ML18101A830
| ML18101A830 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/20/1995 |
| From: | Tosch K NEW JERSEY, STATE OF |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 9507240262 | |
| Download: ML18101A830 (2) | |
Text
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.efu 3h~rs.eu-Christine Todd Whitman Governor Department of Environmental Protection Robert C. Shinn, Jr.
Commissioner July 20, 1995 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:
Subject:
License Amendment Application Salem Generating Station Unit Nos. 1 and 2 License Change Request LCR 94-28 Cont.ainment. Pressure/Vacuum Relief Valves Public Service Electric and Gas. Company submitted the subject amendment to the Nuclear Regulatory Commission on April 18, 1995.
The proposed change would delete the quarterly leak rate test for the containment pressure-vacuum relief valves, which is based on replacement of the resilient valve seat material with a hard seat design. The valves would remain in the 10CFR50 Appendix J, Type c leak rate test program.
The New Jersey Department of E~vironmental Protection's Nuclear Engineering Section (NES) has reviewed the request and the supplemental information in accordance with the requirements of 10 CFR 50.91(b) and has the following comments.
In the no significant hazards determination, PSE&G states that "based on the improved. design and operating experience of the replacement valves, augmented quarterly leak rate testing is no longer necessary No operating experience information. is provided or referenced.
This appears to be a key factor in the acceptability of these valves.
Since thes.e valves are normally
- closed, it..wou.ld seem that a potential for corrosion exists between the disks
- which could cause the
- metal disks
- to bond
- together.
Operating experience information and consultation with a valve specialist would help. determine. if this concern is valid. It appears that there mu~t be limitatioris in the use of *metal to metal disks, otherwise all resilient seating surfaces could be replaced.
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9507240262 950720 PDR ADOCK 05000272 P
' **. *ersey is an Equal Opportunity Employer Recycled Paper
We reyiewed the WPPSS information to determine if it justified this cb.,~nge.for PSE&G's containment relief valves.
These valves are containment relief valves, de.signed for air and steam flow.
And there has been a history of seat deterioration that resulted in very frequent testing.
If the solution is to replace the valve than why wasn't it done earlier and why haven't more valves been replaced.
The WPPSS document provides more in~ormation on Type C testing but makes a general statement* about industry experience without offering supporting data, as well.
. If you have any questions, please contact Dennis J. Zannoni at (609) 987-2037 or Rich Pinney at (609) 987-2086.
Sincerely, Kent W. Tosch, Manager Bureau of Nuclear Engineering c:
Distribution Dr. Lipoti, Assistant Director, DEP D. Zannoll;i, Supervisor, DEP D. Chawaga; NRC.Region I State Liaison Officer C. Marshall, NRC Senior Resident Inspector, Salem 1 and 2
- L. Olshan, NRC Project Manager, Salem 1' and 2 F. Thomson, Nuclear Licensing Manager, PSE&G