ML18153B570
| ML18153B570 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 01/09/1989 |
| From: | Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 88-725, NUDOCS 8901170227 | |
| Download: ML18153B570 (2) | |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. *R. CARTWRIGHT VXCE PRESIDENT NUCLEAR January 9, 1989 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 INSERVICE INSPECTION PROGRAM Serial No.
PES/ISI/JBL:r2 Docket Nos.
License Nos.
RELIEF REQUEST FROM ASME SECTION XI HYDROSTATIC PRESSURE TESTS88-725 50-280 50-281 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 two ASME Section XI Class 2 valves.
The following basis is provided.
During the present Surry Unit 1 forced outage and the Surry Unit 2 refueling outage, a 1-1/2 inch manual isolation valve, 1-MS-74, a 2-1/2 inch manual isolation valve, 1-BD-24, and a 2 inch manual isolation valve, 2-GN-3, were replaced because of valve internal isolation problems.
Replacement of the valves was considered the most appropriate resolution to the problem.
Paragraph 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 on Unit I (1-RC-E-lA), the "C" steam generator on Unit I (1-RC-E-IC), and the "C" steam generator on Unit 2 (2-RC-E-IC) within the hydrostatic pressure test boundaries.
Because hydrostatic pressure testing of steam generators is difficult to perform and sometimes detrimental to steam generator tube integrity, we are requesting alternate examinations for the two small line repairs noted above.
Hydrostatic pressure tests, which include steam generators, are scheduled to be performed this outage on the 8 inch feedwater lines to the "B" steam generator in Unit I (1-RC-E-IB), and the "A" and "B" steam generators in Unit 2 (2-RC-E-lA & IB) due to feedwater line replacements.
No hydrostatic pressure testing of the Unit I "A" or "C" steam generators or Unit 2 "C" steam generator would be otherwise needed except as required for the weld repairs associated with the two manual valves noted above.
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,,,._.I It is proposed that a surface examination (PT) and a system pressure test be performed on the welds and accepted as an alternative to the Code required hydrostatic pressure test for the replacement welding associated with valves l-MS-74, l-BD-24, and 2-GN-3.
This alternate approach is similar to a previous relief request dated February 13, 1987 and granted June 17, 1988.
Add it i ona 1 assurance of the integrity of these we 1 ds wil 1 be provided by a visual check for leakage during startup as part of high energy line walkdowns.
We believe the proposed alternative examinations to provide the necessary assurance of weld integrity intended by the Code.
If you have any questions regarding this request, please do not hesitate to contact us.
In accordance with 10 CFR 170, an application fee of $150 is enclosed.
Enclosure 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. B. C. Buckley NRC Project Manager - Surry Directorate II-2 Division of Reactor Projects I/II