ML20209F418

Notice of Violation from Insp on 860701-0811

ML20209F418
Person / Time
Site:	Vogtle
Issue date:	09/04/1986
From:	Walker R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20209F400	List: ML20209F395 ML20209F418 ML20209F472
References
50-424-86-60, 50-425-86-27, NUDOCS 8609120148
Download: ML20209F418 (2)

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2 ENCLOSURE I NOTICE OF VIOLATION Georgia Power Company Docket Nos. 50-424 and 50-425 Vogtle 1 and 2 License Nos. CPPR-108 and CPPR-109 .

During the Nuclear Regulatory Commission (NRC) inspection conducted on July 1 - /

August 11, 1986, a violation of NRC requirements was identified. The violation involved design control. In accordance with the " General Statement of Policy and

. Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the violation is listed below:

10 CFR 50, Appendix B, Criterion V, and the accepted Quality Assurance (QA)

Program (FSAR 17.1.5) collectively require that activities affecting quality be prescribed by documented instructions, procedures or drawings and be accomplished in accordance with these instructions, procedures, or drawings.

Contrary to the above, activities affecting quality were not adequately implemented in that NRC inspections conducted on July 15 & 16, 1986 revealed the following examples of inadequate implementation of design control.

1. P&ID 1XDB112 shows that direct position indication status for the Pressurizer Primary Safety Valves is to be provided on demand on the Emergency Response Facility (ERF) Computer and on the Plant Safety Monitoring System (PSMS) Computer. In addition, FSAR Table 7.5.2.1 indicates that the Pressurizer Primary Safety Valve position indication status is to be provided on the Plasma Display. However, neither the Bechtel Design Specification No. X5AH01 for the Post Accident Mont-toring System nor the Westinghouse Design Specification No. X6AZ02-18-1 for the PSMS specified the requirement that the function to display Pressurizer Primary Safety Valve position indication status be provided on the Plasma Display. Consequently, the function to display Pres-surizer Primary Safety Valve position indication status is presently not available on the Plasma Display.

2. Bechtel Desk Instruction PFE-X3DIO8, Revision 0 establishes the method for documenting and tracking Unit 1 design changes identified on Design Change Notices Resident, Field Change Requests (FCRs), and Deviation Reports, which are applicable to Unit 2 design. The design changes implemented on Unit I as reflected in FCR Nos. 14678, 14681, 14686, 14687, and 14688 attached to Operations Deviation Report No.

T-1-85-1810 were marked as not applicable to Unit 2 when, in fact, they j are applicable to Unit 2.

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8609120148 860904 PDR ADOCK 05000424 G PDR

2 Georgia Power Company 2 Docket Nos. 50-424 and 50-425 Vogtle 1 and 2 License Nos. CPPR-108 and CPPR-109 In summation, the implementation of design control was not adequate in that in the first example identified above, design criteria was omitted from the Bechtel Specification and, subsequently, was not part of the Westinghouse '

design criteria for Plasma Display. In the second example, design changes being implemented on Unit 1 via FCRs were found to be improperly evaluated as not applicable to Unit 2.

This is a Severity Level IV violation, two examples (Supplement II).

Pursuant to the provisions of 10 CFR 2.201, Georgia Power Company is hereby required to submit to this Office within 30 days of the date of this Notice, a written statement or explanation in reply including 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.

FOR THE NUCLEAR REG LATORY COMMISSION Roger D. Wal , Director

} Division of eactor Projects Dated at Atlanta, Georgia thistluday of g 1986