ML18139C152
| ML18139C152 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/09/1982 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Varga S Office of Nuclear Reactor Regulation |
| References | |
| 680, NUDOCS 8212130327 | |
| Download: ML18139C152 (2) | |
Text
{{#Wiki_filter:~- _ e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS December 9, 1982 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn: Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen: Serial No. 680 NO/RT/WDC:acm Docket No. 50-281 License No. DPR-37 Surry Power Station Unit 2 will be performing a repair within a system boundary designated as ASME Class 2 during the upcoming maintenance outage scheduled to begin December 7. Pursuant to 10 CFR 50.55a paragraph g(5), relief is requested from certain post repair test requirements delineated in ASME Section XI. The following basis is provided. This relief is identical in nature to a previous relief request for replacement of a comparable valve on Surry Power Station Unit 1 (Serial No.
- 530, dated 9/15/82).
A relief was granted for this replacement (dated 10/1/82). Specifically it is planned to replace three 1 1/2 inch drain valves (2-MS-106, 2-MS-74, and 2-MS-268), which are just downstream of the main steam trip valves (drawing attached). The governing code ASME XI 77W78 requires a hydrostatic test for such a repair/replacement. As evidenced by the attached drawing this would require a hydrostatic test of the entire steam generator and a considerable portion of large main steam piping. Thus a hydrostatic test would be especially difficult and concomitantly impractical. Note also that ASME Section XI exempts 1 inch nominal and smaller from hydrostatic pressure tests. Alternate testing proposed supplemented by an inservice normal operating pressure. is liquid penetrant and visual examination leakage test at hot shutdown which is 125% of We contend that adequate basis for relief is presented above and that the proposed alternate testing provide adequate insurance of the integrity of the six 1 1/2" welds affected. cc:, Mr. James P. O'Reilly, Director Office of Inspection and Enforcement Region II Very truly yours, 8212130327 821209 PDR ADOCK 05000281 P PDR
J \\ \\ { \\ \\ i I I I i I I '1 li I I I I j I I I l I I I --{-- I I ! I ...:- E.-.'v\\ (a.. ~E."ATO*":: l T f I
- i.*IIK" £,A I
!) 1_~.,' I ~ .. ~ ,© ~ ,o*. 5"P *1::: !.0 i.~ .~. .,0 1~~~ TURf TR.IP \\}}