ML20247B006
| ML20247B006 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 08/31/1989 |
| From: | Liaw B Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20247B004 | List: |
| References | |
| 50-327-89-14, 50-328-89-14, NUDOCS 8909120304 | |
| Download: ML20247B006 (2) | |
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ENCLOSURE NOTICE OF VIOLATION i
Tennessee Valley Authority Docket Nos. 50-327 and 50-328 Sequoyah Units 1 and 2 License h.os. DPR-77 and DPR-79 During the Nuclear Regulatory Commission (NRC) inspection conducted from April 24, 1989 to April 28, 1989, a violation of NRC requirements was identified.
In accordance with the " General Statements of Policy and Procedures for NRC Enforce-ment Actions",10 CFR Part 2, Appendix C (1988), the violation is listed below:
Technical Specification 6.8.1 requires in part that written procedures shall be established, implemented and maintained covering the activities listed in Appendix A of Regulatory Guice 1.33, Revision 2.
Surveillance Instruction SI-3, Revision 50, approved September 4, 1986, limits the maximum voltage on the 6900 volt Class 1E busses at 7240 volts and the 480 volt busses at 504 volts. Corrective action is required by 51-3 at 7260 volts and 508 volts, respectively, to reduce the voltage to nominal values. The same maximum voltage limits and corrective action were included in SI-3, Revision 68, approved August 23, 1988.
This latest revision was in place on January 21, 1989.
General Operating Instruction G01-6, Revision 28, approvat September 16, 1986, page 23, includes maximum voltage limits for normal weration at 7240 volt for the 6900 volt system and 504 volt for the 480 volt system.
Corrective action is required by G01-6 at 7260 volts and 508 volts, respectively, to reduce the voltage to nominal values. The same maximum voltage limits and corrective action were included in G01-6, Revision 49, approved January 20, 1988. This latest revision was in place on j
January 21, 1989.
System Operating Instruction 501-55-0M26, XX-55-26B, Revision 5, page 14, approved June 24, 1985, requires an alarm setpoint at 105% (7245 volts) and also requires immediate action to reduce shutdown board voltage to nominal values when 7245 vo.ts is exceeded.
Contrary to the above, on January 21, 1989, during surveillance testing of emergency diesel generator 2A-A, the licensee failed to f ollow proce-l dures to reduce voltage at the shutoown board and the board voltage remained at 7400 volts, as determined by calibrated recorder (Visicorder) cha rts. The overvoltage condition was allowed to persist the following day, January 22, 1989, as evidenced by voltage recordings on page 140 of Surveil-lance Instruction SI-26.2A. This is a failure to follow procedures, SI-3, G01-6, and 501-55-0M-26, as required by Technical Specification 6.8.1.
l This is a Severity Level IV violation (Supplement I).
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Pursuant to the provisions of 10 CFR 2.201, Tennessee Valley Authority is hereby required to submit a written statement or explanation to the huclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555, with a copy to the Associate Director for Special Projects, Office of Nuclear Reactor Regulation, and a copy to the NRC Resident Inspector, Sequoyah, 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 including the contribution of the inadequate procedures, (3) the corrective steps 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 responte time.
FOR THf. NUCLEAR REGULATORY COMMISSION p,
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B'.1D.'da,W, Director TVA Projects Division Office of Nuclear Ra ctor Regulation Dated at Rockville, Maryland this 31st day of August 1989.
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