ML20246P062
| ML20246P062 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 03/16/1989 |
| From: | Lainas G Office of Nuclear Reactor Regulation |
| To: | Fitzpatrick E GENERAL PUBLIC UTILITIES CORP. |
| Shared Package | |
| ML20246P069 | List: |
| References | |
| NUDOCS 8903280101 | |
| Download: ML20246P062 (6) | |
See also: IR 05000219/1988203
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D. C. 20555
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March 16, 1989
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Docket No. 50-219
Mr. E. E. Fitzpatrick
Vice President and Director
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Oyster Creek Nuclear Generating Station
Post Office Box 38a
Forked River, New Jersey 08731
Dear Mr. Fitzpatrick:
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SUBJECT:
SAFETY SYSTEMS OUTAGE MODIFICATIONS INSPECTION AT OYSTER CREEK
NUCLEAR GENERATING STATION - (INSPECTION REPORT 50-219/88-203)
This letter forwards the report and Executive Summary of the installation and
testing portion of the safety systems outage modifications inspection (SSOMI)-
conducted by the NRC's Office of Nuclear Reactor Regulation from November 28
through December 16, 1988. The operation of the Oyster Creek Nuclear
Generating Station is authorized by NPC Operating License No. DPR-016. At the
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conclusion of the inspection, the inspection team discussed the findings with
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you and with other members of your staff identified in Appendix A of the
enclosed inspection report.
The purpose of the installation and test portion of the SS0MI was (1) to
determine, through an examination of specific work packages, that installation
of the selected modifications conformed to design and instal stion requirements
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and (2) to verify that the repaired or modified components at:1 systems have the
required operating configurations and have been adequately tested to ensure
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that they are capable of safely performing their intended functions.
The inspection team identified weaknesses involving the implementation of
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existing programs and procedures.
Inadequate management attention had been
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provided to ensure that activities directly related to the satisfactory
performance of safety-related work and maintenance were conducted in accordance
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with approved procedures. Our primary concern was that the failure to
implement these procedures resulted in a degradation in the cleanliness of the
facility and had the potential to adversely affect the quality of maintenance
and modifications performed during the recent outage.
For example, the failure
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to implement the controls for combustibles and housekeeping allowed the
condition of the facility to degrade.
In addition, the failure to revise the
administrative procedures for job orders following a major change in the method
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of controlling work activities resulted in the performance of complex testing
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and maintenance on the emergency diesel generator without prior engineering or
operations review and approval.
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At the conclusion of the inspection, a number of equipment operability concerns
remained to be resolved.
In a letter dated December 23, 1988, we requested
that you expeditiously evaluate several of the inspection team's concerns.
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These involved (1) core spray and containment spray system injection valve
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Mr. E. E. Fitzpatrick
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March 16, 1989
stroke times in excess of design values, (2) grease contamination in Limitorque
motor-operated valves, (3) control room heating, ventilation and cooling system
flows less than design values, and (4) unapproved testing and maintenance
performed on emergency diesel generator No.1.
We have reviewed your response
dated January 12, 1989, and concluded that your evaluations and corrective
actions adequately resolved the concerns with the operability and reliability
of these systems. Although no formal response to this report is required, some
of the items identified by the inspection team 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.
Should you have any questions concerning this inspection, please contact
Mr. C. A. VanDenburgh (301-492-0965).
Sincerely,
Gus C. Lainas, Acting Director
Division of Reactor Projects - I/II
Office of Nuclear Reactor Regulation
Enclosures:
1.
Executive Summary
2.
NRC Inspection Report 50-219/88-203
cc w/ enclosures: See next page
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Mr, E. E. Fitzpatrick
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March 16, 1989
cc w/ enclosures:
Ernest L. Blake, Jr.
Resident Inspector
Shaw, Pittman, Potts and Trowbridge
c/o U.S. NRC
2300 N Street, NW
P. O. Box 445
Washington, DC 20037
Forked River, New Jersey. 08731
J. B. Liberman, Esquire
Consnissioner
Bishop, Liberman, Cook, et, al.
