ML17292B656

Forwards Rev 0 to Calculation ME-02-98-04, Fracture Mechanics Evaluation of N1 Safe End & Calculation Mod Record CMR-98-0243, Fracture Mechanics Evaluation of N1A Nozzle Safe End, as Suppl Info to ISI Exam

ML17292B656
Person / Time
Site:	Columbia
Issue date:	04/29/1999
From:	Coleman D WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17292B657	List: ML17292B656 ML17292B658 ML17292B659
References
GO2-99-083, GO2-99-83, NUDOCS 9905130169
Download: ML17292B656 (4)

Text

REGULAA~RY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9905130169 DOC.DATE: 99/04/29 NOTARIZED: NO DOCKET N FACIL:50-397 -WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUDE.NAME AUTHOR AFFILIATION COLEIIN,D.W. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Records Management Branch (Document Control Desk)

SUBJECT:

Forwards rev 0 to calculation ME-02-98-04, "Fracture Mechanics Evaluation of Nl Safe End" &, calculation mod record CMR-98-0243, "Fracture Mechanics Evaluation of N1A TITLE:

NOTES:

OR Nozzle Safe End," as suppl info to ISI exam.

DISTRIBUTION CODE .. A047D COPIES RECEIVED: LTR Submittal: Inservice/Testing/Relief from 1 ENCL j SIZE ASME Code - GL-89-04 E

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL 0 LPD4-2 LA 1 1 LPD4-2 PD 1 1 CUSHING,J 1 1 R INTERNAL: ACRS 1 1 FILE CENTER 01 1 1 NRR/DE/EMEB 1 1 TRACT 1 1 OGC/HDS3 1 0 RES/DET/EIB 1 1 RES/DET/EMMEB 1 1 EXTERNAL: LITCO ANDERSON 1 1 NOAC NRC PDR 1 1 D

'E NOTE TO ALL URZDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE LISTS DOCUMENT CONTROL DESK (DCD) ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 13 ENCL 12

WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ Richland, Washington 99352-0968 April 29, 1999 G02-99-083 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Gentlemen:

Subject:

WNP-2, OPERATING LICENSE NPF-21 SUPPLEMENTAL INFORMATION ANALYTICALEVALUATIONOF INSERVICE INSPECTION EXAMINATIONRESULTS

Reference:

Letter GO2-99-057, dated March 24, 1999, DW Coleman (SS) to NRC, "Analytical Evaluation of Inservice Inspection Examination Results, Additional Information" The purpose of this letter is to provide supplemental information to assist the NRC staff in review of WNP-2 Inservice Inspection activities associated with the evaluation of a planar indication found on weld number 24RRC(2)A-1 during the Spring 1998 refueling outage. The supplemental information consists of this letter and Attachments A and B.

Attachment A consists of an official copy of calculation ME-02-98-04, "Fracture Mechanics Evaluation of Nl Safe End," Revision 0, which reflects all approval signatures required by our calculation control process. This calculation is a fracture mechanics evaluation of the planar indication on weld 24RRC(2)A-1. Although technically correct, an unofficial copy of the calculation was inadvertently submitted as an attachment to the referenced letter. The unofficial copy established an examination schedule of 1020 days for weld 24RRC(2)A-1. Further refinements were subsequently made to the calculation and the official copy reflected a weld examination schedule of 870 days.

Attachment B consists of Calculation Modification Record (CMR) 98-0243, "Fracture Mechanics Evaluation of N1A Nozzle Safe End." This CMR applies to calculation ME-02-98-04 and provides updated fracture mechanics calculations and computer inputs. Based on the results of the CMR, the examination schedule for weld 24RRC(2)A-1 was re-adjusted to 970 days to account for changes in our refueling outage schedule.

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SUPPLEMENTAL INFO ATION ANALYTICALEVALUATIONOF INSERVICE INSPECTION EXAMINATIONRESULTS Page 2 of2 In addition, the following table is provided and contains information pertaining to our crack growth model. The table includes the crack growth associated with the fatigue cycles assumed to occur during each startup and shutdown cycle.

Startup Date IGSCC Fatigue Change Fatigue Change De th-Inches De th-Inches Len th- Inches June 1998 0.29 0.00064 0.0002 Jul 1998 0.29744 0.00066 0.00025 Au ust 1998 0.32916 0.00088 0.00029 June 1999 0.570493 0.00219 0.00081 November 1999 0.63994 0.00276 0.001 A ril 2001 0.927986 0.0051 0.002 The stresses used are conservative and are a combination of thermal stress and operating basis earthquake and safe shutdown earthquake dynamic stresses. The table has been adjusted to reflect current and future startup and shutdown cycles. As shown by the table, the summation of the incremental crack growth associated with the fatigue cycles is insignificant. The summation, when added to the calculation output, is less than the ASME Code allowable value for flaw size.

Should you have any questions or desire additional information pertaining to this letter, please call P J Inserra at (509) 377-4147.

Respectfully, DW Coleman Manager, Regulatory Affairs Mail Drop PE20 Attachments cc: EW Merschoff- NRC RIV PD Robinson - Winston Ec Strawn JS Cushing - NRC NRR DL Williams - BPA/1399 NRC Senior Resident Inspector - 927N

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