ML18082A147
| ML18082A147 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/03/1980 |
| From: | Mittl R Public Service Enterprise Group |
| To: | Parr O Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18082A148 | List: |
| References | |
| NUDOCS 8004110474 | |
| Download: ML18082A147 (1) | |
Text
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Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201/430-7000 April 3; 1980 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Attn:
Mr. Olan D. Parr, Chief Light Water Reactors Branch 3 Division of Project Management Gentlemen:
RHR SYSTEM NPSH AND RWST CAPACITY NO. 2 UNIT SALEM NUCLEAR GENERATING STATION DOCKET NO. 50-311 In response to concerns raised at a meeting held with representatives of your staff on February 25; 1980, PSE&G hereby transmits the results of a test performed to verify that there is no vortex formation in the RWST (Enclosure 1).
Additionally, Enclosure 2 provides sketches of additional modifications to the containment sump screen.
These modifications are being made at your request and will be completed prior to exceeding 5% power.
Our letter dated October 4, 1979; discussed NPSH testing of the RHR System and provided the results of testing the No. 21 RHR pump.
The No. 22 RHR pump has also been tested.
Operating flow conditions were as described in the referenced letter.
This test showed that with the throttle valve full open, the maximum flow achieved was 4300 gpm.
This flow is acceptable, since the pump has adequate -NPSH for flows up to 4800 gpm, as indicated in our letter dated May 17, 1979.
Please note that the correct orifice diameter is 5.5 inches for both the upstream and downstream flow elements associated with the RHR heat exchanger.
These diameters were incorrect-ly reported in our letter of October 4, 1979.
Should you have any questions, do not hesitate to contact us.
fj_i/J;-rs, R. L. Mittl General Manager -
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