ML20239A588

Notice of Violation from Insp on 870615-0731.Violation Noted:Failure to Follow Work Requests B297733 & B230619 to Obtain & Verify Stuffing Box Dimensions

ML20239A588
Person / Time
Site:	Sequoyah
Issue date:	09/09/1987
From:	Zech G NRC OFFICE OF SPECIAL PROJECTS
To:
Shared Package
ML20239A579	List: IR 05000327/1987037 ML20239A578 ML20239A588
References
50-328-87-37, NUDOCS 8709170500
Download: ML20239A588 (2)

Text

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ENCLOSURE 1 NOTICE OF VIOLATION Tennessee Valley Authority Docket No. 50-328 Sequoyah Nuclear Plant License No. 'OPR-79 During the Nuclear Regulatory Commission (NRC) inspection conducted on June 15 - July 31,1987, a violation of NRC requirements was identified. The violation involved three examples of failure to follow approved plant procedures. 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 below:

Technical Specification 6.8.1 requires that written procedures be implemented covering the applicable procedures recommended in Appendix "A" of Regulatory Guide 1.23, Revision 2, February 1978. Appendix "A" of Regulatory Guide 1.33 states that maintenance that can affect the performance of safety-related equipment should be performed in accordance with documented instructions. Work Requests (WRs) B297733 and B230619 provide the instructions for repacking valves 2-VLV-070-680 and 2-FCV-063-0005, respectively. The repacking steps are in both cases specified in MI-11.4, Maintenance of CSSC Valves, Rev. 19. MI-11.4 requires that the inside diameter of the stuffing box and the outside diameter of the stem or shaft be measured and that the dimensions obtained be verified within +/- 1/64 inch of the packing ring dimensions. This requirement is contained in steps 6.10.9.2 and 6.10.9.3 for valves with graphite packing such as 2-VLV-070-680 (WR B297733) and in step 6.10.6.2 and 6.10.6.3 for valves with split ring packing such as 2-FCV-63-0005 (WR B230619). MI-11.4 also requires, in step 6.9.2, that a Quality Control (QC) inspector verify the lubricant type if a valve stem is lubricated during maintenance.

Contrary to the above, the licensee failed to follow WRs B297733 and B230619 in that the stuffing box dimensions were not obtained and verified to be within +/- 1/64 inch of the packing ring dimensions as requi red by MI-11.4. In addition, during the performance of WR B230619, a lubricant was applied to the stem of valve 2-FCV-63-005. The type of lubricant used was not verified by QC as required by MI-11.4.

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

Pursuant to the provisians of 10 CFR 2.201, the Tennessee Valley Authority is hereoy required to submit to this Office within 30 days of the date of the letter transmitting this Notice a written statement or explanation in reply including: (1) admission or denial of the vioiation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken and the 8709170500 870909 PDR ADOCK 05000327 O PDR

Tennessee Valley Authority 2 Docket No. 50-328 Sequoyah Nuclear Plant License No. DPR-79 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.

4 FOR THE NUCLEAR REGULATORY COMMISSION f/ 'o .c Gary G. Eech, A stant Director, Inspection Programs TVA Projects Division l l Office of Special Projects D3ted at Atlanta, Georgia this 9th day of September 1987 i

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