ML20154H084

Forwards Safety Insp Rept 50-219/88-11 on 880411-15 & Notice of Violation.Most Weaknesses Identified During Integrated Performance Assessment Team Insp Corrected.Issue of Drywell Occupancy Unresolved

ML20154H084
Person / Time
Site:	Oyster Creek
Issue date:	05/13/1988
From:	Bellamy R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Fitzpatrick E GENERAL PUBLIC UTILITIES CORP.
Shared Package
ML20154H088	List: IR 05000219/1988011 ML20154H084 ML20154H090
References
NUDOCS 8805250222
Download: ML20154H084 (3)

See also: IR 05000219/1988011

Text

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MAY l 31989

Docket No. 50-219

GPU Nuclear Corporation

ATTN: Mr. Eugene E. FitzPatrick

Vice President and Director

Oyster Creek Nuclear Generating Station

P. O. Box 388

Forked River, New Jersey 08731

Gentlemen:

Subject: Inspection No. 50-219/88-11

A routine safety ins)ection of your facility was conducted by Dr. S. Sherbini on

April 11-15, 1988. Tie inspection was devoted mainly to checking the status of

weaknesses identified during the Integrated Performance Assessment Team

inspection (IPAT) conducted at Oyster Creek in 1987 (Inspection Report

50-219/87-24). Also reviewed during this inspection were the corrective actions

connected with a recentiv issued Licensee Event Report and the status of

measures taken to contro'l drywell occupancy during fuel movements.

The findings of this inspection are detailed in the attached report. Most of the

weaknesses identified during IPAT were found to have been corrected. A few items

remain uncorrected, but corrective action on these items was in progress. The

issue of drywell occupancy during fuel movement remains unresolved because of

the unavailability at the time of the inspection of certain information needed

to resolve this matter.

A review of the radiation survey data connected with work in the torus room that

was ongoing during this inspection showed that some of the surveys were done in

a manner that failed to identify the field gradients in areas in which the

workers were working. This is an apparent violation of 10 CFR 20.201

requirements. Although no exposures in excess of the regulatory limits occurred,

the lack of proper radiological surveys created a potential for unmonitored

exposures or exposures in excess of the regulatory limits. Details are provided

in the enclosed Appendix A and ins)ection report. You are required to respond to

the violation in accordance with tie instructions contained in the enclosed

Appendix A.

Although this survey problem was identified by the licensee, a citation could

not be mitigated

because in accordance

the problem with 10

of inadequate CFR Part

surveys 2, Appendix

at Oyster Creek C,is aSection 5(G)

recurring problem )

that was the subject of several NRC citations in the recent past. l

Your cooperation with us is appreciated.

Since6Mhl Signed By:

Wittiam J. Lazarus

Chief l

Ronald R.Radio

Facilities Bellambgical Safety l

and Safeguards Branch  !

Division of Radiation Safety and

Safeguards

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GPU Nuclear Corporation

Enclosures:

1

1. Appendix A, Notice of Violation

2. Inspection Report No. 50-219/88-11

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cc w/encls: l

M. Laggart, BWR Licensing Manager l

Licensing Manager, 0 ster Creek

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Local Docket Room (Room)

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Nuclear Safety Information(LPDRcen er (NSIC)

NRC Resident Inspector

State of New Jersey ,

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GPU Nuclear Corporation

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Region I Docket Room (with concurrences

Management Assistant, DRMA (w/o encis) )

DRP Section Chief

Robert J. Bores, DRSS

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