ML20205F287

Forwards SALP Input on Tech Spec Change Re Reactor Vessel Water Level Instrumentation.Due to Urgency of Change,Salp Input Not Submitted W/Ser

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 4

Operating Reactors Assesement Branch 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

. .y. D. Crutchfield J. Donohew e

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SALP INPUT ,

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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