ML18102A340
| ML18102A340 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/20/1996 |
| From: | Eric Simpson Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N96222, NUDOCS 9608300081 | |
| Download: ML18102A340 (3) | |
Text
Public Service Electric and Gas Company E. C. Simpson Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1700 Senior Vice President - Nuclear Engineering AUG 2 O 1996 LR-N96222 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
REVISION TO NRC NOTICE OF VIOLATION RESPONSE INSPECTION REPORT NOS. 50-272/311/94-32, 50-272/311/95-02, 50-272/311/95-07 AND 50-272/311/95-10 SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Public Service Electric & Gas Company (PSE&G) responded to the subject Notice of Violation (NOV) on November 15, 1995 (LR-N95196).
One example cited by the NRC in the NOV related to a failure to implement effective and timely corrective actions for vibration induced failures associated with Emergency Diesel Generator Jacket Wat~r Tubing.
Corrective actions to address the hardware problem were provided in our response.
Specifically, in Example No. 8, PSE&G stated that:
"Jacket Water Pressure transmitting tubing runs will be redesigned to eliminate the piping nipples and associated piping isolation valves."
The intent of the response was to communicate our commitment to redesign the Jacket Water Pressure transmitting tubing runs to reduce their susceptibility to.vibration induced failures. While redesign to eliminate the nipple is feasible, elimination of the isolation valves is not.
Elimination of the isolation valves would impose a maintenance burden in that the 3bility to test and calibrate the pressure switches would require draining the jacket water system.
As a result, changes to the valve supports and the use of flexible hoses have been incorporated into the redesign.
PSE&G is therefore revising its previous commitment as follows:
Jacket Water Pressure transmitting tubing runs will be redesigned to replace the existing nipple and associated isolation valves with a design that is less susceptible to vibration induced failures."
9608300081 960820 PDR ADOCK 05000272 G
/:i.\\. Printed on
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Recycled Paper
AUG 2 O 1996 Document Control Desk LR-N96222 The planned redesign of the tubing runs will bring the design into compliance with applicable requirements while continuing to satisfy the intent of the commitment to reduce the susceptibility of the design to vibration induced failures.
Should there be any questions regarding this submittal, please do not hesitate to contact us.
95-4933
- Document Control Desk LR-N96222 C
Mr. H. J. Miller, Administrator - Region I
- u. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. Olshan, Licensing Project Manager -
Salem
- u. S. Nuclear Regulatory Commission one White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. c. Marschall (X24)
USNRC Senior Resident Inspector Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 AUG 2 0 1~~s