ML20154J397

Notice of Violation from Insp on 880718-22.Violation Noted: Solenoid Operated Valves Relocated W/O Initiating Rev to Plant post-fire Safe Shutdown Procedures Due to Failure to Perform Adequate Evaluation Per App R Design Guidelines

ML20154J397
Person / Time
Site:	North Anna
Issue date:	09/13/1988
From:	Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20154J392	List: IR 05000338/1988013 ML20154J389 ML20154J397
References
50-338-88-13, 50-339-88-13, NUDOCS 8809230014
Download: ML20154J397 (1)

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ENCLOSURE 1

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NOTICE OF VIOLATION I

Virginia Electric and Power Company Docket Nos. 50-388,339 North Anna License Nos. NPF-4,7 l

During the Nuclear Regulatory Comission (NRC) inspection conducted on July 18-22, 1988, 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 (1987), the violation is listed l

below:

i Technical Specification 6.8.1.f requires written procedures to be

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established, implemented, and maintained for the fire grotection program.

f Section 4.1.1.d Plant Standard STD-GN-0021, Appendix R" Design Guide-lines, requires any potential concerns related to fire protection or compliance with Appendix "R" to 10 CFR 50 to be identified on an t

Appendix "R" Design Checklist for all Design Change Packages (DCPs).

t Contrary to the above, the requirements of Section 4.1.1 of STD-GN-0021 l

were not implemented for DCPs 87-01 and 87-02.

The preparing ongineers for these two DCPs failed to perform an adequate evaluation of the impact i

of the design changes on compliance with Appendix R.

DCPs 87-01 and 87-02 relocated the solenoid operated valves (SOVs) associated with the steam l

inlet trip valves for the Unit 1 and Unit 2 Turbine Driven Auxiliary l

Feedwater Pumps from the Main Steam Valve House to the Quench Spray Punp House.

Plant procedures for a fire in the Control Room require the local operation of the SOVs in the Main Steam Yalve House; however, due to the l

inadequate evaluation the SOVs were relocated without initiating a revision to plant postfire safe shutdown procedures.

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This is a Severity level V violation (Supplement I).

FOR THE NUCLEAR REGULATORY COMMISSION l

i Alan R. Herdt, Chief i

Engineering Branch i

Division of Reactor Safety l

Dated at Atlanta, Georgia this Mtfayof 1988 l

A nm88a 888%e a

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