ML20217C306
| ML20217C306 | |
| Person / Time | |
|---|---|
| Issue date: | 03/20/1998 |
| From: | Collins T NRC (Affiliation Not Assigned) |
| To: | Holahan G, Sheron B NRC (Affiliation Not Assigned) |
| Shared Package | |
| ML20217C309 | List: |
| References | |
| TAC-M96746, NUDOCS 9803260419 | |
| Download: ML20217C306 (4) | |
Text
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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20565-4001
% # March 20, 1998 MEMORANDUM TO: Brian W. Sheron, Acting Associate Director for Technical Review THRU: Gary M. Holahan, Director Division of Systems Safety and Analysis FROM: Timothy E. Collins, Chief Reactor Systems Branch [1 [ M LN Division of Systems Safety and Analysis
SUBJECT:
WAIVER OF CRGR REVIEW FOR WCAP-14710(P)
REFERENCES:
Memorandum, E. L Jordan to T. E. Muriey, "CRGR Consideration of Topical Reports," September 29,1989. l Attached is the safety evaluation report (SER) prepared by the Division of Systems Safety and Analysis in which we accept Topical Report WCAP-14710(P), "1-D Heat Conduction ,
Model for Annular Fuel Pellets," (September 1996) for referencing in licensing applications.
We propose that the Committee To Review Generic Requirements (CRGR) review be waived in accordance with the suggested procedures in the memorandum referenced above.
WCAP-14710(P) describes a proposed model change to the 1-D heat conduction package used to analyze nuclear fuel rods in the Westinghouse Electric Corporation Qy.) emergency 1 core cooling system (ECCS) Appendix K evaluation models (EM), which allows for the explicit modeling of annular pellets.
We reviewed WCAP-14710(P) and concluded that, in the licensing application of explicit modeling of annular pellets to PWRs, the EM more realistically represents the fuel pin design, retains conservatism, and continues to meet the requirements (e.g.10 CFR 50.46 (a)(1)(ii) and 10 CFR 50, Appendix K) applicable to the EM in which the explicit modeling is used. Thus, the methodology described in WCAP-14710 (P) is an implementation of the overall methodological approach consistent with our regulatory guidance, without significant alteration.
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4 Brian W. Sheron .
According to the CRGR charter, the CRGR should review all staff approvals of topical I reports. However, since the methodology described in WCAP-14710(P) does not represent a deviation from the staff position embodied in 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. 1
Attachment:
As stated I i
/ original signed by/
Brian W. Sheron Approved: CRGR review is not necessary.
I DISTRIBUTION Central Files PDR SRXS RIF l GHolahan TCollins EWeiss FOrr FOrr R/F 9
SRXB:DSSA SRXB:DSSA 3RXB:DSSA D:DSSA 1 FORR* EWEISS* TCOLLINS* GHOLAHAN 3/13/98 3/13/98 3/13/98 31/dVY DOCUMENT NAME: G:WANPLT2.SER ;
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.....,o Mr. N. J. Liparulo, Manager Nuclear Safety Regulatory and Licensing Activities Nuclear Technology Division Westinghouse Electric Corporation Box 355 Pittsburgh, Pennsylvania 15230-0355
SUBJECT:
ACCEPTANCE FOR REFERENCING OF THE TOPICAL REPORT WCAP-14710(P)
"1-D HEAT CONDUCTION MODEL FOR ANNULAR PELLETS"(TAC NO. M96746)
Dear Mr. Liparulo:
We have concluded our review of the subject topical report of' September 1996 submitted by the Westinghouse Electric Corporation ()V_). The report is acceptable for referencing to the extent specified and under the limitations delineated in the report and in the associated NRC evaluation, which is enclosed. The evaluation defines the basis of acceptance of the report.
We do not intend to repeat our review of the matters described in the report and found l acceptable when the report appears as a reference in license applications, except to
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assure that the material presented is applicable to the specific plant involved. Our l acceptance applies only to matters described in the report. l The staff reviewed WCAP-14710(P) and concluded that the 1-D heat conduction model for annular pellets described therein is acceptable for incorporation in Westinghouse loss-of- l coolant accident (LOCA) Appendix K evaluation models, based on our finding that the !
annular pellet heat conduction model more realistically represents the annular pellets, and LOCA mods.2 incorporating it retain conservatism and continue to comply with the requirements of 10 CFR 50.46.
In accordance with procedures established in NUREG-0390, " Topical Report Review Status," we request that Westinghouse Electric Corporation publish accepted versions of ,
this topical report, proprietary and non-proprietary, within 3 months of receipt of this letter. I The accepted versions shall incorporate this letter and the enclosed evaluation between the title page and the abstract. The accepted versions shallinclude an "A"(designating
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Mr. N. J. Liparuto accepted) following the report identification symbol.
In addition W should submit proprietary and non-proprietary versions of other review documentation not included in the accepted versions of WCAP-14710 within 12 months of receipt of this letter.
If our criteria or regulations change so that our conclusions as to the acceptability of the report are invalidated, Westinghouse and/or the applicants referencing the topical report will be expected to revise and resubmit their respective documentation, or submit justification for the continued applicability of the topical report without revision of their respective documentation.
Sincerely, j
Timothy E. Collins, Chief Reactor Systems Branch Division of Systems Safety and Analysis Office of Nuclear Reactor Regulation Enclosurc:
WCAP-14710(P) Evaluation