BVY-95-125, Responds to GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity

Responds to GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity

ML20094L689
Person / Time
Site:	Vermont Yankee
Issue date:	11/17/1995
From:	Thayer J VERMONT YANKEE NUCLEAR POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BVY-95-125, GL-92-01, GL-92-1, NUDOCS 9511210075
Download: ML20094L689 (2)

Text

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L4 VEitMONT YANKEE 4

NUCLEAR POWER CORPORATION

.- Ferry Road, Brattleboro, VT 05301-7002 REPLY 70 g ENGINEERINGOFFICE 580 MAIN STREET BOLToN, MA 01740 (508) 779-6711 November.17, 1995 BVY 95-125

. United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555

References:

a. License No. DPR-28 (Docket No. 50 -271)

b. Letter R. P. Zimmerman (USNRC) to (All Licensees) NVY 95-72, dated May 19, 1995 (Generic Letter 92-01, Revision 1, Supplement 1) i c. Letter, J. T. Beckham, Jr. (Chairman, BWRVIP) to U. S. Nuclear Regulatory Commission Document Control Desk, "BWRVIP Response to NRC Generic Letter 92-01, Revision 1, Supplement 1, Reactor Vessel Structural Integrity," dated November 15, 1995

d. Report, "BWR Vessel'and Internals Project, Bounding Assessment of BWR/2-6 Reactor Vessel Integrity Issues (BWRVIP-08), *EPRI Report TR-105908, November 1995

Subject:

Vermont Yankee Response to Generic Letter 92-01, Revision 1, Supplement 1, Reactor Vessel Structural Integrity Per 10CFR50.54(f), this letter responds to Reference b) which requested ~

Vermont Yankee to provide:

An assessment of any change in best-estimate chemistry relating to reactor pressure vessel (RPV) materials.

- A determination of the need for use of the ratio procedure in accordance with the established Position 2.1 of Regulatory Guide 1.99 Revision 2, for those licensees that use surveillance data to provide a basis for the RPV integrity evaluation.

A written report including newly acquired data and results of any necessary revisions to the evaluation of RPV integrity according to 10CFR50.60, 50.61, 10 CFR 50 Appendices G and H, impact on LTOP or P-T limits in Technical Specifications, or a certification that previous evaluations are valid, c y - n ., , ,,,

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.e Yl'.HMONT Ymim Nt'Ct.F..ut POWF.H COHFOR.O HIN i

i V-1 I United, States Nuclear Regulatory Conunission j November 17,-1995

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a As a member of the BWR Vessel and Internals Project (BWRVIP), Vermont Yankee i endorses the plan of action described in References c) and d). We consider' ,

.these documents our response to Reference b) requests. We trust that the '

information provided is satisfactory; however, should you have any questions or desire any_ additional information on this issue, please'do not hesitate to contact us.

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Sincerely, VERMONT YANKEE NUCLEAR POWER CORPORATION-A // ,

ay K. Thayer

.Vice President, Engineering B

C: USNRC Region I Administrator USNRC Resident Inspector - VYNPS USNRC Project Manager - VYNPS STATE OF MASSACHUSETTS )

)ss WORCESTER COUNTY )

Then personally appeared before me, Jay K. Thayer, who, being duly sworn, did state that he is Vice President, Engineering of Vernent Yankee Nuclear Power Corporation, that he is duly j authorized to execute and file the foregoing document in the name and on the behalf of  ;

Vermont Yankee Nuclear Power Corporation, and that the statements therein are true to the best of his knowledge and belief.

l Kathryn Gat $s, Notary Public My Connission expires January 24, 1997 l

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