEARD:NG

    CONTEW'S CF TH:J REPORT

    PLEASE READ CAPITUILY

    This repor* was prepared by General Electric solely for Philadelphia Electric Company for use with ~he U.a. Nuclear Regulatory Commission (UadRC) !c: amending PECO's operating licen3e of the Peach 20::cm Atomic Power J ation, Uni '. The informetion ocntained in this report is believed by General Electric to be an accurate and ::ue representation of the facts krcwn, obtained c: provid& to General Electric at the time

    this repor: was prepared.

    The only undertakings c! ~he Gem:31 ileccric Company respacting in!cima- tien in this c..cument a:e contained :n the contract between Philadelphia Electric Compang ani General Electric Company !c: nuclea: fuel and related services !c: the nuclear system for Peach Bottom Atomic ?cwer acation, Uni 3, ani :vthirg ccn~ained in this document shall be c~nstrued as

    u.gp.n, .i .v. , a3ia c., ". ~ .~a c ~. . '..'.a. ''=

  • NEDO-24204A

    1. PLAff"-U'i!QUE ITEX3 ( 1.0 )'

    Appendix A - Loading Error Limiting LHOR

    Append Lx B - Pressarised Test Assembly

    Appendix C - Fast Scram Control Ecd Drive

    Appendix D - New ththods - Fuel Loading Errcr

    Dundle PEDRB234H description is documented in non-approved submittal, Peference 2

    2. RELOAD 7UEL EUNDLES C'.0, 3.3.1, and 4.0)

    Fua l 'vra Number 'Jumba r Drilled

    Ir rad ia ted 7D250 Type II 52 3

    cDB274L 119 117

    3DB274H 68 63

    PTA 1 1

    SDRB283 252 252

    New P8DRB234H 272 272

    .v 3, , ,e , ,.,

    , ,, Ie c_.

    , , e- . n - .L,c, uvRc ,nA ,,ilu- 0,a,i.cr.! ( .3.i) -m , -, , ,:.c .:. o . j.

    Nominal previcus cycle expcsure: 3 3 6 3 M'4d/ t .

    Assumed relcad c'/cle exposure: '7160 M'4d/t-

    Co ra leading pattern : Figure 1.

    . - . - - . . . - - _- ,,-....,,,,.,,.,,.n,In..., . . , q ,. .q ,*, Uw w . a . E~n ,-n.,- 2 .,01 1. -,,--y ,4 LnLvdLALT U LVNO " *'., r r L L i . d e am A o a v a r ov. .6uw

    70 IDS, 200C (3.3 2.1.1 and 3.'.2.'.2)

    B O C k o_ .c , .

    Uncontrolled 1.124

    Fully Centrolled 0.9619

    Strongest Control Rod Out 0.9869

    R, Maximum Increase a. Cold Core Reactivity with 0.0000

    Exposure into Cycle, ak

    *( ) refers to areas of discussian in Reference 1.

    .

  • NE DC-2 4204 A

    5. STANDBY LIOUID CONTROL SYSTEM SHUTDCWN CA?A3ILITY ( 3.3.2.1.3)

    Shutdown Margin (ak) ppa (200C. Xenon Free)

    660 0.032

    6. RELOAD-UNIOUE TRANSIENT ANALYSIS IN?UTS ( 3 3 2.1.5 and 5.2 )

    ECC4 ECC4-2000 mwd /t'

    Void Coefficient N/ A'' (2/%Rg) -3.26/-10.33 -9 24/-11.30 7a id F rac t io n ( % ) 40.23 40.23 Doppler 33 efficient N/A'' (t/ F) -0.2366/-0.2242 -0.2279/-0.21650

    Average Fuel Temperature (cF) 1356 1356 Sc ram Worth N/ A** ( $ ) -35.48/-23.38 -33 93/-27.13 Scra= Reactivity vs Time. Figure 2a Figure 2b

    7. RELCAD-UNIOUE GETA3 TRANSIENT ANALYSIS INITIAL CCNDITION PARAMETERS (5.2)

    7x7 3x3 3xBR PTA/?Sx3R

    EOC4- ECC4- EOCu- 20CU-

    2000 2000 '000 2000

    _EO C4 mwd /t EOC4 mwd /t EOC4 mwd /t E0C4 mwd /t

    Peaking factors

    (local. rad ial

    and axial) 1.24 1.23 1.22 1.22 1.20 1.20 1.20 1.20

    1.23 1.30 1.37 1.43 1.39 1.56 1.47 1.56 * 40 1.40 1.40 1.30 1.40 1.40 1.40 1.40.

    R-Factor 1.100 1.100 1.098 1.098 1.C52 .052 1.052 1.052 Sundle Power (MWt) 5.41t 5.492 5 .77 7 6.02 6 6.237 6 .56 3 6.209 6.563 Sundle 210w

    (103 lbrne) 123.4 122 .3 111.1 109.3 111.1 109.3 111.3 109.5 Initial M:?R 1.23 1.22 1.29 1.24 1.30 1.2u 1.32 1.24

    'Mid Cycle Exposure Point * *N = 'hclear Input Dsta A: Used in Transient Analysis

    0 - -

  • tie DO-24204 A

    8. SELECTED MARGIN IMPROVEMENT OPTICNS (5.2.2)

    Exposure Cependent Licits: From 20C4 to E0C4-2000 M'4d/t and from E004-2000

    mwd /t to ECC4

    Q. rn.D R -g'l u -97 * Q ' t4'0" T. O U* Q C.,0 v L A J' f c . c'_) . j 'Jd . t' A ..'./q T.Jt *T m off**CA..A. .1.w i- . . . \Ja,

    A 4

    2i - . 3-2 w,- , . - . _w , . ,-, , . , . . - ..,,..r= l' 1; 1 22 1 ' 5:4 ;sie v s' "' ' * *

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    * * ' ' ' . -* n

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    3 - . 4 .r .:m. : m .-,; .

