ML18153C306

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Forwards Revised Tech Spec Pages,Addressing Constitution of Quorum & Timeliness of Mgt Safety Review Committe Meeting Minutes,Per NRC Request
ML18153C306
Person / Time
Site: Surry  Dominion icon.png
Issue date: 07/30/1990
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18153C307 List:
References
NUDOCS 9008030050
Download: ML18153C306 (2)


Text

... . ... e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 30, 1990 United States Nuclear Regulatory Commission Serial No.90-037 A Attention: Document Control Desk NL/ETS Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATION SUPPLEMENTAL INFORMATION In a letter dated February 1, 1990 (Serial no. 90-37),Virginia Electric and Power Company requested amendments, in the form of changes to the Technical Specifications, to Operating License Nos. DPR-32 and DPR-37 for the Surry 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.

During telephone conservations with your staff minor changes were requested to address the constitution of a quorum and the timeliness of the MSRC meeting minutes.

The requirement for a quorum is being changed from a minimum of four members to at least 50% of the members. The meeting minutes will be required to be prepared and distributed within 14 days of the meeting rather than prior to the next meeting. In addition, we are changing the audit frequency requirement for the Offsite Dose Calculation Manual and the Process Control Program from 24 to 12 months to be consistent with North Anna Power Station audit requirements. The revised Technical Specification pages are included in Attachment 1.

These minor changes do not impact the results of our original safety analysis and the significant hazards consideration determination. Please replace the appropriate pages in the February 1, 1990 submittal with the attached Technical Specification pages (6.1-10, 12, & 13). The basis of our significant hazards co sideration determination provided in our February 1, 1990 letter remains valid.

If you have any further questions or need additional infor tion to process this request, please call.

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~- L. Stewart Senior Vice President - Nuclear Attachment 9008030050 Q007~0 PDR A:000< frs6i:>C>2EK>

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cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219