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VIRGINIA ELECT.RIC AND POWER COMPANY RICHMOND., VIRGINIA 23261 R.H.LEASBURG VICE PRESIDENT                           April 16, 1982 NUCLEAR OPERATIONS Mr. Harold R. Denton, Director                                 Serial No. 182 Office of Nuclear Reactor Regulation                           NO/DWL:acm Attn: Mr. Darrell G. Eisenhut, Director                       Docket Nos. 50-280 Division of Licensing                                           50-281 U. S. Nuclear Regulatory Commission                                       50-338 Washington, D. C. 20555                                                   50-339 License Nos. DPR-32 DPR-37 NPF-4 NPF-7 Gentlemen:
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:
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.
Mr. Darrell G. Eisenhut, Director Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:
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:
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.
I.A.3.1 (Simulator Exam), II.B.4 (Training for Mitigating Core Damage),
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.
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).
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:
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.
II.B.2 (Plant Shielding),
Very truly yours,
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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J)! f.iu;f R. H. Leasburg
R. H. Leasburg  
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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}}
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}}

Latest revision as of 21:04, 5 January 2025

Informs That Util Will Provide Commitment Schedule for Implementation of NUREG-0737 Items Identified in Generic Ltr 82-05 by 820517.Incomplete Items Include Items II.B.2, II.B.3 & II.F.1
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)
v • d • e


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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.

,r-8204220379 8204-16

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e**.:;. * *. *\\.,
  • ~PR ::

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

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