ML20154H084
| ML20154H084 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/13/1988 |
| From: | Ronald Bellamy NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Fitzpatrick E GENERAL PUBLIC UTILITIES CORP. |
| Shared Package | |
| ML20154H088 | List: |
| References | |
| NUDOCS 8805250222 | |
| Download: ML20154H084 (3) | |
See also: IR 05000219/1988011
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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 in accordance with 10 CFR Part 2, Appendix C, Section 5(G) blem
because the problem of inadequate surveys at Oyster Creek is a recurring pro
that was the subject of several NRC citations in the recent past.
Your cooperation with us is appreciated.
Since6Mhl Signed By:
Wittiam J. Lazarus
Chief
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Ronald R. Bellambgical Safety
Facilities Radio
and Safeguards Branch
Division of Radiation Safety and
Safeguards
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Enclosures:
1.
Appendix A, Notice of Violation
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2.
Inspection Report No. 50-219/88-11
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M. Laggart, BWR Licensing Manager
Licensing Manager, 0 ster Creek
Public Docket Room (Room)
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Local Public Docket
NRC Resident Inspector
State of New Jersey
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