ML17262A919

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Forwards Response to GL 92-01,Rev 1 Re Reactor Vessel Structural Integrity.B&W Rept BAW-2166, B&Wog Response to GL 92-01 Also Encl
ML17262A919
Person / Time
Site: Ginna Constellation icon.png
Issue date: 07/02/1992
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, NUDOCS 9207080334
Download: ML17262A919 (5)


Text

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ACCESSION NBR:9207080334 DOC.DATE: 92/07/02 NOTARIZED: YES DOCKET ¹ FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

05000244 AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas a Electric Corp.

See RECIP.NAME RECIPIENT AFFILIATION gyes JOHNSON,A.R.

Project Directorate I-3

SUBJECT:

Forwards response to GL 92-01,Rev 1 re reactor vessel structural integrity.BSW Rept BAW-2166, "BaWOG Response to GL 92-01" also encl.

DISTRIBUTION CODE:

A028D COPIES RECEIVED:LTR ENCL Q SIZE:

TITLE: Generic Letter 92-01 Responses (Reactor essel Structural Integrity 1

R NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).

05000244

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RECIPIENT ID CODE/NAME PDl-3 LA JOHNSON,A INTERNAL: NRR MCDONALD,D NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB EXTERNAL: NRC PDR COPIES LTTR ENCL 1

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TOTAL NUMBER OF COPIES REQUIRED:

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II'OCHESTERGAS AND ELECTRIC CORPORATION 4

89 EAST AVENUE, ROCHESTER N.K 14649-0001 rr re ROBERT C MECREDY Vlcc Prerldent Clnna Nudear Production July 2, 1992 TELEPtrONE AREACODE 71B 546 2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:

Allen R. Johnson Project Directorate I-3 Washington, D.C.

20555

Subject:

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

Response

to Generic Letter 92-01 Revision 1

R. E. Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Johnson:

Generic Letter 92-01 was issued to obtain information needed to assess compliance with requirements and commitments regarding reactor vessel integrity in view of certain concerns raised in the (NRC) staff's review of reactor vessel integrity for the Yankee Nuclear Power Station.

The requirements are set forth in Appendix G and H of 10CFR Part 50.

In 10 CFR 50.61 the NRC also provided fracture toughness requirements 'for protecting pressurized water reactors against pressurized thermal shock events.

RG&E has also committed, Reference (a), in response to Generic Letter 88-11," NRC Position on Radiation Embrittlement of Reactor Vessel Materials and its Impact on Plant Operations",

to utilize the methodology in Regulatory Guide 1.99 Revision 2,

"Radiation Embrittlement of Reactor Vessel Materials",

to predict the effects of neutron irradiation as required by Paragraph V.A of 10 CFR 50 Appendix G.

For the Ginna Plant a discussion and evaluation of the Reactor Vessel Materials

Program, Fracture Toughness Requirements.

for Protection against Pressurized Thermal Shock Events (10 CFR 50.61),

and Charpy Upper Shelf Energy (USE) has been documented in Reference (b).

The NRC evaluation of the Technical Specification Pressure/Temperature limits relative to the neutron irradiation embrittlement on each beltline material in the reactor vessel is documented in Reference (c).

The RG&E Reactor Vessel Life Attainment Plan, Reference (d), contains a description and results concerning Irradiation Embrittlement Prediction and Ginna Specific Evaluation of Pressurized Thermal Shock, Flux Reduction Goal, and Upper Shelf Fracture Toughness.

RG&E has been a member of the B&W Owners Group and participated. in the preparation of the Owners Group response to Generic Letter 92-01 for the 16 plants in the B&W Owners Group Reactor Vessel Working Group.

The B&W Owners Group Response to Generic Letter 92-01 has been submitted to the NRC in Report BAW-2166 by Reference

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contains individual responses to the Generic Letter for each of these plants including the Ginna Plant.

The individual Generic Letter 92-01 requests and our response to each request is included in Attachment A.

Also enclosed herewith (Attachment B) is a

copy of that portion of BAW-2166 that is applicable to the Ginna Plant.

Ver truly yours, GAHN232 Attachment Robert C.

Mec dy Subscribed and sworn to before me on this 2nd day of July, 1992 MARIE C. VILLENEUVE

,%ovary. Public, State of New York Monroe County tComroission Expires October 31, 19~

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 US NRC Ginna Senior Resident Inspector

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