ML18141A169

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Suppls 830325 Response to 830111 Request for Addl Info Re NUREG-0737,Item Ii.B 3, Post-Accident Sampling. Interim Core Damage Assessment Procedure in Use Until Westinghouse Owners Group Methodology Completed by End of 1983
ML18141A169
Person / Time
Site: Surry, North Anna, 05000000
Issue date: 10/20/1983
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Harold Denton, Eisenhut D
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0737, TASK-2.B.3, TASK-TM 038A, NUDOCS 8310270300
Download: ML18141A169 (2)


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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VrcE PRESIDENT NUCLEAR OPERATIONS October 20, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:

Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:

Serial No. 038A NO/DWL:acm Docket Nos. 50-280 50-281 50-338 50-339 License Nos. DPR-32 DPR-37 NPF-4 NPF-7 VIRGINIA ELECTRIC AND POWER COMPANY SUPPLEMENTAL SER RESPONSE RE: NUREG-0737,ITEM II.B.3 On January 11, 1983, the NRC issued a request for additional information (in the form of four SER open items) for Item II.B.3 of NUREG-0737, "Post Accident Sampling".

Vepco responded to this information request on March 25, 1983 (Serial No. 038).

Via subsequent phone conversations with Mr. Frank Witt of your staff.

Vepco was requested to upgrade our efforts and response regarding\\i.Elplementation of a

Core Damage Assessment Procedure':) Specifically, we were requested to implement an interim procedure in place of our proposed "expertise pool approach".

Vepco has implemented an interim Core Damage Assessment Procedure. At this time, our Corporate Emergency Response Plan Implementing Procedures references the availability of an interim Core Damage Assessment Procedure which is located in the Corporate Emergency Response Center Reference Library.

The interim procedure in place is the Duke Power Company, McGuire Core Damage Assessment Procedure.

We recognize that the McGuire procedure generally addresses only Iodine isotopic concentrations and is therefore not adequate as a final procedure.

Accordingly, as specified in our March 25, 1983 response, Vepco plans to utilize, when available, the Core Damage Assessment Methodology being developed by the Westinghouse Owners Group.

This "Methodology" is expected to be completed by the end of 1983.

. ---- 0310270300 03fo20.

PDR ADOCK 05000280 P

PDR

e VrnoINIA ELECTRIC ANll PoWER CoMPANY To Harold R. Denton cc:

Mr. James P. O'Reilly Regional Administrator Region II USNRC Atlanta, GA 30303 Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Mr. James R. Miller, Chief Operating Reactors Branch No. 3 Division of Licensing Mr. D. J. Burke NRC Resident Inspector Surry Power Station Mr. M. B. Shymlock NRC Resident Inspector North Anna Power Station