ML19093A960
| ML19093A960 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 10/02/1980 |
| From: | Sylvia B Virginia Electric & Power Co (VEPCO) |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| Download: ML19093A960 (2) | |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND,VIRGIN.lA. 23261 October 2, 1980 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
Dear Mr. Denton:
Serial No. 767 NO/DWL :jmj Docket Nos. 50-280, 50-281
_50-338, 50-339 License Nos. DPR-32, DPR-37 NPF-4, NPF-7 RESPONSE TO TMI ACTION PLAN REQUIREMENTS II.K.3.30/31 AND I.C.l SURRY AND NORTH ANNA POWER STATIONS In response to the September 5, 1980 letter from D. G. Eisenhut, NRC, on Preliminary Clarification of TMI Action Plan Requirements, the following information is provided.
Item II.K.3.30 of the subject letter requires that a detailed outline of the scope and schedule for revised small-break LOCA methods be submitted to the NRC by October 1, 1980.
Vepco's position on this requirement is that the current Westinghouse small-break LOCA model used to analyze the Surry and North Anna nuclear units fs already in conformance with 10CFR Part 50, Appendix K.
However, Westinghouse has indicated that they will address the schedule for completion of this requirement by January 1, 1982. Accordingly, Westinghouse will provide a detailed outline of the scope and schedule of this effort by means of a 4irect letter to the NRG on or about the October 1, 1980 deadline.
Item II.K.3.31 requires a plant specific small-break LOCA re-analysis using the revised model of item II.K.3.30. If the results of the new Westinghouse model (and subsequent NRC review and approval) indicate that the present small-break LOCA analyses for the Surry and North Anna nuclear units are not in con-formance with 10CFR Part 50.46, new plant specific analysis utilizing the new and approved Westinghouse model will be submitted to the NRG in accordance with NRC schedules.
Item I.C.l requires a re-analysis of transients, accidents, and inPdequate core cooling and preparation of guidelines for development of emergency procedures.
This information is to be received by the NRG by January 1, 1981.
Currently, Vepco is pursuing this requirement through the Westinghouse Owners Group.
The Owners Group has submitted emergency procedure guidelines for NRG review and comment (Westinghouse to NRC, letter OG-37 dated July 15, 1980).
To date, no feedback has been received by the Owners Group on this effort.
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VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton, Director During the regional meeting held September 22, 1980 to discuss the revisions and clarifications of TMI Action Plan requirements, the Westinghouse Owners Group expressed their willingness to meet with the NRG to further clarify the requirements of I.C.l.
Such a meeting is currently being pursued by the Owners Group for the purpose of determining what additional effort is required to satisfy the requirements of I.C.l.
It is Vepco's position that if significant additional effort is required, the January 1, 1981 deadline.is unrealistic.
The reason for this position is that Westinghouse h_as informed Vepco (and other Owners Group members) that their work load through January 1, 1981, could not support any significant revisions or additional analysis regarding the previously submitted emergency procedure guidelines.
A re-evaluation of our position will be provided to you following Westinghouse Owner Group discussions with the NRC regarding the status of the currently submitted emergency procedure guidelines.
cc:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Mr. Robert A. Clark, Chief Operating Reactors Branch No. 3 Division of Licensing Mr. B. Joe Youngblood, Chief Licensing Branch No. 1 Division of Licensing Very truly yours,
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B. R. Sylvia Manager - Nuclear Operations and Maintenance 2