ML20207A618
| ML20207A618 | |
| Person / Time | |
|---|---|
| Issue date: | 05/21/1999 |
| From: | Wermiel J NRC (Affiliation Not Assigned) |
| To: | Sheron B NRC (Affiliation Not Assigned) |
| Shared Package | |
| ML20207A621 | List: |
| References | |
| TAC-M94035, NUDOCS 9905270091 | |
| Download: ML20207A618 (4) | |
Text
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t UNITED STATES s
j NUCLEAR REGULATORY COMMISSION
\\.....l2 WASHINGTON, D.C. 30666-0001 May 21, 1999
- MEMORANDUM TO: Brian W. Sheron, Associate Directer p
for Project Licensing and Technical Review L
q, THROUGH:
Gary M. Holahan, Director M
l Division of Systems Safety an Andlysis r
i FROM:
Jared S. Wermiel, Chief Q[
- ]
Reactor Systems Branch Division of Systems Safety an Analysis g
SUBJECT:
WAIVER OF CRGR REVIEW FOR WCAP-14449(P) (TAC NO. M94035) h[
REFERENCES:
Memorandum, E. L. Jordan to T. E. Murley, "CRGR Consideration of Topical Reports," September 29,1989.
4 Attached is the safety evaluation report prepared by the Reactor Systems Branch, Division of 9
Systems Safety and Analysis, in which we accept Topical Report WCAP-14449(P), " Application R
of Best Estimate Large Break LOCA Methodology to Westinghouse PWRs With Upper Plenum j L Injection," dated August 1995 with clarifications, revisions, and additions through July 1998 for i 4 referencing in license amendment applications and other licencing actions. We propose that the 1
Committee To Review Generic Requirements (CRGR) review be waived in accordance with the suggested procedures in the memorandum referenced above.
7 WCAP-14449(P) describes the emergency core cooling system evaluation model (EM) that the e
l Westinghouse Electric Corporation proposes to use in license amendment applications and other licensing actions to demonstrate upper plenum injection (UPI) plant conformance with the requirements of 10 CFR 50.46 for postulated pressurized water reactor (PWR) large-break loss-of-coolant accidents (LBLOCAs). This EM was submitted as a realistic EM as described in 10 CFR 50.46(a)(1)(i). We have concluded that this EM is essentially the same as the Westinghouse WCOBRA/ TRAC Best Estimate LBLOCA methodology for Westinghouse 3-and 4-loop plants described in WCAP-12945(P-A) dated March 1998, and has the same underlying technical basis for the acceptability in demonstrating conformance with 10 CFR 50.46.
We reviewed WCAP-14449(P) with the assistance of the Idaho National Engineering Laboratory, and concluded that, in the licensing application of the EM to PWRs, the EM is 1
consistent with the Code Scaling, Applicability, and Uncertainty Evaluation Methodology. We j
also concluded that the EM conforms with the guidance of Regulatory Guide 1.157, "Best-j Estimate Calculations of Emergency Core Cooling System Performance." Thus, this methodology is an implementation of the overall methodological approach consistent with our CONTACT: Frank Orr, SRXB/DSSA NN fD q
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Brian W. Sheron regulatory guidance, without significant alteration. We, therefore, find the EM described in WCAP-14449(P) meets the requirements given in 10 CFR 50.46(a)(1)(i) and is acceptable.
According to the CRGR charter, the CRGR should review all staff approvals of topical reports.
However, since the methodology described in WCAP-14449(P) does not represent a deviation or new position from the requirements of 10 CFR 50.46 and 10 CFR Part 50 (Appendix K), and does not represent an increased burden on, or backfit to, industry, we believe that CRGR review is not necessary.
If you agree that a CRGR review is not necessary, please indicate your agreement by signing below. Otherwise, we shall proceed with preparation of an appropriate CRGR package.
Attachment:
As stated
/s/
Brian W. Sheron Approved: CRGR review is not necessary.
