ML17286A674

Suppl to 910228 Application for Amend to License NPF-21, Revising Tech Spec Safety Limits for Thermal Power,High Pressure & High Flow

ML17286A674
Person / Time
Site:	Columbia
Issue date:	03/21/1991
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17286A675	List: ML17286A674 ML17286A676
References
GO2-91-054, GO2-91-54, NUDOCS 9103280260
Download: ML17286A674 (5)

Text

ACCELERATED D7 BUTION DEMONS TION SYSTEM

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y REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9103280260 DOC.DATE: 91/03/21 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION SORENSEN,G.C. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Suppl to 910228 application for amend to License NPF-21, reviewing Tech Spec safety limits for thermal power, high pressure 6 high flow.

DISTRIBUTION CODE: A001D 'OPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution NOTES RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 1 ENG,P.L. 2 2 INTERNAL: ACRS 6 6 NRR/DET/ECMB 9H 1 1 NRR/DET/ESGB 1 1 NRR/DOEA/OTSB11 1 1 NRR/DST 8E2 1 1 NRR/DST/SELB 8D 1 1 NRR/DST/SICB 7E 1 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT OGC/HDS 1 RES/DSIR/EIB 1

1 1

1 0

1 OC/LFMB-QEG FIQE ~ "'O'Lg 1

1 0

1 EXTERNAL: NRC PDR 1 1 NSIC 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM-DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 22

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@~i WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 March 21, 1991 G02-91-054 Docket No. 50-397 U. S Nuclear Regulatory Commission Attn: Document Control Desk Washington, D. C. 20555 Gentlemen:

Subject:

NUCLEAR PLANT NO. 2, OPERATING LICENSE NPF-21 REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS SAFETY LIMIT; THERMAL POWER, HIGH PRESSURE AND HIGH FLOW REVISION

Reference:

G02-91-040, February 28, 1991, GC Sorensen to NRC, "Request for Amendment to Technical Specifications Safety timit; Thermal Power, High Pressure and High Flow" The following correcti.ons to the..Supply System reference application for change in the'NP-2 safety limit, thermal power., high pressure arid high flow are necessary. These corrections are marked on the attached technical specification change paper.

In several instances, both in tge cover letter and in the proposed technical specifications, the'ocument ANF-524(P)(A)-, Revision 2 and Supplements, is addressed as XN-NF-524(P)(A), Revision 2 and Supplements. In accordance with ANF guality Assurance Procedures, either prefix can be used to identify the documents. This document series has undergone a document number change from XN-NF-524(P)(A) to ANF-524(P)(A) during its evolution, and some references to this document i n various technical discussions have not noted this change. For the purpose of the WNP-2 technical specifications, the best reference is ANF-524(P)(A), Revision 2 and Supplements.

Bases Table B2.1.2-1, Uncertainties Considered in the NCPR Safety Limit, should not include a reference to the ANFB Critical Power Correlation standard deviation. The ANFB critical power correlation database mean is more than offset by conservatism in the ANFB correlation additive constants standard deviation included in the Supply System application for change to this safety limit. The SER on the topical report ANF-524(P)(A), Revision 2 and Supplements accepts the conclusion that the CPR correlation uncertainty is always bounded by the CPR uncertainty introduced by the additive constants.

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f Page Two RE()UEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS SAFETY LIMIT; THERMAL POWER, HIGH PRESSURE AND HIGH FLOW - REVISION Bases Table B2.1.2-1, Uncertainties Considered in the MCPR Safety Limit, should use a value of 0.0409 for the standard deviation of radial assembly power rather than the value of 0.0301 previously submitted. While the value of 0.0301 is referenced for radial assembly power in ANF-524(P)(A), Revision 2, p.22, this value is based on a TIP uncertainty of 0 '231. The SER on the topical report XN-NF-80-19(P)(A), Volume 1, Supplement 3 accepts the radial assembly power uncertainty for Microburn-B with a TIP asymmetry value of 0.060, which was used in the XTGBWR methodology, rather than the TIP uncertainty of 0.0231 used in ANF-524(P)(A), Revision 2. This value of TIP uncertainty, 0.060, when analyzed by the methodology described in XN-NF-80-19(P)(A) Volume 1, Supplement 3, paragraph 5.3.6, p.156, results in a value of 0.0409 for the radial assembly power standard deviation.

The Supply System considers these changes to be administrative and do not effect the proposed MCPR Safety Limits previously submitted (Reference).

Very truly yours, G. C. Sorensen, Manager Regulatory programs WCW:bw Attachments: Revised Marked-Up Technical Specification Pages B2-1, B2-2, B2"3 cc: JB Martin - NRC RV NS Reynolds - Winston 8 Strawn PL Eng - NRC DL Williams - BPA/399 NRC Site Inspector - 901A RG Waldo - EFSEC

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