ML20006C531

Application for Amends to Licenses NPF-4 & NPF-7,replacing Independent/Operational Event Review Group W/Mgt Safety Review Committee as Organization Responsible for Offsite Review Function

ML20006C531
Person / Time
Site:	North Anna
Issue date:	02/01/1990
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20006C532	List: ML20006C531 ML20006C533
References
90-038, 90-38, NUDOCS 9002080186
Download: ML20006C531 (3)

Text

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VlactNIA EticialC AND PowEn COMPANY RICHMOND, VIRGINIA 23261 C ,

4 February 1, 1990 i United States Nuclear Regulatory Commission Serial No.90-038 Attention: Document Control Desk NO/ETS Washington, D. C. 20555 Docket Nos. 50 338 i 50 339 License Nos. NPF-4 NPF-7 i

Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION e Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests I amendments, in the form of changes to the Technical Specifications, to Operating i License Nos. NPF 4 and NPF 7 for the North Anna Power Station Units 1 and 2 ,

respectively. This proposed change will replace the Independent / Operational Event

! > Review Group with the Management Safety Review Committee (MSRC) as the organization responsible for the offsite review function. This management committee Will meet quarterly to review and assess plant activities. In addition, the audits required by Technical Specification that were the responsibility of the Quality-Assurance Department will now be performed under the cognizance of the MSRC.

These changes will bring the North Anna Technical Specifications in line with the Standard Technical Specification Section 6.5. The proposed change is included in '

Attachment 1.

This request has been reviewed and approved by the Station Nuclear Safety and Operating Committee. It has been determined that the proposed changes do not involve an unreviewed safety question as defined in 10 CFR 50.59 or a significant '

hazards consideration as defined in 10 CFR 50.92. The basis for our no significant  ;

hazards consideration determination is included in Attachment 2.

L Very truly yours, W. L. Stewart Senior.Vice President - Nuclear J

Attachments

1. Proposed Technical Specification Change

2. Significant Hazards Consideration Determination t

9002080186 900201 3 '

PDR ADOCK 05000338 P PDC ,

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h cc: U. S. Nuclear Regulatory Commission Region ll  ;

101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. J. L. Cadwell ,

NRC Senior Resident inspector North Anna Power Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219 5

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The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by W. L. Stewart who is Senior Vice President -. Nuclear, of- Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document in behalf of ,

that. Company, and-the statements in the document are true to the best of'  ;

his knowledge and belief. '

Acknowledged before me this /Eday of MAem,, , 19 90, t

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