ML20138J112

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Confirms 851001 Telcon Commitment to Supply Details of Updated Reactor Vessel Matls Surveillance Program for Facility by 860415.Programmatic Review of Vessel Matls Surveillance Programs Underway
ML20138J112
Person / Time
Site: North Anna  
Issue date: 10/21/1985
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Butcher E, Harold Denton
Office of Nuclear Reactor Regulation
References
85-722, NUDOCS 8510290253
Download: ML20138J112 (2)


Text

3 VIHOINIA ELucTHic Axn POS EH COMI%NY l{ICIIMOND, VI140 INIA 2006]

W.L. STEWART Vers PassinsNr NrcLsAn OrsaATIONS 5

October 21, 1985 Mr. Harold R. Denton, Director Serial No.85-722 Office of Nuclear Reactor Regulation E&C/NAS/DV:acm Attn:

Mr. Edward J. Butcher, Acting Chief Docket Nos. 50-338 Operatir:g Reactors Branch No. 3 50-339 Division of Licensing License Nos. NPF-4 U. S. Nuclear Regulatory Commission NPF-7 Washington, D. C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS NO. 1 AND 2 REACTOR VESSEL MATERIALS SURVEILLANCE PROGRAM On April 30, 1985, Virginia Electric and Power Company requested amendments in the form of changes to the Technical Specifications, to Operating Licenses NPF-4 and NPF-7 for North Anna Units No. 1 and 2, respectively.

The proposed changes involved updating the pressure-temperature limit curves to be applied during heatup and cooldown, in accordance with 10 CFR 50 Appendices G and H.

Also presented in our April 30 submittal were the evaluation reports associated with removal of the first capsules for the Reactor Vessel Materials Surveillance Program.

On Tuesday, September 24, 1985, in a Telephone Conference with the NRC staff regarding our submittal, Mr. Barry Elliot of the h7C requested that we supply the capsule withdrawal schedule associated with the Vessel Materials Surveillance Program, or commit to a date for supplying a program which would, as far as practicable, be in compliance with the latest revision of 10 CFR 50 Appendix H.

In a subsequent telephone call on October 1, 1985, we committed to supplying the details of an updated surveillance program for North Anna Units 1 and 2 by April 15, 1986. The purpose of this letter is to provide written confirmation of that verbal commitment.

As we discussed during our September 24 conference, we are currently performing a thorough programmatic review of our Vessel Materials Surveillance Programs for both our North Anna units in light of the most recent versions of 10 CFR 50 Appendices G and H, American Society for 8510290253 851021 DR ADOCK 050C0338 goal m

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VinointA Etccraic Awn Powra CourAwr to Mr. Harold R. Denton t

Testing and Materials Standard E-185 and 10 CFR 50.61, " Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events."

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The results of this evaluation will be reflected in our forthcoming submittal.

Very truly yours,

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W. L. Stewart i

cc:

Dr. J. Nelson Grace j

Regional Administrator h7C Region II 4

Mr. M. W. Branch h3C Resident Inspector North Anna Power Station Mr. D. Price Department of Health 109 Governor Street Richmond, Virginia 23219 Director, Office of Nuclear Reactor Regulation Attention: Chief, Core Performance Branch U. S. Nuclear Regulccory Commission Washington, D. C. 20555

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