ML17263A652

Provides Addl Info Re Topical Repts BAW-2178P & BAW-2192P

ML17263A652
Person / Time
Site:	Ginna
Issue date:	05/16/1994
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
GL-92-01, GL-92-1, TAC-M83733, NUDOCS 9405260073
Download: ML17263A652 (6)

Text

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~)ACCELERATED DISTRIBUTION DEMONSTPWTION SYSTEM 1

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9405260073 DOC.DATE: 94/05/16 NOTARIZED: NO DOCKET; 8 FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G 05000244 AUTH:NAME AUTHOR AFFILIATION MECREDY,R.C. Rochester Gas & Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R. Project Directorate I-3 R

SUBJECT:

Provides addi info re Topical repts BAW-2178P 6 BAW-2192P. I DISTRIBUTION CODE: A028D COPIES RECEIVED:LTR ENCL SIZE: D TITLE: Generic Letter 92-01 Responses (Reactor Vessel Structural Integrity 1 S

05000244

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RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD1-3 PD 1 JOHNSON,A D

INTERNAL: NRR/DE/EMCB NRR/DORS/OGCB NRR/DRPE/PDI-1 NRR/DRPW D NUDOCS-ABSTRACT OC CB OGC/HDS 1 RE FILE 01 S RES/DE/MEB EXTERNAL: NRC PDR NSIC I

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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 15 ENCL ~3

)ZPrI lr IIIIIIIIII 8Z Zi7>> II!IiZZZZII ROCHESTER GAS AND ELECTRIC CORPORATION o 89 EAST AVENUE, ROCHESTER N.K 14649-0001 ROBERT C MECREDY TELEPHONE Vice Pierldent ArtEA COOE r le 546-2700 Cinne Nudeer Production May 16, 1994 U.S. Nuclear Regulatory Commission Document Control Desk Attn: Allen R. Johnson Project Directorate I-3 Washington, D.C. 20555

Subject:

Generic Letter 92-01 Revision 1 Reactor Structural Integrity Response to Request for Additional Information R.E. Ginna Nuclear Power Plant Docket No. 50-244 Ref.(a): Letter from A. R. Johnson (NRC) to R. C. Mecredy (RG&E),

"Generic Letter (GL) 92-01, Revision 1, 'Reactor Structural Integrity,'ochester Gas and Electric Corporation R. E. Ginna Nuclear Power Plant (TAC No.

M83733)", dated April 12, 1994 (b): Letter from R. C. Mecredy (RG&E) to A. R. Johnson (NRC)

"Reactor Vessel Structural Integrity, 10CFR50.54(f)

Response to Generic Letter 92-01, Revision 1," dated July 2, 1992 (c): Letter from R. C. Mecredy (RG&E) to A. R. Johnson (NRC),

"Analysis of Capsule "S" from the Rochester Gas and Electric Corporation R. E. Ginna Reactor Vessel WCAP-13902 December 1993," dated March 29, 1994 (d): Letter from R. C. Mecredy (RG&E) to A. R. Johnson (NRC),

"Reactor Vessel Structural Integrity Response for additional information" dated November 29, 1993

Dear Mr. Johnson:

The purpose of this letter is to provide additional information, as requested by reference (a), regarding Topical Reports BAW-2178P and BAW-2192P, and summary data file information included with reference (a).

The R. E. Ginna reactor vessel limiting material is the circumferential weld identified as SA-847, as indicated by reference (b). As shown in the reference (c) submittal, this weld

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0 4 demonstrates a Charpy upper shelf energy CUSE greater than the 50 ft-lb limit of 10CFR50 Appendix G through the licensed plant life of 32 EFPY. The cited Topical Reports BAW-2178P and BAW-2192P provide analyses and the technical bases which provide an alternative that would support continued plant operation should CyUSE values not meet the Appendix G threshold limit. These Topical Reports present a bounding case alternative for the B&W Owners Group which includes the R. E. Ginna reactor vessel. Though the R. E. Ginna reactor vessel surveillance capsule analysis, reference (c), demonstrates that the vessel CyUSE will remain above the threshold limit, Rochester Gas and Electric may seek approval based upon these Topical Reports for operation beyond 32 EFPY.

The data presented in the Summary File for Pressurized Thermal Shock and the Summary File for Upper Shelf Energy of reference (a) are currently being compared to the latest surveillance capsule data with the following changes to date:.

A. Pressurized Thermal Shock Table:

For column 3 Heat No. Ident. 125S255VA1, 125P666VA1, and 61782, the Column 4 fluence should be 3.68 E19 for all three heat numbers.

B. Upper Shelf Energy Table For Column 3 Heat No. 125S255VA1, 125P666VA1, and 61782, the Column 6 fluence should be 2.70 E19 for all three heat numbers.

These fluence values are based on surveillance capsule "S" data submitted in reference (c).

All other data presented in these summary file tables are still undergoing comparison review. For example, RG&E has previously indicated, in reference (d), that some USE values reflected in these summary tables do not represent the latest data. It should not be assumed that the information presented in the reference (a) tables is appropriate for use until the RG&E comparison with the latest data has been completed. Upon completion of this review, expected by June 30, 1994, a letter documenting the results will be transmitted to NRC.

Very truly yours, Robert C. Mecre y REJi332

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xc,: Mr. Allen R. Johnson (Mail Stop 14D1)

Project Directorate I-3 Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 USNRC Ginna Senior Resident Inspector