ML20205F287
| ML20205F287 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/31/1985 |
| From: | Holahan G Office of Nuclear Reactor Regulation |
| To: | Zwolinski J Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8511050285 | |
| Download: ML20205F287 (3) | |
Text
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OCT 311383 MEMORANDUM FOR:
John Zwolinski, Chief
.0perating Reactors Branch #5 Division of Licensing FROM:
Gary Holahan, Chief Operating Reactors Assessment Branch Division of Licensing
SUBJECT:
OYSTER CREEK - SALP REPORT Recently, ORAB provided your Branch with an SER for an emergency Technical Specification change dealing with the reactor vessel water level instrumentation at Oyster Creek. Due to the urgency of that change, we were unable to include our SALP input but are doing so now.
Gary Holahan, Chief Operating Reactors Assesement Branch 4
Division of Licensing
Enclosure:
As stated cc:
F. Miraglia D. Crutchfield J. Donohew DISTRIBUTION:
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- s,*****gl QCT 31885 MEMORANDUM FOR:
John Zwolinski, Chief Operating Reactors Branch #5 Division of Licensing FROM:
Gary Holahan, Chief Operating Reactors Assessment Branch Division of Licensing
SUBJECT:
OYSTER CREEK - SALP REPORT Recently, ORAB provided your Branch with an SER for an emergency Technical Specification change dealing with the reactor vessel water level instrumentation at Oyster Creek.
Due to the urgency of that change, we were unable to include our SALP input but are doing so now.
?
Gary Holahan, Chief Operating Reactors Assessment Branch Division of Licensing
Enclosure:
As stated cc:
F. Miraglia D. Crutchfield
..y.
J. Donohew e
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w
l 9
SALP INPUT l
1.
Management Involvement and Control in Assuring Quality During the review of the emergency Technical Specification change regarding reactor vessel water level instrumentation, there was no evidence of licensee management involvement. The utility contact was the normal licensing contact who arranged and participated in the numerous telephone conferences required to complete this review.
The basic need for the change was a lack of adequate planning for a special maintenance outage. Perhaps better management involvement could have helped avoid last minute problems such as this.
Rating:
Category 3 2.
Approach to Resolution of Technical Issues From a Safety Standpoint The licensee's approach appeared lacking in thoroughness and depth. The approach focused upon a legal technicality of the Technical Specifications regarding operability of the Standby Gas Treatment System. There appeared to be little regard for the safety issues related to disabling a large portion of the water level instrumentation.
The licensee's approach to the question of the accuracy of " hot-calibrated" instruments when operated under cold conditions suggests a lack of technical understanding and lack of thoroughness.
Rating:
Category 3 3.
Responsiveness to NRC Initiatives Although the basic Technical Specificat' ion change was not an NRC initiative, several questions were raised by the NRC staff. Obtaining adequate answers to the NRC questions involved considerable effort on the part of the NRC and required repeated submittals by the licensee.
Rating:
Category 3