ML18139B848
| ML18139B848 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna, 05000000 |
| Issue date: | 04/16/1982 |
| From: | Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.3.1, TASK-2.B.2, TASK-2.B.3, TASK-2.B.4, TASK-2.E.1.2, TASK-2.E.4.2, TASK-2.F.1, TASK-TM 182, GL-82-05, GL-82-5, NUDOCS 8204220379 | |
| Download: ML18139B848 (2) | |
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VIRGINIA ELECT.RIC AND POWER COMPANY RICHMOND., VIRGINIA 23261 R.H.LEASBURG VICE PRESIDENT NUCLEAR OPERATIONS April 16, 1982 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. 182 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 SCHEDULE FOR RESPONSE TO GENERIC LETTER 82-05 Vepco will provide our commitment schedule for the implementation of the NUREG-0737 items identified in Enclosure 1 of Generic Letter 82-05 no later than May 17, 1982.
We require this additional time because we are performing a thorough evaluation of the remaining work effort, manpow_er availability, and the details of material delivery and construction schedules.
We recognize that Generic Letter 82-05 is requesting firm commitment dates, therefore, it is our desire to supply these dates with a high degree of confidence.
Of the seven NUREG-0737 items identified in Enclosure 1 of Generic Letter 82-05, four items have been completed and are documented as such in Vepco's "Response to NUREG-0737 Post-TMI Requirements".
These completed items are:
I.A.3.1 (Simulator Exam),
II.B.4 (Training for Mitigating Core Damage),
II. E. l. 2 (Auxiliary Feedwater Indication and Flow Indication), and II. E. 4. 2 (Containment Isolation Dependability).
Vepco' s "Response to NUREG-0737" was transmitted to the NRC staff on December 15, 1980 (Serial No. 985).
Since the original transmittal of this document, Vepco has twice updated our response on June 18, 1981 and December 9, 1981 (Serial Nos. 358 and 655, respectively).
The remaining items identified in Enclosure 1 of Generic Letter 82-05 are:
II.B.2 (Plant Shielding),
II.B.3 (Post-Accident Sampling),
and II.F. l (Additional Accident Monitoring Instrumentation).
The completion schedules for these remaining NUREG-0737 items will be provided within the schedule given in this letter.
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Very truly yours, J)! f.iu;f
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R. H. Leasburg
e VIRGINIA ELECTRIC AND POWER COMPANY TO Harold R. Denton cc:
Mr. James P. O'Reilly Regional Administrator, Region II U. S. Nuclear Regulatory Commission Atlanta, Ga. 30303 Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. Robert A. Clark, Chief Operating Reactors Branch No. 3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555