ML18150A057
| ML18150A057 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/23/1987 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| Shared Package | |
| ML18150A059 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.2, TASK-TM 87-206, NUDOCS 8704290210 | |
| Download: ML18150A057 (2) | |
Text
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10 CFR 50.90 VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L, STEWART VICE PRESIDENT NUCLEAR OPERATIONS April 23, 1987 U. S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D. C.
20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATIONS CHANGE CORE EXIT THERMOCOUPLE ADDITION Serial No.87-206 NOD/JBL:vlh Docket Nos.
50-280 50-281 License Nos. DPR-32 DPR-37 Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests amendments, 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, respectively.
In accordance with your letter, dated December 4,
- 1985, we are submitting this proposed Technical Specification change to include the Core Exit Thermocouple (CET) system in the Accident Monitoring Instrumentation in Tables 3.7-6 and 4.1-2.
This proposed change addresses the CET requirements of NUREG-0737 Item II.F.2, "Instrumentation for Detection of Inadequate Core Cooling."
The CET upgrade was considered complete upon the return to power Unit 2 on December 2, 1986.
As discussed with your staff, submittal proposed Technical Specification was delayed due to our efforts in to the Surry Unit 2 pipe rupture on December 9, 1986.
of Surry of the response Additionally, in our letter dated March 3, 1987 (Serial No.86-801),
"Reactor Coolant Pump Trip Criteria," we indicated the loop RTDs as well as the CETs were an input to the Subcooling Margin Monitor (SMM).
In clarification, the only temperature input to the SMM is the CETs.
The loop RTDs can, however, be used by the operators as a backup indication to monitor RCS subcooling.
This request has been reviewed by the Station Committee and the Safety Evaluation and determined that this request does not involve as defined in 10 CFR 50.59 or a significant in 10 CFR 50.92.
8704,29021 O 870423
~DR ADOCI-( 05000280 PDR Nuclear Control Safety staff.
and Operating It has been any unreviewed safety questions hazards consideration as defined
L We have evaluated this request in accordance 170.12.
A voucher check in the amount application fee.
Very truly yours, W. L. Stewart Attachments
- 1.
Proposed Technical Specification Changes
- 2.
Discussion of Changes
- 3.
Application Fee cc:
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.
Suite 2900 Atlanta, Georgia 30323 Mr. Chandu P. Patel NRC Surry Project Manager PWR Project Directorate No. 2 Division of PWR Licensing-A Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219 e
with the criteria in 10 CFR of
$150.00 is enclosed as an