ML20141L944

Discusses Rept on Exxon Nuclear Co WREM-based Nonjet Pump BWR ECCS Evaluation Model.Informs That Model Conforms W/ App K to 10CFR50 & Acceptable

ML20141L944
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Issue date:	02/16/1977
From:	Bender M Advisory Committee on Reactor Safeguards
To:	Bowden M NRC COMMISSION (OCM)
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ML20091A092	List: IA-91-282, Forwards Written Statement Submitted by Sp Russo for ECCS Subcommittee Meeting on 770129,for Info.W/O Encl ML20141K026 ML20141K047 ML20141K056 ML20141K063 ML20141K066 ML20141K070 ML20141K076 ML20141K082 ML20141K091 ML20141K095 ML20141K121 ML20141K137 ML20141K141 ML20141K153 ML20141K163 ML20141K175 ML20141K185 ML20141K190 ML20141K359 ML20141K365 ML20141K368 ML20141K372 ML20141K375 ML20141K379 ML20141K382 ML20141K386 ML20141K390 ML20141K395 ML20141K398 ML20141K402 ML20141K406 ML20141K408 ML20141K415 ML20141K418 ML20141K423 ML20141K426 ML20141K432 ML20141K436 ML20141K441 ML20141K618 ML20141K620 ML20141K625 ML20141K626 ML20141K630 ML20141K633 ML20141K635 ML20141K637 ML20141K641 ML20141K643 ... further results
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FOIA-91-282 NUDOCS 9203270249
Download: ML20141L944 (2)

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• ; 3.h '7. l ADVISORY COMMITTf E ON RE ACTOR SAFEGUARDS t, / !yf / usmo row o. c. m february 16, 1977 Honorable Marcus A. Paaden Cnnirvan U. S. !;uelcar Regulatory Comission Washington, D.C. 20555

! SUa7ECT: REPORT 01 EXXCN 1;UCLEAR COSATI kW.-BASED lot 4-JET PCMP l DOILIlU h%TER REACIOR ECCS E*ALUATICN FDDEL Dear 12. Pa. den .

At its 202nd neeting, February 10-12, 1977, the Advisory Comittee on Reactor Safeguards completed its review of the Exxon !;uclear Coapany's ECCS Evaluation !bdel for non-jet pu p boiling water reactors. Sub-comittee ncetings were held on July 21-22, 1976, in Richland, Washing-ton, and on Dece:r.ber 21, 1976, and January 29, 1977, in Washington, D.C.

During its review, the Comittee had the benefit of discussions with representatives of the Exxon liuclear Conpany cnd the imC Staff. We Comittee also had the benefit of the documents listed.

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The ACPS previously reported on an evaluation nodel developed by. Exxon f' for non-jet pu p boiling water reactors in the Comittee's letter of March 10, 1975. Tnat nodel required the coupling of the Ge 1eral Elec-tric non-jet pt:rp boiling water react 6r nodel for blevJown with the Exxon nodel for the fuel heatup. We Comittee recomanded that future applications be based upon an integrated set of approved codels. We first Exxon integrated ixdel reviewed by the Comittee was approved in i a September 15, 1975 report on an evaluation nodel for a PWR.

he present non-jet parp BWR intcyated evaluation nodel uses ceveral -

portions of the Exxon UREM-Based Gen? tic PWR Evalbation Mod?l, an'd the Comittee concurs with the NRC Staff that the blowdown portions are treated in an acceptable manner. ,

he NRC Staff has not accepted the proposc'd transient critical heat flux correlation, and Exxon has agreed to use a conservative pro-cedure proposed by the Staff. %c Comittee concurs with the Staff '

in inposing this requirement.

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lionoudble !breas A. PMen February 16, 1977 Use of the Evaluation tb3e1 will reqJire revleW by the MC Staf f of planta specific iten for case-cy-case applications. She Comittee telieves that, with the tcqJirn ents set forth by the 7;ic Staf f, the Exxon 1;uclear Co@any UFLHused :;on-Jet hr p Boiling Water Reactor ECCS D/aluation ficdel will '

conform to App:ndix K to 10 CPR 50.

Drs. S.11. Cush and M. W. Carton did not participate in this review.

Sincerely yours, i

M. Bender e

' Chairran l PIrDtt;CES:

i 1. Exxon 1:uclear Co pany, *CAPEJ.: A Computer Program for Predicting l

Pellet-to-Claddi.ng Heat Transfer Coef ficients," >21-73-25, August 13,

! 1973, as found in r;-174 "D:nsification Ef fects on Exxon ltuclear i Boiling Uater Reactor Fuel," lloverber 1973, and Supplerent 1, 2 llove-ber 29, 1973.

2. Exxon 1:uclear Company, "210: A Two-Dimensional Qucnching Model,"

>21-74-25, Revision 1, Octot>2r 30, 1974.

I 3. Exxen !;uclear Company, "BUwr3: A Coquter code to Determine the Daforratien and the Ontat of Bulging of Zircaloy Fuel PMCladding,"

>21-74-27, Revision 2, Deccab2r 1974.

4. U.S.1:aclear Regulatory Comission, "hAD1: Water Reactor Evalua-f tion Model," Revisicn 1, Iby 1975.

5 Exxon 1:uclear Co reany, " Exxon 1:uclear Company WREM-Bastd Generic PdR IrCS Dvaluatien 1:odel," E4-75-41, Vol. I, Vol. II, cnd Appen-dices A, B, C, and D, Vol. III (Revision 2), and Surrp1<nents 1-7, July-tioverbar 1975.

Exxon !;uclear Ccg any, "frUXY: A Generalized Multirod !!eatup Code

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with 10 CFR 50 Appendix K Ueatup Option - User's Ftinual," 204-CC- '

33(A), July 28,1975.

7. Exxon 1;uclear Ccapany, " Core Physics Methcds and Data Used as Input to IDCA Analysis," >N-75-43, August 1975.

8. Exxon 1;uclear Co pany, '"Ihe Exxon 1;uclear Company McMused NJP-Bh'R ECCS Dealuation Model and Application to the Oyster Creek Plant,"

>21-7 5-55, revision 2, August 1976, Supplenent 1, SeptcJ2cr 1976, and Supplerent 2, Decerber 1976.

9. Interrountain Technologies, Inc., " Comparisons of the REIAP-4 Computer Code with Exp3r irental Data," IMcceb2r 1976

10. U.S.1:uclear Rojulatory Comission, " Revision 1 to Safety Evaluation Report ikgarding Review of the Exxon 11uclear Company 1 on-Jet remp lbiling b'ater Reactor ECCS INaluation P.odel for Conforrance to Appmlix K to 10 CFR 50 by the Of fice of Nuclear Henctor Regulation,"

January 14, 1977.

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