ML18153B667

Application for Amends to Licenses DPR-32 & DPR-37,changing Tech Specs by Raising Nub Circulating & Svc Water Intake Canal Level from 18 to 23 Ft & Providing Operability Requirements for Canal Level Actuation Sys

ML18153B667
Person / Time
Site:	Surry
Issue date:	03/27/1989
From:	Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18151A691	List: ML18151A690 ML18153B667
References
88-796, NUDOCS 8904030350
Download: ML18153B667 (2)

Text

__ ,_,,.

• e VIRGINIA.

ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W, R. CARTWRIGHT VICE PRESIDENT NUCLEAR March 27, 1989 ( U. S. Nuclear Regulatory Commission Attention:

Document Control Desk Washington, DC 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 Serial No.88-796 NO/ETS: Docket Nos. 50-280 50-281 License Nos. DPR-32 / DPR-37

SUMMARY

REPORTS AND PROPOSED TECHNICAL SPECIFICATION CHANGES CIRCULATING WATER, SERVICE WATER AND RELATED SYSTEMS In our letter (Serial No.88-689) of October 19, 1988, and during a meeting on October 26, 1988, several items were identified which required appropriate corrective action prior to restart of the Surry units. This letter provides summary reports which discuss the Canal Inventory issues, Component Cooling heat exchanger operability, and the Emergency Service Water Pump modifications.

As part of our corrective actions, pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests an amendment in the form of a change to the Technical Specifications to Operating Licenses DPR-32 and DPR-37 for Surry Power Station Units 1&2, respectively.

This change, provided in Attachment 1, will: 1) raise the minimum Circulating and Service Water Intake Canal level from eighteen feet to twenty-three feet, 2) increase the requirement from two to three Emergency Service Water pumps to be operable with provision for limited duration maintenance outages, and 3) provide operability and surveillance requirements safety-related canal level actuation system. for the new The summary Inspection.

consistency design basis Cooling heat reports address issues raised in the Safety System Functional The proposed Technical Specification changes will ensure between the operating requirements and the reconstituted plant in the area of Intake Canal inventory management and Component exchanger operability.

These proposed changes have been reviewed by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control staff. It has been 8904030350 890327 PDR ADOCK 05000280 p PNU

• determined that the changes constitute an unreviewed safety question as defined in lOCFRS0.59, but do not involve a significant hazards consideration as defined in 10 CFR 50.92. The determination that these changes constitute an unreviewed safety question is largely due to the reconstituted design basis which represents a substantial change from the design specified in the UFSAR. Our basis for determining that no significant hazards consideration exists is contained in Attachment 1 and is supplemented by the report provided in Attachment

2. This letter also provides the final summary report for the Emergency Service Water pumps. This report is provided in Attachment

3. Very truly yours, Attachments

1. Proposed Technical Specifications Change 2. Evaluation of Surry Intake Canal Inventory and Component Cooling Heat Exchanger Operability

3. Evaluation of Emergency Service Water Pump Modifications cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W. Suite 2900 Atlanta, .GA 30322 Mr. W. E. Holland NRG Senior Resident Inspector Surry Power Station Department of Health 109 Governor Street Richmond, VA 23219