ML20209C853

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Provides Guidance for Verifying Acceptability of Plant Mods Identified in Seismically Induced Sys Interaction Program. Verification Should Be Completed by mid-Apr for Inclusion in Recommendations to Commission
ML20209C853
Person / Time
Site: Diablo Canyon Pacific Gas & Electric icon.png
Issue date: 04/03/1984
From: Eisenhut D
Office of Nuclear Reactor Regulation
To: Martin J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
Shared Package
ML17083B484 List:
References
FOIA-86-197, RTR-NUREG-0675, RTR-NUREG-675 NUDOCS 8404180252
Download: ML20209C853 (2)


Text

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53 p Docket No. 50-275 MEMORANDUM FOR: John B. Martin, Administrator Region V FROM: Darrell G. Eisenhut, Director Division of Licensing

SUBJECT:

DIABLO CANYON - SYSTEMS INTERACTION PROGRAM Per your request to George Knighton of my staff, this memorandum provides guidance for verifying the acceptability of plant modifications identified in PG&E's Seismically Induced Systems Interaction Program for Diablo Canyon Nulcear Power Plant, Unit 1. In our evaluation of the program (Section 8.2 of Supplement 11 to the Diablo Canyon Safety Evaluation Report, NUREG-0675),

we found the program acceptable and planned to rely upon Region V to verify both the completion of the PG&E program and the acceptability of any modifications made as a result of their program.

We have continued to review documents provided by PG&E concerning the progress and completion of their Seismically Induced Systems Interaction Program. PG&E stated that their program has been completed including the plant modifications. At this time it is necessary to verify both that the plant modifications are completed and that the modifications comply with the l objectives of the program as documented by PG&E.

I suggest that the verification should be both (1) an inspection of the PG&E program records to assure the completion of,the plant modifications identified l by their program and (2) a visual inspection of some of the plant modifications.

The visual inspection should provide assurance both that the plant modification resolved the postulated systems interaction and that the modification was examined against not introducing any new systems interaction. To facilitate the visual inspection, we have selected some of the identified

, interactions which were resolved by plant modification:

. PG&E Classification PG&E Systems Interaction Number Structural 03-022-001-001

! 07-008-001-002 09-004-002-003 32-001-033-005 l

l Mechanical 06-001-001-006 15-001-029-001 l

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APR 3 1964 PG&E Classification PG&E Systems Interaction Number Piping 01-006-001-001 18-001-023-002 22-017-001-001 24-001-118-001 25-200-002-001 Electrical 04-004-001-001 22-001-001-002 23-012-004-001 24-012-003-001 I&C 03-028-023-001 06-001-004-007 30-001-099-002 HVAC 03-005-002-003 11-007-005-005 23=067-002-001 25-179-002-001 SSER 11 states that the verification will occur during the normal course of inspection activities. Since the matter of systems interactions has been the subject of recent allegations, it is appropriate to complete the verification early. I request the completion by mid-April to allow the results to become part of the staff recommendations to the Commission concerning authorization for full power operations. We expect the verification will require less than one person-week for completion. Please advise us of your schedule and provide a brief report on the results of your veri fi ca t. ion. NRR personnel can be available to assist your staff in this verification. For further clarification please contact Hans Schierling, Licensing Branch 3, FTS 492-7100 or Frank Coffman, Reliability and Risk Assessment Branch, FTS 492-7497.

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Distribution Central file Darrell G. Eisenhut, Director RRAB Rdg Division of Licensing F Coffman Coffman CHRON A Thadani WG Knighton T Novak D Eisenhut i ,u - / A

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