ML17056C319

Forwards Upper Shelf Energy Uncertainty Analysis for Nine Mile Point Unit 1 Beltline Welds Final Rept MPM-USE-393215, Per 921013 Meeting W/Nrc Re GL 92-01,Rev 1

ML17056C319
Person / Time
Site:	Nine Mile Point
Issue date:	03/19/1993
From:	TERRY C D NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML17056C320	List: ML17056C319 ML18038A738
References
GL-92-01, GL-92-1, NMP1L-0747, NMP1L-747, TAC-M83486, NUDOCS 9303260004
Download: ML17056C319 (6)

Text

act"n.mru x-OOCvMKm" MSra mrOx SvSrKM REGULAT INFORMATION DISTRIBUTION STEM (RIDS)()ACCESSION NBR:9303260004 DOC.DATE: 93/03/19 NOTARIZED:

NO DOCKET'0 FACIL:50-220 Nine Mile Point Nuclear Station, Unit 1, Niagara Powe 05000220 AUTH.NAME AUTHOR AFFILIATION TERRYgC;D.

Niagara Mohawk Power Corp.RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)D NOTES: g~~mW~

SUBJECT:

Forwards"Upper Shelf Energy Uncertainty Analysis for Nine I Mile Point Unit 1 Beltline Welds" Final Rept MPM-USE-393215, per 921013 meeting w/NRC re GL 92-01,Rev l.DISTRIBUTION CODE: 8028D COPIES RECEIVED:LTR ENCL I SIZE: TITLE: Generic Letter 92-01 Responses (Reactor Vessel Structural Integrity 1 RECIPIENT ID CODE/NAME, PD1-1 PD INTERNAL: ACRS NRR/DE/EMCB NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB EXTERNAL: NRC PDR COPIES LTTR ENCL 1 1 6 6 2 2 1 1 1 0 1 1 1 1'ECIPIENT ID CODE/NAME BRINKMAN,D.

Ol NSIC NRR MCDONALDiD NRR/DORS/OGCB

~L REG FILE COPIES LTTR ENCL 2 2 1 1 1 1 1 0 1 1 1 1 DD D NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.504-2065)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!D TOTAL NUMBER OF COPIES REQUIRED: LTTR 20 ENCL 18 0 C'l II h V Mlle%,M 0 Si&oRIAWK NIAGARA MOHAWK POWER CORPORATION/301 PLAINFIELD ROAD, SYRACUSE, N.Y.13212/TELEPHONE (315)474-1511 March 19, 1993 NMP1L 0747 U.S.Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C.20555 Re: Nine Mile Point Unit 1 Docket No.50-220 DPR-63 TAC No M8 4

SUBJECT:

GENERIC LETTER 92-01, REVISION 1, REACTOR VESSEL STRUCTURAL INTEGRITY, UPPER SHELF ENERGY ESTIMATES FOR BELTLINE WELDS Gentlemen; Your letter of October 13, 1992, provided a summary of a meeting between the Staff and Niagara Mohawk Power Corporation to discuss our response to Generic Letter 92-01 for Nine Mile Point Unit 1 (NMP1).In the letter, the Staff recommended that Niagara Mohawk submit the uncertainty analysis for the evaluation of upper shelf energy (USE)for the beltline welds and include benchmarking against data in the Power Reactor Embrittlement Data Base.Our letter of February 26, 1993 (NMP1L 0739), indicated that the report on USE estimates for beltline welds would be submitted by March 22, 1993.Enclosed is a copy of our report entitled,"Upper Shelf Energy Uncertainty Analysis for Nine Mile Point Unit 1 Beltline Welds." Based on the analysis contained herein, Niagara Mohawk has concluded that the USE estimates provided in our July 2, 1992 response to Generic Letter 92-01 (NMP1L 0677)are accurate and conservative, and none of the beltline weld materials will exhibit USE levels below 50 ft-lbs prior to end of license.~SOO~5 9303260004 930319 PDR ADQCK 05000220 p PDR 4 e j~5"'ps~~,k>C V,, I~

Page 2 As discussed in the enclosed report, ABB/Combustion Engineering has recently notified Niagara Mohawk that they have discovered an inconsistency in the NMP1 beltline material documentation.

In particular, Niagara Mohawk now believes that only one wire heat/flux lot combination was used in weld seam 2-564-A/C.

The correct records pertaining to weld seam 2-564-A/C list the following information:

3/16 inch RACO-3 wire, Heat No.86054-B ARCOS B-5 flux, Lot No.4ESF Backchip: E8018 3/16 inch Lot HADD;1/4 inch Lot JBGD Accordingly, the enclosed report contains a corrected summary of the welds used in the NMP1 vessel fabrication.

This finding does not affect previous calculations or results submitted to the Staff.The only impact is to correct earlier documentation to indicate that wire heat/flux lot combination 1248/4K13F is not used in beltline weld seam 2-564-A/C.

Very truly yours, C.D.Terry Vice President Nuclear Engineering AER/pr 003708GG Enclosure XC: Regional Administrator, Region I Mr, R.A.Capra, Director, Project Directorate I-l, NRR Mr.D.S.Brinkman, Senior Project Manager, NRR Mr.W.L.Schmidt, Senior Resident Inspector Mr.K.Cozens, NUMARC Records Management

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