ML18152A918
| ML18152A918 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/26/1988 |
| From: | Cruden D VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 88-297, NUDOCS 8806070234 | |
| Download: ML18152A918 (2) | |
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D.S.CRUDEN VICE PRESIDENT-NUCLEAR VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 May 26, 1988 United States Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D.C.
20555 Gentlemen:
'VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS I AND 2 CONTAINMENT INTEGRATED LEAKAGE RATE TESTING Serial No.
NO/ETS:vlh Docket Nos.
License Nos.88-297 R2 50-280 50-281 DPR-32 DPR-37 In a telephone conversation on May 13, 1988, with Mr. Chandu Patel of your staff and Mr. George Pannell of my staff, the status of containment integrated leakage rate testing (Type A) with the containment 1 iner weld leak-chase channel plugs installed and our submittal of February 8, 1988 were discussed.
This letter documents our telephone conversation and details our plans for resolution of the l~ak-chase channel issues.
Both Surry Units are scheduled to perform a Type A test during the 1988 refue 1 i ng outages, Un it 1 is current 1 y in a refue 1 i ng outage with a Type A test scheduled near term, whereas Unit 2 is scheduled for 1 ater this year.
Based on our comparison of the Surry and Beaver Va 11 ey containments, which established the similarities in construction techniques and materials, we plan to perform the Unit 1 and 2 Type A tests with the 1 eak-chase channel plugs installed.
We are concurrently performing site specific analyses to establish that the leak-chase channels and their welds are completely compatible with the liner and capable of withstanding any normal test or upset load condition within the design basis of the containment.
The report wi 11 inc 1 ude a description of the 1 i ner and test channe 1 s with respect to configuration, materials, fabrication, tests and inspections.
The analysis will concentrate on the structural behavior and integrity of the liner and channels at design basis conditions.
This analysis will be completed and forwarded for your review.
It is anticipated this submittal will be made by July 31, 1988.
Should you have any questions, please contact us.
Very truly yours, 8806070234 880526 f
PDR ADOCI< 05000280 *
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cc:
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Mr. Chandu P. Patel NRC Surry Project Manager Project Directorate II-2 Division of Reactor Projects - I/II e