ML19257A046

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Comments on Draft Integrated Reliability Evalution Program in Relation to Mark I Containment long-term Program:Program Results Could Be Useful in Implementation of long-term Program
ML19257A046
Person / Time
Issue date: 11/27/1979
From: Charemagne Grimes
Office of Nuclear Reactor Regulation
To: Aycock M
Office of Nuclear Reactor Regulation
References
REF-GTECI-A-07, REF-GTECI-CO, TASK-A-07, TASK-A-7, TASK-OR NUDOCS 7912310545
Download: ML19257A046 (1)


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  • 9 NOV 2 71979 MEMORANDUM FOR:

M. B. Aycock, Deputy Director, Unresolved Safety Issues Program FROM:

C. I. Grimes, A-7 Task Manager

SUBJECT:

C0f!!EN~S ON DRAFT IREP In response to S. 'Hanauer's memo dated November 15, 1979, I have reviewed the proposed Integrated Reliability Evaluation Program as it relates to the Mark I Containment Long Tem Program (LTP).

The principal objective of the LTP is to restore the nargins of safety in the suppression chamber designs of all Mark I plants for all suppression pool hydrodynamic loading co.ditions and thereby preclude (or at least significantly reduce) the p.tential for a breach of hhe containment boundary. Since the purpo,e of the IREP is to identify potentially high risk accident sequences, I doubt that either the objectives or appmach of the LTP would be significantly changed by the roults of the IREP. This is especially true relative to the proposed schedule for the IREP in relation to the schedule for the completion of A-7.

However, the results of the IREP could be of use in the inplementation of the LTP. The identification of sensitive systems or significant failure modes-that are within the scope of the LTP could be focused on in the review of the plant-unique analyses.

For example, if a particular plant were found to be susceptible to failures in the RHR system, our review of the LTP plant-unique analysis could focus on the response of the RHR piping and less attention would be needed for other piping systems.

Here again, the IREP schedule is the limiting condition.

C.I. Grimes Plant Systems Branch Division of Operating Reactors -

, 7912310 6 PSB: DOR,

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