ML20205E136

Notice of Violation from Insp on 860414-0601

ML20205E136
Person / Time
Site:	Oyster Creek
Issue date:	08/08/1986
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20205E123	List: ML20205E116 ML20205E136 ML20205E159
References
50-219-86-12, NUDOCS 8608180253
Download: ML20205E136 (2)

Text

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APPENDIX A NOTICE OF VIOLATION GPU Nuclear Corporation Docket No. 50-219 Oyster Creek Nuclear Generating Station License No. DPR-16 As a result of the inspection conducted from April 14 - June 1, 1986, and in accordance with the NRC Enforcement Policy (10CFR 2, Appendix C) Published in the Federal Register on March 8, 1984 (49 FR 8583), the following violations were identified:

A. 10 CFR 50 Appendix B Criterion V and Section 3 of the Oyster Creek Opera-tions Quality Assurance Plan require, in part, that activities affecting quality be prescribed by procedures.

Contrary to the above, as of April 21, 1986, pipe support, FP-008, which had been recently installed as part of a seismic upgrade of the Spent Fuel Pool Cooling System, was disassembled after its acceptance by QC without procedures to control the rework and to ensure reinspection.

This is a Severity Level IV Violation (Supplement I).

B. 10 CFR 50 Appendix B Criterion IV and Section 5.1 of the Oyster Creek Operations Quality Assurance Plan require, in part, that measures be esta-blished to assure applicable design bases and other requirements necessary to assure adequate quality are suitably included or referenced in documents for procurement of services.

Contrary to the above, as of April 21, 1986, documents involved in procure-ment of services by the licensee to design seismic supports for the Spent Fuel Pool Cooling system did not contain specific information as to limita-tions regarding attachment of seismic supports to existing components. As a result seismic restraints FP-001 and FP-002 were welded to non-seismic, not important to safety floor penetrations to transfer seismic loads to the building structure.

This is a Severity Level IV Violation (Supplement I).

C. 10 CfR 50 Appendix B Criterion IX and Section 6.4 of the Oyster Creek Operations Quality Assurance Plan require, in part, that special pro-cesses, such as welding, be controlled and accomplished in accordance with codes, standards, specifications, criteria, and other special requirements.

10 CFR 50 Appendix B Criterion X and Section 6.12 of the QA Plan require, in part, that a program for inspection of activities affecting quality shall be executed to verify conformance with documented instructions, procedures, and drawings.

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Appendix A 2 Paragraph 4.2.4 of the GPUN Welding Manual requires that engineering documents and Weld Package Information Requests must specify base material specification and grade for new and existing material used in structural welding applications.

Contrary to the above, as of April 21, 1986, engineering documents and weld packages controlling welds connecting seismic supports FP-001 and FP-002 for the Spent Fuel Cooling System to existing floor penetrations did not specify the material specification and grade of the existing floor penetrations. This resulted in issuance of weld packages and filler metal to make a weld between two pieces of material, one of which was unknown.

This is a Severity Level IV Violation (Supplement I).

Pursuant to the provisions of 10 CFR 2.201, GPU Nuclear Corporation is hereby required to submit to this office within 30 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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