ML19296D724
| ML19296D724 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 02/22/1980 |
| From: | Lazo R Atomic Safety and Licensing Board Panel |
| To: | |
| References | |
| NUDOCS 8003130069 | |
| Download: ML19296D724 (4) | |
Text
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION g
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,9 THE ATOMIC SAFETY AND LICENSING BOARD cdg#' @ y g
'2 Robert M. Lazo, Esquire, Chairman 6-g Dr. Hugh C. Paxton, Member pg '3 9
p,g eg Dr. Paul W. Purdom, Member
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m In the Matter of
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Docket No. 50-219 JERSEY CENTRAL POWER & LIGHT COMPANY
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(Conversion to Full-Term Operating. License Proceedings)
(0yster Creek Nuclear Generating Station)
February 22, 1980 ORDER DISMISSING PROCEEDING On May 31, 1979, the Atomic Safety and Licensing Board issued a Memorandum and Order which approved the environmental technical specifica-tions previously submitted for the Board's review and which indicated that the pending Motion to Terminate Hearing could now be considered except for one concern.
The Board asked that the NRC Staff advise it of the significance of the recent (May 2,1979) loss of coolant inventory transient and consequent olant shutdown at Oyster Creek Nuclear Generating Station.
Thereafter, on June 8,1979, the Staff provided the Board with a copy of the Restart Safety Evaluation Report (Potart SER) concerning the event which the Staff had issued on May 30, 1979.
As indicated by the Restart SER, the Staff concluded the Oyster Creck core was undamaged and that with additional technical specifications imposed there was reasonable 800313 0 0 M
- assurance plant operation could be resumed without undue risk to the health and safety of the public.
The Licensee was authorized to resume operation on May 30, 1979.
On September 25, 1979, the Staff again moved to terminate the proceeding.
Having reviewed the information provided by the Staff, the Board has concluded it has no further questions to be addressed in this matter and the Staff requests that the proceeding be terminated should be granted.
The description of the abnormal occurrence event and the remedial actions taken by the Licensee and the Staff are suamarized in the report published by the Commission in the Federal Register on August 30, 1979 (44 Fed. Req. 50925-28).
The loss of feedwater transient at the Oyster Creek facility on May 2,1979, resulted in a significant reduction in water inventory above the reactor core area as measured by one set of water level instruments (triple-low level), while the remaining two sets of level instrumentation in the reactor annulus indicated water levels above any protective feature setpoint. The water level measured within the core shroud area fell be-low the triple-low level setpoint, a safety limit, of five feet six inches above the top of the fuel.
Subsequent analyses by the licensee have con-servatively determined that the minimum water level over the top of the fuel was one and one-half feet.
Coolant sample analyses and offgas re-lease rates support the conclusion that no fuel damage occurred.
. After performing a thorough evaluation of the event to determine whether any fuel damage had occurred and discussing the evaluation with the Staff, the Licensee took ti.9 following actions:
1.
The triple-low level was established as a Safety Limit for at modes of reactor operation; 2.
A requirement was added to the Technical Specifications that the suction and discharge valves in at least two recir-culation loops be open at all times.
The procedures were changed to implement this requirement; 3.
Operator training sessions were held, the event was thoroughly discussed and the revised procedures reviewed.
Following Staff review and preparation of the Saf:ty Evaluation Report, the following three requirements were added to the Technical Speci fications :
1.
The triple-low level was made a Safety Limit for all mode-switch positions; 2.
At least two recirculation loop discharge and suction valves must remain in the full open position; 3.
The time duration of the low-low level signal was required to be not greater than that used in the safety analysis for the limiting loss-of-inventory transient.
It was concluded that no evidence of fuel damage was apparent and that the facility could be safely returned to operation.
The Joint Motion to terminate the proceeding is granted. All pro-ceedings involving the application to convert the provisional operating license for this facility to a full-term operating license are terminated and the case is dismissed.
Dr. Hugh C. Paxton and Dr. Paul W. Purdom, Board Members, join in and concur with this Order.
It is so ORDERED.
FOR THE ATOMIC SAFETY AND LICENSING BOARD L.
Robert M. Lazo, Chairm o Dated at Bethesda, Maryland, this 22nd day of February,1980.