ML18153C772
| ML18153C772 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/08/1991 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18153C773 | List: |
| References | |
| 91-503, GL-89-19, NUDOCS 9110150292 | |
| Download: ML18153C772 (2) | |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 8, 1991 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 CLARIFICATION OF SURVEILLANCE REQUIREMENT Serial No.
NO/ETS Docket Nos.
License Nos.
TECHNICAL SPECIFICATION CHANGE
- ESF INSTRUMENTATION 91-503 50-280 50-281 DPR-32 DPR-37 In our letter (Serial No.90-195) dated November 8, 1990, we submitted a proposed Technical Specification change that would provide Limiting Conditions for Operation and Action Statements for the ESF and Containment Isolation instruments consistent with WCAP 10271 and your associated SER. This proposed Technical Specification change included several new surveillance requirements for the instruments as well as the associated actuation logic and relays.
The proposed change also added operability and surveillance requirements for Feedwater Isolation/Turbine Trip instruments in accordance with Generic Letter 89-19.
To further define the applicability of the proposed surveillance requirements for the Turbine Trip and Feedwater Isolation actuation logic and actuation relays (Table 4.1, Item 41.b), a note is being included defining applicability. Specifically, the note excludes the actuation relays from monthly surveillance testing because the test cannot be completed without lifting leads and/or defeating both logic trains. Testing of the relays will be performed at each refueling calibration when entire loop testing can be accomplished.
As a clarification to the proposed additional surveillance, this change does not impact the original safety analysis or the significant hazards determination. Therefore, the significant hazards determination submitted in the November 6, 1990, submittal remains valid.
Should you have any further questions, please contact us.
Very tr~IY. yours,
,41Cr 1 \\
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W. L. Stewart Senior Vice President - Nuclear Attachment
- cc:
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219