ML18082B331
| ML18082B331 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/29/1980 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Miraglia F Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8010160486 | |
| Download: ML18082B331 (2) | |
Text
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PS~G Public Service Electric and Gas Company 80 Park Plaza Newark, N.J. 07101 Phone 201/430-7000 September 29, 1980 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Gentlemen:
Mr. Frank J. Miraglia, Chief Licensing Branch 3 Division of Licensing RCS PRESSURE ISOLATION VALVES LEAK RATE TESTING NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 PSE&G hereby submits the following information regarding leak rate testing of RCS pressure isolation valves.
Interim Program The Salem 2 pressure isolation valves will be tested using the existing test piping.
The leak rate will be measured by using the existing system flow meter or by using actual measurements.
Valves which separate the RCS from a low pressure system will be tested at normal RCS operating pressure and temperature.
Valves which are in series and downstream of these valves will be pressurized to greater than 1000 psig and tested.
Where multiple valves are cross-connected to one test connection, a total leak rate will be determined.
If the leakage exceeds 1 gpm (or in limited cases where four (4) valves are in a parallel configuration where leakage is not to exceed 4 gpm), then corrective action will be taken.
Long Term Program The long term program will require additional system test connections, flow meter calibration, and final leak rate criteria.
Additional system test connections will be engi-neered and installed before and during the first refueling outage.
The installed flow meter will be evaluated for reliability and modified as required.
A reasonable leakage acceptance criteria will be developed.
The leak rate test-ing program will be conducted, using these modifications, prior to startup from the first refueling outage.
The Energy People 801016 1 0'/lr~
95*0942
Dir. of Nuc. Reactor Reg. 9/29/80 Valve Classification Pressure isolation valves for the Safety Injection, Residual Heat Removal, and Boron Injection Systems will be categor-ized as Category A or AC, as discussed with Mr. Cappucci of your staff.
Should you have any questions in this regard, do not hesi-tate to contact us.
CC:
Mr. Leif Norrholm Salem Resident Inspector BT04/l 1/2 Very truly r-1¥1.
R. L. Mittl General Manager -
Licensing and Environment Engineering and Construction