    , 0. , Uy,,, . L,D . .. . pD .a. A. 4 L n R O R ., . . . H . . d r- r. .,.# Ic- :r. w ... . n. .. u . . - ) . a . .;3. r.740 :. nm .. aA .. an - a. i u a . o i . . v . .- . 4 on. --

    SU.P.A R Y ( 5 . 2 .1 )

    Rod

    Position ACPR* v;HCR f KW/ f t) * * * *

    Rod Block (Feet 3x3R/ 3x3R/ isiting Set Poin* With d rwn ) 7x7'' 3x3 P8x3R/?TA 7x7'' 3x3 ?3xiR/?TA Ro d P ' ttern

    105 4.5 - 0.10 0.14 - 12.13 14.37 Tigure 6 1C6 5.0 - 0.10 0.16 - 12.09 14.41 rigure 6

    107''' 6.0 - 0.11 0.20 - 12.01 14.53 Figure 6 108 3.0 - 0.14 0.25 - 'i.70 16.39 rigure 6

    109 9.0 - 0.15 0.27 - 12.06 17.99 rigure 5 110 12.0 - 0.16 0.33 - 12.56 13.09 rigure 6

    ' Based on an initial MCPR o f 1.43 ( 3x3) an d 1.34 (3x33 and P3x3R' **7x7 fuel is located Only en the core periphery and is not limiting; t here fo re

    its response .2 not giten.

    * ** Indicates setpoint selected.

    "'* Includes the effects of densification power spiking.

    tall aCFR ralues calculated from initial power of 104.5%.

    7 s

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    NEDO-24204A

    11. CPERATING MCPR LIMIT (5.2) _

    BOC4 to EOC4-2000 mwd /t

    EOC4-2000 mwd /t to EOC4

    1.23 (7x7 fuel) 1.23 (7x7 fuel) 1.24 (3x3 fuel) 1.30 (3x3 fuel) 1.27 ( 3 x3R fu el) 1.30 (3x3R fuel) 1.27 (PTA/P8x3R fuel) 1.32 (?TA/P8x3R fuel)

    12. O'IERPRESSURIZ ATICN ANALY3IS SUMMARY (5.3 )

    ower Core Flow ?3L P Planty (%) /%) fosi2) (osic) Rascensa

    M3:7 Clocure 104.5 100 1271 1301 Tigure 7 (Flux Scram)

    -

    13 STABILITY ANALYSI3 RESULTS ( 5.4 )

    Decay Ratio: Figure 3

    Reactor Core S tability

    Decay Ratio , x;/x . 0.9Ca ( 105 % Ro d L in e - Na tu ra l

    Circulation Power)

    Channel Hydrcdynacic Performan^a ecay Ratio, x2 Xn / O '105% Rod ine - Natural Circulation Power)

    3x3R/P3x33/?TA Channel 0.29

    8x3 Channel 0.40

    7x7 Channel

  • NEDO-24204A

    14 LOSS-CF-COOLANT ACCIDENT RESULTS ( 5.5.2)

    MAPLH OR PCT Local oxidation

    Exposure (kW/ft) (cF) Fraction (mwd /t) P SD H B28 4 H PSDR3234H PSDRB284H

    200 11.3 1812 0.007

    1000 11.3 1813 0.007

    5000 11.7 1358 0.008

    10000 12.1 1994 0.009

    15000 12.0 1897 0.009

    20000 11.6 1858 0.008

    25C00 10.9 1777 0.006

    30000 10.2 1700 0.004

    15. LOADING ERRCR RESULTS (5.5.4)

    Limiting Events: Mislocated Bundle P 3DRB2 34H MCP R 21.07 Ro tated Bundle ? 3DRB2 3uH MCPR ll 07

    ,g ,m,. (r. .1,.u v a . :.C,m . tD .-no ad. A L .r- eo.o, ...c:ob.; . orc u. o. . . e

    Doppler Reactivity Coefficient: Figure 9

    Ac c i den t Reactivity Shape Function: Figures 10 and 11

    Scrim Reactivity Tunctions: Figures 12 ara 13

    Plant 3pecific Analysis Results

    Para eters No t Bounded:

    3 c ~15 React ivity Functions: Cold and Hot 3tartup

    Resu_ unt Peak Enthalpies (cal /g):

    Cald Hot Startuo ,93 =ciIsi 4

    a

  • 'tEDO-24204A

    17. REFERE! ICES

    1. " General Electric Soiling '42.ter Reactor Generic Reload Fuel Applicaticn,"

    August 1978, (!iEDE-24011-P-A).

    2. " General Electric Boiling ' dater Reacur Gencric F.eloa d Fuel Application,"

    May 1979, ( tIEEE-24011 -P- A , Amendment 3 ),

    .

    ;I

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  • NECO-242r4A

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