ML18151A036
| ML18151A036 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 08/31/1987 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 87-223A, NUDOCS 8709040385 | |
| Download: ML18151A036 (2) | |
Text
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e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS August 31, 1987 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D. C.
20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 REACTOR VESSEL MATERIALS SURVEILLANCE PROGRAM Serial No.
E&C/DMB:vlh Docket No.
License No.
87-223A 50-280 DPR-32 In a letter dated May 22, 1987 (Serial No.87-223), Virginia Electric and Power Company committed to submit by August 31,
- 1987, applicable Technical Specification changes associated with the recent Surry Unit 1 reactor vessel capsule analysis.
Since the Unit 2 capsule has been analyzed and its associated report is nearly complete, it is considered to be reasonable to delay the Technical Specification submittal for Unit 1 until December 15,1987, when Unit 2 can concurrently be addressed.
Since Surry has common Technical Specifications, a combined submittal would facilitate processing by minimizing the need for supplemental unit specific text.
Both units have accumulated less than nine (9) EFPY of ope.ration.
In con-trast, the heatup and cooldown curve Technical Specification is valid through eleven (11)
EFPY.
A projected fluence at the 1/4T location of 1.323 X 1019 2
n/cm was used to determine transition temperature for the current heatup and cooldown curve for both units.
The accumulated fluence through the end of the last complete fuel cycle for Unit 1 was 0.6 X 1018 n/cm2 at the 1/4T location based on plant specific power distributions.
The 1/4T fluence is now not projected to reach the 1.323 X 1019 n/cm2 fluence limit until 18.9 EFPY of operation.
- Thus, based on actual fluence, the current curves would remain acceptable for continued use significantly beyond when revised curves are proposed to be submitted in December.
The existing heatup and cooldown curves were generated based on the initial issue of Standard Review Plan, Section 5.3.2.
The proposed curves will be generated utilizing the methodology of Revision 1 to Standard Review Plan, Section 5.3.2.
In the interim, additional operational restrictions resulting from using the newer methodology will conservatively be addressed by administrative control for Unit 1.
Corresponding relaxations resulting from the newer methodology will not be taken until after Technical Specifications approval.
Delay in submitting proposed Technical Specifications for Unit 1
until December 15, 1987, poses no significant safety concern.
Accordingly, we plan on submitting the Unit 2 capsule report and associated Technical Specifications changes for both Unit 1 and Unit 2 by December 15, 1987.
Based on a telephone conversation between Mr. Chandu Patel of the NRC and Mr. D. A. Sommers of my staff, we understand that this approach is considered acceptable.
Very truly yours, W. L. Stewart cc:
U. s. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, GA 30323 Mr. Chandu P. Patel NRC Surry Project Manager Directorate 11-2 Division of Reactor Projects I/II Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station