ML20204J382

Notice of Violation from Insp on 860601-30

ML20204J382
Person / Time
Site:	Brunswick
Issue date:	07/15/1986
From:	Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20204J372	List: ML20204J367 ML20204J382 ML20204J399
References
50-324-86-16, 50-325-86-15, NUDOCS 8608110076
Download: ML20204J382 (2)

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4 NOTICE OF VIOLATION Carolina Power and Light Company Docket Nos. 50-325 AND 50-324 Brunswick 1 and 2 License Nos. DPR-71 and DPR-62 During the Nuclear Regulatory Commission (NRC) inspection conducted on June 1-30, 1986, violations of NRC requirements were identified. The violations involved failure to promptly correct deficiencies with the jumper / bypass control program and failure to declare a support _ inoperable when required by procedure. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix.C (1985), the violations are listed below:

A. 10 CFR 50, Appendix B, Criterion XVI, Corrective Action, as implemented by the licensee's accepted Quality Assurance .(QA) program (FSAR Chapter 17.2.6) requires, in the case of significant conditions adverse to quality, measures shall assure that the cause of the condition is determined and corrective action taken to preclude repetition.

Contrary to the above, significant conditions adverse to quality were not corrected, in that conditions similar to those found in September, 1984 and April,1986 were again found in May, 1986, as documented in NCR S-86-028.

These similar significant conditions involved jumper No. 2 as being listed as active, not signed out and not in the storage cabinet (May, 1986), which is the same condition found in April,1986 for jumpers No. 201, 293, 330 and 345 and found in September,1984 for jumpers No. 27, 28, 29, 32, 46, 76 and 79.

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

B. Technical Specification 6.8.1.c, requires procedures be implemented for surveillance and test activities of safety-related equipment. Surveillance requirement 4.0.5 of Technical Specifications requires inspection be performed of ASME Code 2 components. The inspection of the Residual Heat Removal (RHR) class 2 supports is performed by PT-91.0.37 whi.ch requires a support to be declared inoperable if a missing support item could impair the proper functioning of the support.

Contrary to the above, procedures for surveillance test were not properly implemented in that support 2E11-21FH62 was not . declared inoperable as required by PT-91.0.37 when ' a missing nut which impaired the proper functioning of the support was identified.

This is a Severity Level IV violation (Supplement I) for Unit 2 only.

Pursuant to the provisions of 10 CFR 2.201, Carolina Power and Light Company is hereby required to submit to this office within thirty days of the date of the letter transmitting this Notice, a written statement or explanation in reply, including (for each violation): (1) admission or denial of the violation, 0 g4 ..

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Carolina Power _ and_ Light, Company 2 Docket Nos. 50-325 AND 50-324 Brunswick 1 and 2 License Nos. DPR-71 and DPR-62 (2) the reasons 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 be achieved. Where good cause is shown, consideration will be given to extending the response time.

FOR THE'NU AR EGULATORY COMMISSION S *, l.s d'/Division o Luis A.~ Rey Acting Director l seactor Projects Dated at Atlanta, Georgia this 15 day of. July 1986

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