DISTRIBUTION:
F#e Conter PDR SRXB R/F l
TCollins/GHolahan JWermiel EWeiss 1
Forr DOCUMENT NAME: G:\\TBE4UPl3.WPD q
l To receive a copy of this documerst, indicate in the box C= Copy w/o attachment / enclosure E= Copy with attachment / enclosure N = No copy
- See previous concurrences OFFICE SRXB:DSSA SC:SRXB:DSSA C:SRXB:DSSA D:DSSA:NRR NAME FOrr*
EWeiss*
JWermiel*
GHolah DATE 4/15/99 4/19/99 4/19/99 5/f]499 OFFICIAL FILE COPY
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I Bkran W. Sheron \\
of Em'ergency Core Cooling System Performance." Thus, this methodology is an implementation of the overall methodological approach consistent with our regulatory guidance, without significant alteration. We, therefore, find the EM described in WCAP-14449 meets the requirements given in 10 CFR 50.46(a)(1)(i) and is acceptable.
According to the CRGR charter, the CRGR should review all staff approvals of topical reports.
However, since the methodology described in WCAP-14449(P) does not represent a deviation or new position from the requirements of 10 CFR 50.46 and 10 CFR Part 50 (Appendix K), and does not represent an increased burden on, or backfit to, industry, we believe that CRGR review is not necessary, If you agree that a CRGR review is not necessary, please indicate your agreement by signing below. Otherwise, we shall proceed with preparation of an appropriate CRGR package.
Attachment:
As stated x',
\\
\\
Brian W. Sheron i
Approved: CRGR review is not necessary.
NN\\\\N DISTRIBUTION:
File Center PDR
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TCollins/GHolahan
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j To receive a copy of this document, indicate in the box C= Copy w/o attachment / enclosure E= Copy with attachment / enclosure N = No copy
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OFFICE SRXB:DSSA, SC:SRJB,D,SSA C:SpB:DpSA D:DSSA:NRR \\
NAME FOrr ewe s JWe GHolahan
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4/ h/99 DATE 4//[ 99 4/[f/99 I
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r, N. J. Liparulo implementations, as reviewed by the staff. The accepted versions shall be formatted, providing up fr' opt a road map describing the overallM/ BE EM approach and comparison to the accepfable Code Scaling, Applicab5ty, and Uncertainty approach. It must also provide in an orderly al d understandable far.nion 1) descriptions of the approved changed individual correlation and/or changes in their use, and how they were determined to be appropriate,2) descriptions f the as approved validations performed on the code, and 3) a description of the approved unckainty evaluation process. It should be indexed such that information contained is readily located Also, it should contain in appendices historical review information, such as g
. questions and ac ed responses, and original report pages that were replaced. The accepted versions shallinclu an "A" (designating accepted) following the report identification symbol.
The staff will review t s report when it is submitted.
N If our criteria or regulations change so that our conclusions as to the acceptability of WCAP-14449(P) are invali' dated, Westinghouse and/or the applicants referencing the topical report will be expected to reh and resubmit their respective licensing basis documentation, or submit justification for the continued applicability of the topical report without revision of their respective documentation.
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Sincerely, ynthia A. Carpenter, Chief Geperic Issues, Environmental, Financial and Rulemaking Branch Divisi'on of Regulatory improvement Programs Office of Nuclear Reactor Regulation Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation N\\
Enclosure:
Safety Evaluation for WCAP-14449 Ng DISTRIBUTION:
File Center PDR SRXB R/F TCollins'/GHolahan JWermiel EWeiss Forr
'N To receive a copy of this document, indicate in the box C= Copy w/o attachment /enclosu E= Copy with attachment / enclosure N = No copy OFFICE SRXB:DSSA SC:SyBfSSA C:SgXB:DS,SA DRIP;NRR FOrrdh_
ewe JWer CCarpenteE -
NAME DATE 4// 99 4/)7 /99 4/h/99
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