ML17289A533

Forwards App B, 8X8 Extended Burnup, of EMF-92-040 for Review & Approval of Mechanical Design Analysis to Extend Assembly Exposure Limits from 35 Gwd/Mtu to 37 Gwd/Mtu

ML17289A533
Person / Time
Site:	Columbia
Issue date:	05/11/1992
From:	Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17289A534	List: ML17289A533 ML17289A535
References
GO2-92-118, NUDOCS 9205180065
Download: ML17289A533 (6)

Text

ACCELERATED DI~TRJBUTION DEMONS~TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9205180065 DOC.DATE: 92/05/11 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) R

SUBJECT:

Forwards App B, "8X8 Extended Burnup," of EMF-92-040 for review 6 approval of mechanical design analysis to extend assembly exposure limits from 35 GWD/MTU to 37 GWD/MTU. D DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution NOTES RECIPIENT COPIES RECIPIENT COPIES A ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 1 D DEAN,W. 2 2 D

INTERNAL: ACRS 6 NRR/DET/ECMB 7D 1 1 NRR/DET/ESGB 1 NRR/DOEA/OTSB11 1 1 NRR/DST 8E2 1 NRR/DST/SELB 7E 1 1 NRR/DST/SICB8H7 1 NRR/DST/SRXB 8E 1 1 NUDOCS-ABSTRACT 1 OC/LFMB 1 0 OGC/HDS1 RES/DSIR/EIB 0

1 REG~IXZ ~'OP 1 1 EXTERNAL: NRC PDR 1 NSIC 1 1 D

D D

NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED: LTTR 24 ENCL 22

~ ~

WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Bax968 ~ 3000 George Washtngton Way ~ Rtobland, Wasbtngton 993524968 ~ (509) 372-5000 9205180065 920511 Hay 11, 1992 PDR ADOCK 05000397 G02-92-118 P PDR 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 APPROVAL OF EXTENDED BURNUP FOR 8x8 FUEL

References:

1) EHF-92-040, WNP-2 Cycle 8 Reload Analysis, dated March 1992

2) Letter dated July 23, 1986, GC Lainas (NRC) to GW Ward (Exxon Nuclear), "Acceptance for Referencing of Licensing Topical Report XN-NF-85-67(P), Revision 1, 'General Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel'"

3) Letter, GE Rossi (NRC) to GW Ward (Exxon Nuclear), dated July 18, 1986, "Acceptance for Referencing of Licensing Topical Report XN-NF-82-06(P) Rev. 1, 'gualification of Exxon Nuclear Fuel for Extended Burnup'"

4) Letter dated Hay 3, 1988, AC Thadani (NRC) to DA Adkisson (ANF) "Acceptance for Referencing of Licensing Topical Report XN-NF-82-06(P), Supplement 1, Revision 2, 'gualification of Exxon Nuclear Fuel for Extended Burnup, Supplement 1, Extended Burnup gualification of ANF 9X9 BWR Fuel'"

The Supply System is requesting NRC review and approval of the mechanical design analysis, provided in Attachment 1, to extend the assembly exposure limits for the Siemens Nuclear Power Corporation (SNP) 8x8 fuel from 35 GWD/HTU to 37 GWD/HTU. Attachment 1 was provided to the Supply System as Appendix B of Reference 1, in support of the Cycle 8 Reload Design. During Cycle 8, scheduled from June 1992 until April 1993, at least 4 assemblies are predicted to exceed the current limit. This letter and the attachment provide the justification for the request.

ool

.500~4

~ 1 4

)

Page Two Hay 11, 1992 APPROVAL OF EXTENDED BURNUP FOR 8x8 FUEL In Reference 2, the NRC accepted the reload design limited to previously approved burnup levels for the SNP 8x8 BWR fuel for batch average exposures to 30 GWD/HTU.

The SER also stated "staff approval for operation to extended burnup levels is contingent on the generic approval of the method by which burnup is considered in the design and analytical processes as described in XN-NF-82-06 (P) and Supplements 1, 2, 4, and 5." The approval of this methodology was provided in References 2 and 3. This SER also limited the SNP BWR fuel to the 30 GWD/MTU batch average exposure, contingent on the approval of additional justification for acceptable design limits for fuel rod bowing beyond these burnup values. The approval of the extended burnup to 35 GWD/MTU bundle exposure was provided by Reference 3. In summary, the approval of the mechanical design for the SNP fuel was limited to a batch exposure of 30 GWD/MTU until the methodology for extended burnup was approved. The methodology was approved in References 2 and 3.

Together these three documents provide approval for using the SNP 8x8 BWR fuel to 35 GWD/HTU bundle exposure and the methodology for justifying extended burnup on a plant specific basis. , prepared by SNP, is similar to ANF-90-018 (P), Revision 1, "Susquehanna Unit 1 8x8 Extended Burnup Design Report", Advanced Nuclear Fuels Corporation, June 1990. The Staff provided approval of that submittal in an SER to Mr. HW Kaiser, PPSL Co., November 2, 1990 (TAC 77165).

The R7 Refueling Outage is currently in process at WNP-2. This outage will involve a complete core offload. The core reload activities are currently scheduled to begin May 27, with the vessel internals to follow on June ll.

restart is scheduled for June 29. Failure of the Supply System to obtain the Plant extended burnup approval will necessitate an early shutdown near the end of Cycle 8 to preclude violation of the 35 GWD/HTU limit. We understand that this request has not been provided to the Staff within a normal time frame to support approval prior to the completion of the fuel assembly loading into the core, the Supply System would appreciate review and approval to support the June 29 plant restart.

If review and approval is not possible, please contact AG Hosier at your earliest convenience so that an alternative approach can be developed. Any changes to the reload design will have to be completed prior to June 13 to support the outage schedule.

Sincerely,

. C. Sorensen, Manager Regulatory Programs (Hail Drop 280)

HGE/bk Attachments cc: JB Hartin - NRC RV NS Reynolds - Winston & Strawn WH Dean - NRC DL Williams - BPA/399 NRC Site Inspector - 901A

~ 'I