ML17291A994

Provides Info to Support Amend of TS 6.9.3.2

ML17291A994
Person / Time
Site:	Columbia
Issue date:	08/23/1995
From:	Parrish J WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GO2-95-160, NUDOCS 9508290337
Download: ML17291A994 (6)

Text

PRZOR1TY (ACCELERATED RIDS PROCESSING)

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9508290337 DOC.DATE: 95/08/23 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit. 2, Washington Public Powe 05000397 P AUTH. NAME AUTHOR AFFILIATION PARRISH,J.V. Washington Public Power Supply System R RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Provides info to support amend of TS 6.9.3.2.

DISTRIBUTION CODE: AOOID COPIES RECEIVED:LTR ( ENCL 0 SIZE:

TITLE: OR Submittal: General Distribution NOTES:

RECIPIENT ID CODE/NAME PD4-2 LA COPIES LTTR ENCL 'D RECIPIENT CODE/NAME PD4-2 PD COPIES LTTR ENCL CLIFFORD,J INTERNAL: ACRS I E CENTE 01 1 NRR/DE/EMCB CH HICB 1 NRR/DSSA/SPLB NRR/DSSA/SRXB 1 NUDOCS-ABSTRACT OGC/HDS3 1 EXTERNAL: NOAC NRC PDR D

0 N

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5DS (415-2083) TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 17

ti WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352-0968 ~ (S09) 372-SOOO August 23, 1995 G02-95-160 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

WNP-2, OPERATING LICENSE NPF-21 INFORMATIONTO SUPPORT AMENDMENTOF TECHNICAL SPECIFICATION 6.9.3.2

References:

1) Letter G02-95-104, dated June 6, 1995, JV Parrish (SS) to NRC, "Request For Amendment to Technical Specifications: Revision to Section 6.9.3,2 - Implementation of Generic Letter 88-16"

2) Topical report, WPPSS-FTS-127(A), "Qualification of Core Physics Methods for BWR Design and Analysis", November 1994

3) Topical report, WPPSS-FTS-129(A), Revision 1, "BWR Transient Analysis Model", November 1994

4) Topical report, WPPSS-FTS-131(A), Revision 1, "Applications Topical report for BWR Design and Analysis", November 1994 The Technical Specification amendment requested by Reference 1 would modify Section 6.9.3.2 by adding three topical reports pertinent to determination of reactor core operating limits for reload licensing applications, as required by Generic Letter 88-16. These three reports are listed above as References 2, 3, and 4.

References 2 and 3 describe the qualified methods and models used in Reference 4, and therefore are not used directly in analysis activities.

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INFORMATIONTO'UPPORT AMENDMENTOF TECHNICAL SPECIFICATION 6.9.3.2 Reference 4 would be used to establish the MINIMUMCRITICAL POWER RATIO (MCPR) core operating limitfor Technical Specification 3.2.3. Bounding analysis described in Reference 4 would be performed to confirm that the AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR) and the LINEAR HEAT GENERATION RATE (LHGR) core operating limits for Technical Specifications 3.2.1, 3.4.1.1, and 3.2.4 respectively remain applicable for current and future reloads.

Should you have any questions or desire additional information regarding this matter, please call me or D. A. Swank at (509) 377-4563.

Sincerely,

. V. Parrish (Mail Drop 1023)

Vice President, Nuclear Operations CJF/ml CC: LJ Callan - NRC RIV KE Perkins, Jr. - NRC RIV, Walnut Creek Field Office NS Reynolds - Winston & Strawn JW Clifford - NRC DL Williams - BPA/399 NRC Sr. Resident Inspector - 927N