ML20216E476
| ML20216E476 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/29/1997 |
| From: | Roche M GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 50-219-96-12, 6730-97-2191, NUDOCS 9709100202 | |
| Download: ML20216E476 (2) | |
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GPU Nuclear. inc.
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U S Route 79 South NUCLEAR Forud Rwer. NJ 08D1-0388 Tel 609 944300 (6091971 4814 August 29, 1997 6730 97 2191 l
l U.S. Nuclear Regulatory Commission Attn: DocumentControlDesk Washington,DC 20555 Gentlemen:
i
Subject:
Oyster Creek Nuclear Generating Station (OCNGS)
Docket No. 50 219 Facility Operating License No. DPR 16 Response to inspection Report 50-219/96-12 Notice of Violation NRC Inspection Report 50 219/96-12, dated February 14,1997, cited a Notice of Violation (NOV) of 10 CFR 50.59 regarding a change to the shutdown cooling system configuration. This inspection report noted that GPU Nuclear was not required to respond to the specific NOV because our response to the similar recent 10 CFR 50.59 violations documented in inspection Report 50-219/96-09 and 50/219/96-11 should address this violation.
This letter provides additional information regarding actions taken and identified corrective actions related to these recent 10 CFR 50.59 violations.
GPU Nuclear letter to the NRC dated January 24,1997 (6730 97-2030) provided the required response to NRC Inspection Report 50 219/96-09 and 50-219/96-11 Notices of Violation regarding 10 CFR 50.59. In addition to correcting the specific safety determinations, identified corrective steps taken included: (1) enhancing the safety review training program to emphasize the accuracy of safety determination question conclusions and to discuss tools available to facilitate licensing basis review and, (2) issuing a " Safety Review Newsletter" reinforcing safety review performance expectations. These steps have been completed as committed in GPU Nuclear letter to the NRC dated January 24,1997 (6730-97-2030).
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9709100202 970829 0
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,67304)7 2191 Page 2'of 2 Additionally, as a result of,these violations and the subsequent siolation identified in NRC Inspection Report 50-219/96-12, GPU Nuclear conducted a self assessment of the OCNGS safety review process implementation This self a:sessment was focused on the Safety Detennination element of the GPU Nuclear Safety Resiew Process A number of strengths, as well as process issues, were identified The self assessment team identifini twenty three (23) recommendations addressing Safety Review Process programmatic aspects. Safety Resiew Process Training Program improvements, and enhancements to facilitate licensing basis resiev.s. GPU Nuclear believes that these recommendations will enhance implementation of the Safety 'teview Process, help prevent recurrence of similar violations, and proside a beneficial etreet on plant safety. A formal plan and schedule for implementation of the self.
assessment recommendations is being developed and the actions are being identified in a formal conective action process if any additional infonnation is needed, please contact Mr. David J. Distel, Regulatory AITairs, at (201)
?16-7>55.
Sincerely, h
Michael 11. Roche Vice President and Director, Oyster Creek MillVDjD Cc:
Administrator, Region i NRC Project Manager NRC Senior Resident inspector 1