ML18150A107

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Application for Amends to Licenses DPR-32 & DPR-37,changing Tech Spec Sections 3.7 to Reformat & Upgrade Table 3.7.1, Reactor Trip Instrumentation Operating Conditions & 4.1 to Modify Surveillance Requirements for Reactor Trip
ML18150A107
Person / Time
Site: Surry  Dominion icon.png
Issue date: 05/22/1987
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML18150A108 List:
References
87-212, GL-83-28, NUDOCS 8706020023
Download: ML18150A107 (2)


Text

e e 10 CFR 50.90 VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 M~y 22, 1987 W. L. STEWABT VICE PRESIDENT NUCLEAR 0PERAT.I0NS U. S. Nuclear Regulatory Commission Serial No.87-212 Attn: Document Control Desk NO/ETS/vlh 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 SPECIFICATIONS CHANGES Pursuant to 10 CFR 50.90, Virginia Electric and Power Company requests an amendment, in the form of changes to the Technical Specifications, to Operating License Nos. DPR-32 and DPR-37 for Surry Power Station Units 1 and 2.

This Technical Specification change request supersedes our previous submittals, dated September 9, 1985 (Serial No. 85-229A) and October 31, 1985 (Serial No. 85-211C) and September 25, 1986 (Serial No.86-509). This change request combines those requests.

We are proposing changes to Section 3.7, Instrumentation Systems, and Section 4.1, Operational Safety Review. The proposed changes to Section 3.7 would reformat and upgrade Table 3.7-1, Reactor Trip Instrumentation Operating Conditions, to more closely conform to Standard Technical Specifications. The proposed changes to Section 4.1 would add a surveillance requirement for the reactor trip system interlocks and modify some of the surveillance requirements for portions of the reactor protection system instrumentation channels in accordance with Standard Technical Specifications and other appropriate source documents. Changes are incorporated to address Items 4.3 and 4.5.3 of Generic Letter 83-28. Other minor changes are also being proposed for this section of the Technical Specifications.

The proposed changes to the Technical Specifications are provided in Attachment 1. A discussion of the proposed changes to the Technical Specifications is provided in Attachment 2. The application fee was previously submitted with our April 12, 1985 Technical Specification change request.

r 8706020023 870522 PDR ADOCK 05000280 P PDR

This request has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff. It has been determined that this change does not pose an unreviewed safety question as defined in 10 CFR 50.59 and does not pose a significant hazards consideration as defined in 10 CFR 50.92.

If you have any questions, or need additional information to process this request, please contact us.

Very truly yours, W. L. Stewart Attachments

1. Proposed Technical Specification Changes for Surry Units 1 and 2
2. Discussion of Proposed Changes cc: Dr. J. Nelson Grace Regional Administrator NRC Region II Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219 Mr. Chandu P. Patel NRC Surry Project Manager PWR Project Directorate No. 2 Division of PWR Licensing-A