ML20236Q522
| ML20236Q522 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 11/06/1987 |
| From: | Murley T Office of Nuclear Reactor Regulation |
| To: | Phyllis Clark GENERAL PUBLIC UTILITIES CORP. |
| Shared Package | |
| ML20236Q524 | List: |
| References | |
| CAL-87-12, NUDOCS 8711200106 | |
| Download: ML20236Q522 (4) | |
Text
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NOV 0 61997 i
Docket No. 50-219 Mr. P. R. Clark, President GPU Nuclear Corporation 100 Interpace Parkway Parsipanny, New Jersey 07054
Dear Mr. Clark:
SUBJECT:
RESTART OF OPERATION - OYSTER CREEK NUCLEAR GENERATING STATION On September 11, 1987, Oyster Creek Nuclear Generatirg Station reported to the Nuclear Regulatory Commission that a violation of Safety Limit 2.1.E of the Technical Specifications had occurred in that fewer than two sets of recirculation loop valves were fully open for a short period of time as required by the limit.
In our Confirmatory Action Letter 87-12 of September 11, 1987, we stated that GPU Nuclear Corporation (GPUN) will:
1.
Maintain the plant in a shutdown condition per the requirements of 10 CFR 50.36 which require Commission approval for restart.
2.
Establish and maintain as found conditions for relevant hardware and process systems which pertain to analysis of the event. These conditions will be maintained until released by the NRC.
3.
Conduct an independent review of the circumstances surrounding the events and forward a report to the Commission per the requirements of Technical Specification Section 6.7.
On September 14, 1087, the NRC modified Confirmatory Action Letter 87-12 in that it released all plant equipment which was to be maintained as found by condition 2 of the Confirmatory Action Letter.
In letters dated September P0 and 22, 1987 and October 14, 1987, GPUN provided an analysis of the event and its corrective actions and has satisfied condition 3 of the Confirmatory Action Letter. A meeting in Region I was also held on September 29, 1987 to discuss this matter.
Region I inspected GPUN's procedure charges and supplemental training to be provided to the control room operators. The details of this inspection will be documented in a subsequent inspection report.
We have reviewed the above information and have determined that the cause of the event has been identified and corrective actions appear to be adequate.
In our Safety Evaluation which is enclosed, we conclude that the event is considered a violation of the safety limit Technical Specification, but its safety significance is considered low. The basis for this conclusion is that core cooling was always adequate due to the low decay heat levels, fluid communication between l[k300$
k9 P
C l vessel regions was always maintained and, in addition, the fuel zone level instrumentation was. functional and indicated that the fuel region water level was always maintained at appropriate levels for a shutdown reactor. Reactor water level was always maintained at several feet above the top of the active fuel. There was no fuel or equipment damage during the event.
The maintenance activities leading to a leak and the resulting operator actions violating the safety limit are safety significant and have been the focus of licensee corrective action and NRC confirmatory inspection. Our review of corrective actions related to the Safety Linit Violation are complete regarding maintenance activities. Personnel retraining was accomplished as I
described in your letter of September 22, 1987. Appropriate procedure changes are complete and the Maintenance Division reorganization appears to improve I
communication and control of the work force.
Our review of changes to operations procedures has concluded that appropriate j
changes have been incorporated. Training of onshift personnel on taese changes is complete.
It has also been determined that the operators have received adequate training.
1 Furthermore, we find that standards of conduct and the need to adhere to procedures are clearly described, communicated and enforced down to the working level.
Use of task / teamwork methods, to assess the'3hift assignments is evident. Teamwork training at the site is continuing; the operating crews are being carefully evaluated and balanced. A site attitude survey which was begun l
prior to the event was used to assess and improve overall site coordination and communication.
1 In conclusion, based on the review and inspections by the NRC staff, the above corrective actions are appropriate, and have been completed in conformance with requirements and commitments. Accordingly the requirements of 10 CFR 50.36 (c)(1)(1)(A) have been satisfied for restart of operation and GPUN is hereby released from condition 1 of the Confirmatory Action Letter.
4 However, in addition to satisfying the above requirements, we also had concerns about the integrity of the operating staff and operating ma'nagement related to the destruction of records subsecuent to the September 11, 1987 event.
In a letter dated September 22, 1987 concerning this matter, GPUN provided the preliminary findings of its investigation and stated that the "B" shift crew l
was relieved of licensed duties on September ll, 1987 pending results of the investigation and if GPUN desired to return any of them to licensed duties the licensee would provide prior notification to the NRC.
In a letter dated October 26, 1087, GPUN reiterated the findings of its investigation and committed not to return any member of the "B" shift crew to licensed duties without specific approval of the NRC. Although the NRC staff's investigation regarding this matter is still in progress, we have completed our evaluations sufficiently to conclude that (1) potential responsibility is confined to the l
"B" shift crew on duty at the time and (2) GPUN management and other operating personnel possess the qualifications and training to operate the Oyster Creek Nuclear Generating Station safely and that standards of conduct and the need to i
adhere to procedures are clearly described, communicated and enforced down to the working level.
l
I I.
Based on the above letters from GPUN, the NRC staff has issued Confirmatory Order dated November 5, 1987, confirming the licensee's commitment to i
(1) prohibit any member of the operating Shift B who was on duty September 11, 1987 from performing licensed duties unless the licersee notifies and obtains approval of the NRC Regional Administrator, Region I, prior to returning such a person to licensed duties and (2) provide the NRC Regional Administrator, Region I, a copy of the Investigation Report prepared by or on behalf of the licensee concerning this event upon completion of its investigation.
Sincerely, Orlsi:n] :.!r,rd b/,
Yncro E..drley Thomas E. tiurley, Director Office of Nuclear Reactor Regulation Enclosure Safety Evaluation cc w/ enclosure:
See next page DISTRIBUTION Docket. FHe -
NRC'& Local PDRs PDI d Peading File S. Varga B. Boger S. Norris A. Dromerick OGC-Bethesda E. Jordan J. Partlow ACRS (10) l PDI-4 (Gray File)
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Oyster Creek Nuclear Generating Station
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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, D.C.
20037 Forked River, New Jersey 08731 J.B. Libeman, Esquire Commissioner Bishop, Libeman, Cook, et al.
New Jersey Department of Energy 1155 Avenue of the Americas 101 Comerce Street New York, New York 10036 Newark, New Jersey 07102 Mr. David M. Scott, Acting Chief Regional Administrator, Region I Bureau of Nuclear Engineering U.S. Nuclear Regulatory Commission Department of Environmental Protection 631 Park Avenue CN 411 King of Prussia, Pennsylvania 19406.
Trenton, New Jersey 08625 BWR Licensing Manager Mr. Pr B. Tiedler GPU Nuclear Corporation Vice President and Director 1 Upper Pond Road oyster Creek Nuclear Generating Station Parsippany, New Jersey 07054 Post office Box 388 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 0/ ster Creek Nuclear Generating Station Mail Stop: Site Emergency Bldg.
P. O. Box 388 Forked River, New Jersey 08731
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