ML20129D084

Notice of Violation from Insp on 960804-0921.Violation Noted:Changes Implemented by Licensee Identified That Involved Failures to Appropriately Evaluate Proposed Changes Involved Change in TS or Unreviewed Safety Questions

ML20129D084
Person / Time
Site:	Hope Creek
Issue date:	10/18/1996
From:	NRC (Affiliation Not Assigned)
To:
Shared Package
ML20129D067	List: ML20129D061 ML20129D084 ML20129D089
References
50-354-96-07, 50-354-96-7, NUDOCS 9610240193
Download: ML20129D084 (1)

Text

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o NOTICE OF VIOLATION r 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). )

l B. Hope Creek Technical Specification 6.5.2.4.2.a requires in part, that the Offsite i Safety Review Committee review safety evaluations completed under the provision I 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 PDR &

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