ML18149A537
| ML18149A537 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/13/1987 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 87-056, 87-56, NUDOCS 8702250534 | |
| Download: ML18149A537 (2) | |
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10 CFR 50.55a VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS February 13, 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 RELIEF REQUEST FROM ASME SECTION XI HYDROSTATIC TESTS Serial No.87-056 NO/ISI/vlh Docket Nos.
50-280 50-281 License Nos. DPR-32 DPR-37 Pursuant to 10 CFR 50.55a paragraph g(5), relief is requested from certain post replacement test requirements identified in ASME Section XI, 1980 Edition, Winter 1980 Addenda for certain ASME Class 2 valve replacements.
The following bases are provided.
From October 4 through December 2, 1986 Surry Unit 2 was shutdown for a
refueling outage.
During that outage, a
4 inch manual isolation valve, 2-MS-86, was replaced because of valve internal isolation problems.
This valve is used to isolate the "A" steam generator PORV for maintenance.
Replacement of the valve was considered the most appropriate resolution to the internal isolation problem.
IWA-5214 of ASME Section XI requires, following replacement welding, that a hydrostatic test (IWC-5222) be performed on the affected area.
Because no intermediate isolation exists, this test would place the "A" steam generator (2-RC-E-lA) within the hydrostatic test boundary.
Hydrostatic tests which include steam generators are extremely difficult and deemed impractical when compared to other possible alternatives.
It is proposed that the volumetric examination (RT) and the surface examination (PT) performed on the welds be accepted as an alternative to the Code required hydrostatic test.
This approach is similar to a previous relief request dated April 12, 1984 and approved May 17, 1984.
Additional assurance in the integrity of these welds can be provided because there was no leakage detected at startup nor during normal operations as part of the high energy line walkdowns.
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1 Surry Unit 1 is currently involved in a maintenance outage for secondary piping repair.
A 2 inch steam generator nitrogen isolation valve, l-GN-3, and a 1-1/2 inch main steam drain isolation valve, l-MS-80, were replaced during this outage because of excessive body-to-bonnet steam leaks.
Replacement of these valves offers the most economical solution in the harsh (main steam) environment.
The code required hydrostatic test (IWC-5222) would place the "A" and "C" steam generators (1-RC-E-lA and 1-RC-E-lC) within the test boundary.
As previously discussed, alternative examinations are preferred.
Since the socket welds preclude an adequate RT, it is requested that a surface examination (PT) and a visual examination (VT-2) performed during a
system functional test (IWC-5221) be accepted as a substitute.
This is similar to a previous relief request dated February 1, 1985 and approved April 11, 1985.
The proposed alternative examinations provide the necessary inspection and integrity assurance intended by the code.
Acceptance of this request would be consistent with previous requests concerning small steam generator isolation valves.
In accordance with 10 CFR 170, an application fee of $150 is enclosed.
Very truly yours,
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Attachments cc:
U. S. Nuclear Regulatory Commission 101 Marietta Street, N. W.
Suite 2900 Atlanta, GA 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Mr. Chandu P. Patel NRC Surry Project Manager PWR Project Directorate No. 2 Division of PWR Licensing-A