ML20246D178

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Notice of Violation from Insp on 890710-14.Violation Noted: Pipe Support 2 SGT-6VH30 Not Repaired within Time Prescribed by EER 85-0364 & Licensee Design Verification Inadequately Implemented During Review of EER 85-0364
ML20246D178
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 08/14/1989
From: Julian C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20246D169 List:
References
50-324-89-18, 50-325-89-18, NUDOCS 8908250281
Download: ML20246D178 (2)


Text

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ENCLOSURE 1 NOTICE OF VIOLATION Carolina Power and Light Company Docket Nos. 50-325, 50-324 Brunswick License Mos. DPR-71, OPR-62 During the Nuclear Regulatory Commission (NRC) inspection conducted on July 10-14, 1989, a violation of NRC requirements was identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1989), the violation is listed belnw:

.10 CFR 50, Appendix B, Criteria V, and the licensee's accepted QA program (FSAR Section 17.2.5) collectively require that activities affecting quality shall be prescribed by documented instructions and shall be accomplished in accordance with these instructions. Engineer Procedare ENP-12, Engineering Evaluation Procedure, requires resolution of problem identified in Engineering Evaluation Reports (EER) be repaired as directed by the EER, within tha time prescribed on the EER, 10 CFR 50, Appendix B, Criterion III, as implemented by the CP&L accepted QA Program (FSAR Chapter 17.2.3) requires that design control measures provide for verifying or checking the adequacy of design, such as by the performance of design. reviews, by use of alternative or simplified calculation methods, or by performance of a suitable testing program.

Contrary to the above, pipe support 2 SGT-6VH30 was not repaired within time prescribed by EER 85-0364, and the licensee's design verification was inadequately implemented during review of EER 85-0364, in that, the structural s teel beam supporting support 2 SGT-6VH30 was overstressed, it was not identified during the evaluation of the EER, and a similar nonconforming condition was not identified for Unit 1 support 1 SGT-6VH30.

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

Pursuant to the provisions of 10 CFR 2.201, Carolina Power and Light Company is hereby required to submit a written statement or explanation to the Nuclear Regulatory Conutssion, ATTN: Document Control Desk, Wa'hington, DC 20555, with e copy to the Regional Administrator, Region II, and a copy to the NRC

. Resident Inspector, E'runswick, within 30 days of the date of the letter transmitting this Notice. This reply should be clearly marked as a " Reply to a Hotice of Violation' and shculd include [for each violation]: (1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken and the results achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will te achieved. Where good cause is shown, i

990825028 epog14 (DR ADOCK 05000324 PDC s

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Carolina Power and Light _ Company 2 Docket Hos. 50-325, 50-324

- Brunswick- License Nos. DPR-71, DPR-62 .

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consideration will be given to' extending the response time. If an adequate

'.s reply is not received within the. time specified in this Notice., an order may be  !

. issued to show cause why the license should not be modified, suspended, or revoked or why such other. action as cay be proper should not be taken.

FOR THE NUCLEAR REGULATORY COMMISSION c

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- / A. Julian, Chief

/ Engineering Branch Division of Reactor Safety Dated at Atlanta, Georgia this 4h day of August 1989 1

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