ML17292A287

Provides Suppl Info to TS Amend Request Re New Fuel Vendor

ML17292A287
Person / Time
Site:	Columbia
Issue date:	05/29/1996
From:	Bemis P WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GO2-96-111, NUDOCS 9606040083
Download: ML17292A287 (5)

Text

CATEGORY 1 z REGULATO INFORMATION DISTRIBUTION YSTEM (RIDS)

ACCESSION NBR:9606040083 DOC.DATE: 96/05/29 NOTARIZED: NO . ,

DOCKET ¹ FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washin'gton Public'Powe 05000397 AUTH. NAME AUTHOR AFFILIATION BEMISzP.R. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Provides suppl info to TS amend request re new fuel vendor.

DISTRIBUTION CODE: ROOID COPIES RECEIVED:LTR I ENCL C SIZE:

TITLE: OR Submittal: General Distribution NOTES:

RECIPIENT COPIES RECIPIENT- COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD4-2 LA PD4-2 PD COLBURN,T N

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'OTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTETH CONTACT THE DOCUMENT CONTROL SD"5(EXT. 415-2083) TO ELIMINATE YOUR NAME DESK,'OOM OWFN FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED]

TOTAL NUMBER OF.,COPIES",REQUIRED:'LTTR, 13,'; .ENCL'";;~

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0 aa WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352-0968 ~ (509) 372-5000 May 29, 1996 G02-96-111 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 SUPPLEMENTAL INFORMATION TO TECHNICAL SPECIFICATION AM<ADMI<2TTREQUEST RELATED TO A NEW FUEL V1<2ffDOR

References:

1) Letter GO2-96-089 dated April 24, 1996, & Parrish (SS) to VS Nuclear Regulatory Commission, "Request For Amendment To Technical Specifications"

2) Letter dated May 24, 1996, RC Jones (NRC) to DB Eberling-Koning (ABB/CE), "CENPD-300-P 'Reference Safety Report For Boiling Water Reactor Reload Fuel,'TAC NO. M91197)"

3) ABB/CE Report CE NPSD-803-P, "WNP-2 Cycle 12 Reload Report" dated May 1996

4) S. Levy Report SLI 96-04 dated February 1996, "An Assessment Of The ABB Method For Determining Critical Power For The Resident SPC 9X9-9 Fuel Assemblies In The WNP-2 Core" In Reference 1) the Supply System requested a Technical Specification Amendment to support use of Asea Brown Boveri/Combustion Engineering (ABB/CE) manufactured fuel and reload analyses.

Reference 2) documented NRC review and approval of the ABB reload analysis methodology, as should be reflected in Item 11 of proposed WNP-2 Technical Specification 6.9.3.2 The Cycle 12 core for WNP-2 will consist of 10x10 (ABB/CE), 9x9-9 (Siemens Power Corporation (SPC)), and 8X8-2 (SPC) fuel. In Reference 2) the staff stated:

,9606040083 960529 RDR ADOCK 05000397 P . PDR'

Page 2 SUPPLElVH~22ITAL INFORMATION TO TECHNICAL SPECIFICATION AMENDMENT REQUEST RELATED TO A NEW FUEL VI<ADOR The ABB/CE methodology for determining the operating limit maximum critical power ratio (OLMCPR) for non-ABB/CE fuel as described in CENPD-300-P and additional submittals...is acceptable only when each licensee application of the methodology identifies the value of the conservative adder to the OLMCPR. The correlation applied to the experimental data to determine the value of the adder must be shown to meet the 95/95 statistical criteria. In addition, the licensee's submittal must include the justification for the adder and reference the appropriate supporting documentation.

In Reference 1) the Supply System docketed the requested adder to be used by ABB/CE for the 9X9-9 SPC fuel. The value of the adder was 0, or the equivalent of a multiplier of 1.0. A similar value was not provided for the adder to be used for the 8X8-2 fuel. A discussion of this multiplier is provided.

In Reference 3) ABB/CE derived a multiplier for the 8X8-2 SPC fuel in the same manner as for the 9X9-9 SPC fuel. The ABB/CE results for 9X9-9 SPC fuel were independently reviewed as documented in Reference 4). A conservative multiplier for the 8X8-2 SPC fuel of 1.02 was used by ABB/CE in the evaluation of 8X8-2 OLMCPR, This approach bounds the 95% confidence limit on the 8X8-2 OLMCPR. This restriction is acceptable since the 8X8-2 assemblies will have substantial margins to OLMCPR in Cycle 12. The 8X8-2 fuel will occupy non-limiting locations on the core periphery (edge assemblies).

Should you have any questions or desire additional information regarding this matter, please contact L.C. Fernandez at (509) 377-4147.

Respectfully,

.R. is ice r i e t, Nuclear Operations (Mail Stop PE20)

DAS/lm cc: LJ Callan - NRC RIV TG Colburn - NRC KE Perkins, Jr. - NRC RIV, WCFO DL Williams - BPA/399 NS Reynolds - Winston & Strawn NRC Sr. Resident Inspector - 927N

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