ML20202F136

Notice of Violation from Insp on 860224-28

ML20202F136
Person / Time
Site:	Salem
Issue date:	04/07/1986
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20202F124	List: IR 05000272/1986007 ML20202F119 ML20202F136
References
50-272-86-07, 50-272-86-7, 50-311-86-07, 50-311-86-7, NUDOCS 8604140111
Download: ML20202F136 (2)

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APPENDIX A NOTICE OF VIOLATION Public Service Electric & Gas Co.

Docket Nos. 50-272 Salem Nuclear Generating Station 50-311 Unit I and Unit 2 License Nos. DPR-70 DPR-75 As a result of the inspection conducted on February 24-28, 1986, and in accord-ance with the NRC Enforcement Policy (10 CFR 2, Appendix C), published in the Federal Register on March 8,1984, the following violation was identified:

10 CFR 50, Appendix B, Criterion III requires that measures shall be established to assure that design bases (i.e. information which identifies the functions to be performed or the specific values or range of values chosen for controlling parameters as references bounds for design) are correctly translated into specifications, procedures and instructions.

Section 17.2.3 of the licensee's Quality Assurance Program Description implements these design control requirements of 10 CFR 50 Appendix 8.

PSE&G's procedure, " Criteria for Calculating Expansion Bolt Loads with i'

Flat Plate Supports", and Associated Technologies, Inc. procedure, " Pipe Support Base Plate Flexibility Evaluation" describe the design approaches to be used to account for base plate flexibility and concrete expansion anchor bolt loads in response to IE Bulletin 79-02.

Contrary to the above, on or before January 30, 1984 the foregoing proce-dures were used to reanalyze safety related pipe support base plates for Salem Units 1 and 2 and these procedures did not correctly translate the design bases in that:

1.

The procedure used by Associated Technologies, Inc. utilized a design approach in the AISC Manual of Steel Construction which did not account for base plate flexibility in the calculation of anchor bolt loads.

2.

The procedure used by PSE&G underestimated anchor bolt loads such that appropriate factors of safety as derived from more accurate analytical techniques, such as finite element analysis, were not provided.

This is a Severity Level IV violation (Supplement I) applicable to DPR-70 and DPR-75.

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Appendix A 2

i Pursuant to the provisions of 10 CFR 2.201, Public Service Electric and Gas Company is hereby required to submit to this office within thirty days of the date of the letter which transmitted this Notice, a written statement or explanation in reply, including: (1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further violations; and (3) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending this response time.

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