ML19332F766

Notice of Violation from Insp on 891030-1103.Violation Noted:Failure to Have Adequate Design Controls Re Preparation,Review & Approval of DCR 85-007,Rev 1 for Installed commercial-grade Relays on Class IE Sys

ML19332F766
Person / Time
Site:	Hatch
Issue date:	12/08/1989
From:	Peebles T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19332F765	List: IR 05000321/1989030 ML19332F764 ML19332F766
References
50-321-89-30, 50-366-89-30, NUDOCS 8912180228
Download: ML19332F766 (4)

Text

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ENCLOSURE 1 NOTICE OF VIOLATION Georgia Power Company Docket Nos. 50-321 and 50-366 Hatch License Nos. DPR-27 and NPF-5 During the Nuclear Regulatory Comission (NRC) inspection conducted on October 30 - November 3,1989, 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 below:

10 CFR 50 Appendix B, Criterion III, and the accepted QA Program require establishing measures to assure that applicable regulatory requirements and the design bases are correctly translated into specifications, drawings, procedures, and instructions.

These measures shall include provisions to assure that appropriate quality standards are specified and included in design documents and that deviations from such standards are controlled.

Measures shall also be established for the selection and review for suitability of application of materials, parts, equipment and processes that are essential to the safety related functions of structures, systems and components.

Section 17.2.3 of the accepted QA l

Program requires the review of applicable regulatory standards, design bases, and requirements of the licenses to ensure that these factors are taken into account in preparation of drawings, specifications, and other design documents.

The program endorses Regulatory Guide 1.64 and ANSI N45.2-11-1974.

Section 4 of this standard specifically requires that appropriate quality standards be identified, documented and their selection reviewed and approved.

Contrary to the above, on January 12, 1985, plant modification package DCR 85-007,. Revision 1, installed two commercial grade Agastat time-day-relays, model 7022AD, in the 120V Class 1E instrument panels H11-P612 and H11-P613.

A design basis for use of the non-seismically qualified relays in a seismic application was not provided in that an engineering evaluation and/or test to assess the seismic adequacy of the relays was not performed.

Neither was a failure analysis of the relays during and after a seismic event performed to determine the effects on other safety related components mounted in the Class 1E instrument panels.

This is a Severity Level IV violation (Supplement 1).

8912180228 891208

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PDR ADOCK 0S000366 o

FDC

Georgia Power Company 2

Docket Nos. 50-321 and 50-366 Hatch License Nos. DPR-27 and NPF-5 Pursuant to the provisions of 10 CFR 2.201, Georgia Power Company is hereby required to submit a written statement or explanation to the Nuclear Regulatory Comission, ATTN: Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, within 30 days of the date of the letter transmitting this Notice.

t This reply should be clearly marked as a " Reply to a Notice of Violation" and should-include [foreachviolation]:

(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 be achieved.

Where good cause is shown, consideration will be given to extending the response time.

If an adequate 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 may be proper should not be taken.

FOR THE NUCLEAR REGULATORY COMMISSION

/

Thomas A. Peebles, Chief Operations Branch Division of Reactor Safety Dated at Atlanta, Georgia dayofp 1989 this 1

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l ENCLOSURE 1 NOTICE OF VIOLATION L

Georgia Power Company Docket Nos. 50-321 and 50-366 Hatch License Nos. OPR-27 and NPF-5 During the Nuclear Regulatory Comission (NRC) _ inspection conducted on October 30 - November 3,1989, a violation of NRC requirements was identified.

In accordance with the " General Statement of Policy and Procedure for NRC EnforcementActions,"10CFRPart2.AppendixC(1989),theviolationislisted below:

10 CFR 50 Appendix B, Criterion III, and the accepted QA Program require establishing measures to assure that applicable regulatory requirements and the design bases are correctly translated into specifications,-

drawings, procedures, and instructions.

These measures shall include provisions to assure that appropriate quality standards are specified and included in design documents and that deviations from such standards are l

controlled.

Measures shall also be established for the selection and L

review for suitability of application of materials, parts, equipment and processes that are essential to the safety relateo functions-of structures, systems and components.

Section 17.2.3 of the accepted QA Program requires the review of applicable regulatory standards, design bases, and requirements of the licenses to ensure that these factors are taken into account in preparation of drawings, specifications, and other design documents.

The program endorses Regulatory Guide 1.64 and ANSI N45.2-11-1974.

Section 4 of this standard specifically requires l

l that. appropriate quality standards be identified, documented and their L

selection reviewed and approved.

Contrary to the above, on January 12, 1985, plant modification package DCR l

85-007, Revision 1, installed two commercial grade Agastat time-day relays, model 7022AD, in the 120V Class 1E instrument panels H11-P612 and H11-P613.

A design basis for use of the non-seismically qualified relays in a seismic application was not provided in that an engineering evaluation and/or test to assess the seismic adequacy of the relays was i

I not performed.

Neither was a failure analysis of the relays during-and after a seismic event performed to determine the effects on other safety L

related components mounted in the Class IE instrument panels.

This is a Severity Level IV violation (Supplement 1).

Georgia Power Company 2

Docket Nos. 50-321 ano 50-366 Hatch License Nos. DPR-27 and NPF-5 Pursuant to the provisions of 10 CFR 2.201, Georgia Power Company is hereby required to submit a written statement or explanation to the Nuclear Regulatory Comission, ATTN:

Document Control Desk Washington, DC 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, within 30 days of the date of the letter transmitting this Notice.

This reply should be clearly marked as a " Reply to a Notice of Violation" and should 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 be achieved.

Where good cause is shown, consideration will be given to extending the response time.

If an adequate 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 may be proper should not be taken.

FOR THE NUCLEAR REGULATORY COMMISSION f

Thomas A. Peebles, Chief Operations Branch Division of Reactor Safety Dated at Atlanta, Georgia this day of 1989 I

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