New Jersey Department of Energy
1155 Avenue of the Americas
101 Commerce Street
Newark, New Jersey 07102
Regional Administrator, Region I
Jennifer Moon, Acting Chief
U.S. Nuclear Regulatory Commission
New Jersey Department of Environmental
745 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
Parsipanny, New Jersey 07054
Deputy Attorney General
State of New Jersey
Department of Law and Public Safety
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 Building
P.O. Box 388
Forked River, New Jersey 08731
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EXECUTIVE SUMMARY
An installation 'and testing portion of a safety systems outage and modifica-
tions inspection (SS0MI) was performed at the Oyster Creek Nuclear Generating
Station during the period November 28 through December 16, 1988. The purpose
of the inspection was to determine whether the licensee properly implemented
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' design, design control, procurement control, material control, and work control
systems to ensure that modifications being implemented during the current
outage conformed to design and installation requirements and that repaired,
modified, or newly installed components or systems were tested to ensure that
they were, or remained, capable of performing their intended safety functions.
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The inspection team concluded that the craftsmanship of the work performed in
the modifications was of high quality.
The team identified several minor
hardware deficiencies, which resulted from not adhering to the installation
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criteria provided in the modification packages; however, the licensee corrected
these deficiencies before the team's departure.
Increased management attention
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is required to ensure that the installation criteria are properly implemented
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(Section2.2.4).
The inspection team also concluded that the licensee provided insufficient
management attention to ensure the successful implementation of existing
programs and procedures for document adequacy and control, post-maintenance
testing, and general plant maintenance. These conclusions were based on the
following deficiencies.
The licensee inadequately controlled the work control process because the
implementing procedures had not been rev Q ed following the incorporation
of a computer-based work control system,
c 9 dition, the new system did
not incorporate equivalent requirements for post-maintenance testing
(Section 2.1.6).
As a result, complex maintenance and modifications
performed under the new system did not receive the same level of
engineering review and approval as was required under the old system
(Section 2.2.2).
The licensee inadequately evaluated the design basis for valve stroke
times during post-maintenance testing of core spray and containment spray
system valve modifications (Section 2.1.4).
The licensee inadequately evaluated the post-maintenance testing of the
control rcom ventilation system modification (Section 2.2.7).
The licensee inadequately implemented existing procedures for the control
oftransientcombustiblesandhousekeeping(Section2.2.8),exeting
- methods for craft identification of pre-existing deficient material
conditions (Section 2.1.4) and existing procedures for changing
quality assurance verification inspections (Sections 2.1.4 and 2.1.10).
The licensee inadequately implemented a previously identified corrective
action program for grease contamination of Limitorque motor-operated
valves (Section 2.2.3).
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Mr. E.E. Fitzpatrick
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Distribution
Docket File 50-219
DRIS R/F
RSIB R/F
LPDR
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CHaughney
JDyer
Elmbro
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JKonklin
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GHolahan
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JStolz
SNorris
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MGallo, RI
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JDurr, RI
CCowgill, RI
Inspection Team
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Regional Administrators
Regional Division Directors
Division Directors
IS Distribution
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DATE :03/n /89
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Mr. E. E. Fitzpatrick
-4-
March 16, 1989
Distribution
Docket File 50-219
DRIS R/F
RSIB R/F
LPDR
BGrimes
CHaughney
JDyer
Elmbro
JKonklin
CVanDenburgh
GHolahan
LSpessard
TMurley
JSniezek
SVarga
BBoger
ADromerick
JStolz
SNorris
MGallo, RI
JDurr, RI
CCowgill, RI
Inspection Team
Regional Administrators
Regional Division Directors
Division Directors
IS Distribution
GLainas
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- SEE PREVIOUS CONCURRENCES
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NAME :CAVanDenburgh
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- AWDromerick
Clai.
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DATE :03/13/89
- 03/13/89
- 03/13/89
- 03/13/89
- 03/14/89~
- 03/j /89
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