ML20215C100

Notice of Violation from Insp on 860706-0805

ML20215C100
Person / Time
Site:	Sequoyah
Issue date:	09/26/1986
From:	Zech G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20215C092	List: ML20215C088 ML20215C100 ML20215C112
References
50-327-86-42, 50-328-86-42, NUDOCS 8610100087
Download: ML20215C100 (2)

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3 ENCLOSURE 1

' s NOTICE OF VIOLATION Tennessee Valley Authority Docket Nos. 50-327 and 50-328 Sequoyah Units 1 and 2 License Nos. DPR-77 and DPR-79 ,

The following violations were identified during an inspection conducted on July 6 - August 5,1986. The severity levels were assigned in accordance

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with NRC Enforcement Policy (10 CFR Part 2 Appendix C).

A. Technical Specification 6.8.1 states that written procedures shall be established, implemented and maintained covering the maintenance of safety related equipment. Standard Practice SQA-119 establishes the procedure to implement a PORC approved temporary alteration to a safety related system.

The standards established for the temporary alteration and the Unreviewed Safety Question Determination are documented in a Temporary Alteration Change Form (TACF). TACF 0-85-097-234 established the standard for the total amount of wattage applied by a replacement heat trace tape in a safety related portion of the Chemical Volume Control System.

i Contrary to the above, Work Requests A-529926 and A-539170, among others, did not adequately control the configuration of replacement heat trace tape application. This resulted in a condition where the wattage requirements of TACF 0-85-097-234 were not complied with.

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

B. 10 CFR 50, Appendix B, Criterion V, requires that activities affecting quality shall be prescribed by procedures of a type appropriate to the circumstances and shall be accomplished in accordance with these procedures.

l 1. Sequoyah Nuclear Plant Construction Procedure P-30, Rev.1, "Fabri-i cation and Installation of Seismic Supports," requires that a support variance sheet be used to alter an existing typical support drawing and shall be applicable to one specific support at a specified location.

Contrary to the above, this procedure was not implemented in that

, solenoid valve 1-FSV-63-42 was mounted in a way which did not conform

! to the specifications of the typical drawing, and a support variance sheet was not used.

2. Administrative Instruction 19, Rev. 12, " Plant Modifications After Licensing," was established to provide that work instructions shall give a step-by-step sequence of events required to perform the work correctly and that the procedure identify the results of improper action.  ;

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• Tenne'ssee Valley Authority 2 Contrary to the above, this procedure was not implemented in that Work Plan 11806 did not give adequate instructions for craft personnel to reconfigure 10 CFR 50.49 qualified ASCO solenoid valves for proper installation and tiid not give the results of improper actions asso-ciated with modifying the valves.

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

Pursuant to 10 CFR 2.201, you are required to submit to this office within 30 days of the date of this Notice, a written statement or explanation in reply, including: (1) admission or denial of the alleged violations; (2) the reasons for the violations if admitted; (3) the corrective steps which have been taken and the results achieved; (4) corrective steps which will be taken to avoid further violations; and, (5) the date when full compliance will be achieved.

Security of safeguards information should be submitted as an enclosure to facilitate withholding it from public disclosure as required by 10 CFR 2.790 (d) or 10 CFR 73.21.

FOR THE NUCLEAR REGULATORY COMMISSION f -,

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Gary G.--I ch,hc or TVA Projects Datem 4' gia this 26 . September 1986

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