ML20235H799
| ML20235H799 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/17/1989 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | Fitzpatrick E GENERAL PUBLIC UTILITIES CORP. |
| Shared Package | |
| ML20235H802 | List: |
| References | |
| NUDOCS 8902240052 | |
| Download: ML20235H799 (5) | |
See also: IR 05000219/1988202
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555
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February 17, 1989
' Dock'et No. 50-219
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Mr. E. E. Fitzpatrick
Vice President and Director
Oyster Creek Nuclear Generating Station
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P.O. Box 3E8
Forked River, New Jersey 08731
Dear Mr. Fitzpatrick:
SUBJECT: SAFETY SYSTEM OUTAGE H0DIFICATION INSPECTION (DESIGN) 50-219/88202
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This letter conveys the results and conclusions of the design portion of the
Safety System Outage Modification Inspection (SSOMI) of the Oyster Creek-
Nuclear Generating Station conducted by the NRC's Office of Nuclear Reactor
Regulation. The inspection team was composed of NRC personnel and consul-
tants and was conducted at your engineering offices in Parsippany,
New Jersey,-and at the Oyster Creek site during the periods October 17-21 and
' October 31 - November 4, 1988.
The purpose of the design portion of the SSOMI.was to examine, on a sampling
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basis, the detailed design and engineering which was required to support
modifications implemented during the outage.
In addition to the design portion
of the SSOMI, this office has also conducted inspections on installation and
test activities during the outage. A separate report will be published
detailing that phase of the SSOMI.
The report is organized to present the findings in three formats. Section
1.3 provides an overview of the team's activities and sumarizes major findings
by discipline.
Sections 2 and 3 sumarize the effectiveness of your design
effort in terms of strengths and weaknesses. The items of concern identified
by the team during the inspection have been classified as deficiencies and
are referenced throughout the report and presented in detail in Appendix C.
By separate correspondence dated November 16, 1988 you were advised of five
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deficiencies considered by the team to have sufficient safety significance to
justify their classification as items requiring resolution prior to restart
from the current refueling outage. Regular communications between our staffs
indicate that corrective action to resolve these deficiencies continues.
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Of particular concern to the team were findings related to control room
heating, ventilation,andairconditioning(HVAC),andtothefullyloaded
condition of the emergency diesel generator (EDG) buses. The HVAC issue
encompasses deficiencies related to weak controls over the design process,
questionable design input values, undocumented assun.ptions used in calcula-
tions yielding conflicting results, and actual r rformance of the system
during recent special tests which fell signific Aly short of design perfor-
mance. Appropriate corrective action for the HA issue should include a
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8902'40052 890217
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ADOCK 05000219
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Mr. E. E. Fitzpatrick
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February 17, 1989
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comprehensive review that resolves conflicts in design studies, ensures
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sufficient actual ventilation flow to pemit habitability and prevent
equipment failure under postulated accident conditions, and satisfies the
requirements of NUREG-0737.
The team's concerns with the EDG issue focus on the heavily loaded emergency
buses. The combined effect of fully loaded buses.with little margin, auto-
matica11y started and sequenced loads, random loads, and inadequate operator
guidance creates the possibility of an overloaded EDG during.a postulated
accident. The procedural guidance you are now preparing for manual loading
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and unloading of the EDG is expected to partially alleviate the concern by
providing direction to operators. However, the team concluded that your
past performance in monitoring and controlling load growth on the EDG buses
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has not been consistent with conservative facility operation, and warrants
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increased managerial attention.
The team identified several programmatic strengths which contribute to the
effectiveness of your design effort. Safety evaluations were generally
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comprehensive and well documented, as were the Modification Design
Descriptions reviewed during the inspection. The reviews indicated
that you have generally been successful in controlling design interfaces,
and many modification packages reviewed during the ir.spection were deter-
mined to be free of apparent deficiencies. Your initiatives to conduct
Safety System Functional Inspections and develop a configuration management
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program are considered positive steps in effective management of the design
process.
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The NRC Region I staff will continue to monitor your corrective actions to
determine that adequate corrective resolution of the identified concerns is
achieved prior to plant restart.
Some of the identified items may be
potential enforcement findings. Any enforcement actions will be identified
by Region I in separate correspondence.
In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure
will be placed in the NRC Public Document Room.
You are requested to respond to this office within 60 days regarding the
concerns and weaknesses identified in the enclosed inspection report.
Should you have any questions concerning this inspection, please contact
me or Mr. Stephen Guthrie (301-492-0991).
Sincerely,
&
Gus C. Lainas, Acting Director
Division of Reactor Projects - I, II
Office of Nuclear Reactor Regulation
Enclosure:
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NRC Inspection Report 50-219/88-202
cc w/ enclosure:
See next page
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- Mr.-E..E.~F1tzpatrick
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February 17, 1989
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Ernest!L. Blake, Jr.
Resident Inspector
Shaw, Pittman,;Potts and Trowbridge
c/o U.S. NRC
-2300 N Street, NW
Post Office Box 445
Washington, DC 20037
Forked River, New Jersey 08731
J. B. Liberman, Esquire
Commissioner
P>ishop,'Liberman, Cook, et al.
New Jersey Department of Energy
1155 Avenue of the Americas
'101 Commerce Street
Newark, New Jersey 07102
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Regional Administrator, Region I
Jennifer Noon, Acting Chief
U.S. Nuclear Regulatory Comission
New Jersey Department of Environmental
475 Allendale Road
Protection
King of Prussia, Pennsylvania 19406
Bureau of Nuclear Engineering
CN 415'
BWR Licensing Manager
Trenton, New Jersey 08625
GPU Nuclear Corporation
1 Upper Pond Road
Institute of Nuclear Power Operations
Parsippany, New Jersey 07054
1100 Circle 75 Parkway
Atlanta, Georgia 30339
Deputy Attorney General
State of New Jersey
Department of Law and Public Safety
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36 West State Street - CN 112
Trenton, New Jersey 08625
Mayor
Lacey Township
818 West Lacey Road
Forked River, New Jersey 08731
Licensing Manager
Oyster Creek Nuclear Generating Station
Mail Stop: Site Emergency Bldg.
Post Office Box 388
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Forked River, New Jersey 08731
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Distribution:
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