ML20246J596
| ML20246J596 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 08/24/1989 |
| From: | Wenzinger E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Fitzpatrick E GENERAL PUBLIC UTILITIES CORP. |
| Shared Package | |
| ML20246J601 | List: |
| References | |
| NUDOCS 8909050215 | |
| Download: ML20246J596 (2) | |
See also: IR 05000219/1989016
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AUG 2 41939
Docket'No. 50-219
License No. 50-DPR-16
'GPU Nuclear Corporation
ATTN:
Mr.. Eugene.E. Fitzpatrick
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Vice. President and Director
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Oyster Creek Nuclear Generating Station
P.O. Box.388
Forked River, New Jersey 08731
Gentlemen:
=
Subject: ~ Inspection Report No. 50-219/89-16
,
This letter refers' to the routine safety inspection conducted by M. Banerjee.
S. Chaudhary, E. Collins, H.. Gregg and D. Lew, for the period July 2,1989
through July 29, 1989, at the Oyster Creek Nuclear Generating Station. The
inspection, consisting of docu.nent reviews, personnel interviews, and
observations of activities, is documented in the enclosed inspection report.
.The findings were discussed with you and members of your staff after the
inspection.
Paragraph 4.0 of the enclosed report discusses an event where your
identification and correction of deficient conditions were inadequate.
In this
. event, the evaluation of high canal water temperature on plant operations was
.not formally reviewed or approved, and a written safety evaluation was not
performed to evaluate the changes in containment response as presented in the
Safety Analysis Report (FSAR-Update).
the basis for the containment response curves in the FSAR-Update.A contributing
Additionally,
corporate procedures do not address the evaluation of changes in assumptions
used in th analysis which form the licensing basis of the plant. These
factors resulted in the plant being operated in an unanalyzed condition.
Your
attention is required to ensure engineering evaluations of potential safety
problems are performed.
Two events discussed in this report are not in full compliance with NRC
requirements.
These are set forth in the Notices of Violation enclosed as
Appendix A.
The violations have been categorized by severity level in
accordance with the " General Statement of Policy and Procedure for NRC
Enforcement Actions," 10 CFR Part 2, Appendix C (Enforcement Policy).
You are
required to respond to this letter following the instructic,ns in Appendix A.
. In your response to Violation A of Appendix A, include your proposed corrective
actions to ensure that changes in the analysis which form the licensing basis
for your plant are identifiec and adequately evaluated.
[PI
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0FFICIAL RECORD COPY
IR OC 89-16 8/11/89 - 0001.0.0
08/24/89
6909050215 999924
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ADOCK 05000219
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GPU Nuclear Corporation
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SVG 2 41989
Your cooperation with us in these matters is appreciated.
Sincerely,
E. Wenzinger,' Chief
Projects Branch No. 4
Division of Reactor Projects
Cnclosures:
1.
Appendix A, Notice of Violation
2.
NRC Region I Report No. 50-219/89-16
cc w/encis:
M. Laggart, BWR Licensino Manager
,
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Public Document' Room (PDR)
local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector
State of New Jersey
bec w/ enc 15:
Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o enc 1)
Section Chief, DRP
A. Dromerick, Project Manager, NRR
J. Dyer., EDO
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08/17/89
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