ML20244C126

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Forwards SER Re Tech Specs for Containment Cooling Sys Operability.Current Tech Spec Deficient Since Combinations of Inoperable Containment Heat Removal Equipment May Result in Accident Conditions Less Conservative than FSAR
ML20244C126
Person / Time
Site: Kewaunee, 05000000
Issue date: 02/28/1983
From: Houston R
Office of Nuclear Reactor Regulation
To: Lainas G
Office of Nuclear Reactor Regulation
Shared Package
ML16342B348 List: ... further results
References
FOIA-87-121 TAC-48377, TAC-49884, NUDOCS 8303090397
Download: ML20244C126 (1)


Text

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  • ENCLOSURE 1

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NUCLEAR REGULATORY COMMISSION t' 4 v.iseciou.o c. mss

's t FEB 2 8 B33 MEMORANDUM TOR:

G. Laines, Assistant Director for Operat'ing Raattors, DL FROM:

R. Houston, As'sistant Director for Reactor Safety, D51

SUBJECT:

SAFETY EVALUATION OF TECHN] CAL SPECIFICATION CONCERNIf?G CONTAltiMENT COOLING SYSTEM OPERABILITY, KEWAUNEE NUCLEAR GENERATING PLANT (TACS 48377) ,

1 Plant Nane: Kewaunee Naclear Generating Plant Locket Nos.: 50-305 Responsible Branch: OF.E (1, DL Froject Manager: M. Grotenhuis Review Brench: CSB:D5]

Review Status: Compl ete In response to Technical Assistance Request TACS 48377 (Task Interface Agrement TI A 82-16), regarding the evaluation of Tec hnical Specification 3.3.b.2 as it relates to' contairr.ent cooling system operability for the Kewaunee plant, the Contairnent Systems Branch has completed its review and furnishes the enclosed Safety Evaluation Report. The need for this . l review 111.

resulted from a recommendation by a reactor inspector from Region

  • In the enclosed SER, we conclude that the current Technical Specification 3.3.b.2 is deficient in that it allows combinations of inoperable contain-ment heat removal eouipment that could result in accident conditions less conservative than specified in the facility's Updated f5AR. We have also suggested a revised Technical Specification that would correct these de-ficiencies.

This completes our review as called for in TACS 48377.

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R. Houston, Assistant Director for Reactor Safety, Division of Systems Integration cc: R. Mattson

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[N.Grotenhuis o3 o*t OM r n

Contact:

J. Pulsipher, CSB:DSI 24953 e >