ML20101C546
| ML20101C546 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 03/13/1996 |
| From: | Storz L Public Service Enterprise Group |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LR-N96067, NUDOCS 9603190011 | |
| Download: ML20101C546 (3) | |
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o' Pubhc Service Electnc and Gas Company Loul) F. Storz Public Service Electric and Gas @fpaly3 leox 23e. Hancocks Bridge, NJ 08038 609-339-5700 Senor Vice President Nuclear Operatore United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 l
l Gentlemen:
HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 l
DOCKET NO. 50-354 STATUS OF CORRECTIVE ACTIONS - FOR VIOIATION 354/95-10-03 On August 11, 1995, NRC Inspection Report 354/95-10 was issued.
This inspection report included a Notice of Violation for failure to meet the requirements of 10CFR50, Appendix B, Criterion XVI, l
Corrective Action.
Specifically, Public Service Electric & Gas Company (PSE&G) was cited for inadequately determining the cause of Hiller-actuated valve failures and for implementing ineffective corrective actions to preclude recurrence of these l
failures.
On September 11, 1995, via letter LR-N95139, PSE&G responded to the Notice of Violation.
In that response, PSE&G described the results of its root cause analysis.
As a result of that l
analysis, PSE&G committed to implementing a number of corrective l
actions for the actuator and packing.
In letter LR-N95255, dated l
12/28/95, PSE&G committed to completing these corrective actions prior to the end of Refueling Outage Number 6 (RFO6).
In baseline data collected during implementation of the corrective actions during RFO6, some of the valves that had been modified were exhibiting high measured opening forces.
As a l
result, the valve manufacturer (Anchor-Darling) was consulted and provided additional recommended actions.
Although performance of the valves had significantly improved, PSE&G has concluded that the corrective actions described in the violation response may j
not have been sufficient to prevent recurrence of random valve failures.
A team was formed to continue to investigate the cause(s) of the high measured forces and determine additional corrective actions to assure reliable valve performance.
1 This team has concluded that the combination of a Hiller actuator and six inch Anchor-Darling flexible wedge gate valve is not the optimal application for the installed service.
This is due to r
9603190011 960313 PDR ADOCK 05000354
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. MAR 131996 '
Document Control Desk LR-N96067 l
the relatively large spring forces needed to consistently assure desired performance.
As an immediate corrective action, PSE&G
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L has determined that selected six inch valves will remain in the l
open position (to perform its safety function) and has completed j
a 10CFR50.59 safety evaluation for this plant configuration change.
These six inch valves will be administratively controlled until permanent corrective actions are implemented.
1 The three and four inch Hiller-actuated valves in the Safety l
Auxiliaries Cooling System will not be changed since their performance during periodic testing has been satisfactory.
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Conclusion:==
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Previous root cause analysis of the Hiller-actuated valve failures focused on the failure modes associated with the valve actuator and the valve packing.
It is believed that the root cause and corrective actions performed on that portion of the
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assemblies have been effective in precluding failures associated j
with the actuator (as demonstrated by the satisfactory j
performance of the three and four inch valves).
However, recent testing on the six inch valves indicated less than optimum performance.
Therefore, one of the two redundant Hiller-actuated valves for the diesel generator room coolers will remain in the open position, to ensure performance of its safety function, until permanent corrective actions are in place.
Should you have any questions or comments on this transmittal, do l
not hesitate to contact us.
Sincerely, b
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i MAR 131996 Document Control Desk LR-N96067 C:
Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission l
475 Allendale Road l
King of Prussia, PA-19406 l
l Mr. D. Jaffe, Licensing Project Manager j
U. S. Nuclear Regulatory Commission One White Flint North I
11555 Rockville Pike Mail Stop 14E21 l
Rockville, MD 20852 Mr. R. Summers (SO9)
USNRC Senior Resident Inspector l
Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering j
33 Arctic Parkway l
CN 415 Trenton, NJ 08625 l
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