ML20129D084
| ML20129D084 | |
| Person / Time | |
|---|---|
| Site: | Hope Creek  |
| Issue date: | 10/18/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20129D067 | List: |
| References | |
| 50-354-96-07, 50-354-96-7, NUDOCS 9610240193 | |
| Download: ML20129D084 (1) | |
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i Public Servica Electric and Gas Company Docket No: 50-354 Hope Creek Generating Station License No: NPF-57 During an NRC inspection conducted on August 4,1996 to September 21,1996, violations of NRC requirements were identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violations are listed below:
A.
10 CFR 50.59 requires in part, that the holder of a license authorizing operation of a production f acility may make changes in the facility as described in the safety analysis report unless the proposed change involves a change in the technical specifications or an unreviewed safety question.
I Contrary to the above, on September 21,1996, two examples of changes implemented by the licensee were identified that involved failures to appropriately l
evaluate whether the proposed changes involved changes to technical specifications or unreviewed safety questions, including t
(i)
On August 13,1996, the licensee " blocked" open a turbine auxiliaries cooling system supply isolation valve (1EGHV-2522E) described by the i
safety analysis report to automatically close in response to system low pressure signals.
i (ii)
On September-10,1996, the licensee placed non-safety related closed circuit
)
television camera cables over and in close proximity to safety related cable trays and conduit.
l This is a Severity Level IV violation (Supplement 1).
)
B.
Hope Creek Technical Specification 6.5.2.4.2.a requires in part, that the Offsite Safety Review Committee review safety evaluations completed under the provision of 10 CFR 50.59 to verify that completed actions did not constitute an unreviewed
' l safety question.
I Contrary to the above, on August 20,1996,it was determined that the Hope Creek Offsite Safety Review Committed failed to review the safety evaluations associated with the following activities:
(i)
Temporary Modifications #95-060 (Service Water Discharge) and #95-065 Reactor Vessel Level - Shutdown);
(ii)
Design Change Package 4EX-3510 (Cooling Tower); and, (iii)
Hope Creek Emergency Classification Guide attachments 2,3,4, and 8.
This is a Level IV violation (Supplement l).
Dated at King of Prussia, Pennsylvania this 18th day of October,1996 9610240193 961018 PDR ADOCK 05000354 G
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