ML20245A560

Notice of Violation from Insp on 890306-10.Violation Noted: Fire Hazards Analyses for Plant Mod Request 2206, Auxiliary Bldg Fire Protection Sys Did Not Include Consideration of Radiation Release Potential Under Stated Condition

ML20245A560
Person / Time
Site:	Wolf Creek
Issue date:	04/13/1989
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20245A556	List: IR 05000482/1989008 ML20245A554 ML20245A560
References
50-482-89-08, 50-482-89-8, NUDOCS 8904250270
Download: ML20245A560 (2)

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APPENDIX A NOTICE OF VIOLATION Wolf Creek Nuclear Operating Corporation Docket: 50-482 Wolf Creek Generating Stat 1on Operating License: NPF-42 During an NRC inspection corducted March 6-10, 1989, violations of NRC requirements were identified. The violations involved a failure to provide an adequate procedure, failure to conduct training for operators on a safety-related control board modification, and failure to conduct adequate test of the battery. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions,"

10 CFR Part 2. Appendix C (1988), the violatier;s are listed below:

A. Inadeouate Procedures Technical Specification 6.8.1 requires that written procedures shall be established, implemented, and maintained covering activity recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. The Regulatory Guide requires, in part, that tbare ha procedures covering the control of modification work for the plant fire protection program.

Procedure KGP-1131, Revision 6, " Plant Modification Process," requires that a fire hazard analysis be conducted for modifications to minim'ze and control the release of radioritive material to the environment.

Contrary to the above, the fire hazards analyses for Plant Modification Request 2206, " Auxiliary Building Fire Detection System " did not include in its fire hazards analysis consideration of the radiation release potential from the combustion of large amounts of radioactive contaminated material stored within the fire zones.

This is a Severity Level IV violation. (Supplements)(482/8908-01)

B. Failure to Train Operators in Plant Modifications The Code of Federal Regulations, 10 CFR Part 55.59, requires that licensed operators be cognizant of facility design changes.

Contrary to the above, information on a facility change, Plant Modification Request 02427, concerning emergency diesel generator controls, was not provided to all licensed operators prior to returning the modified equipment to service.

This is a Severity Level IV violation. (Supplement I) (482/8908-02)

C. Inadequate Testing Criterion XI of Appendix 10, 10 CFR Part 50, requires that there be a test program established and implemented to demonstrate acceptability in service of systems and components.

8904250270 890413 PDR ADOCK 05000482 o PNU

L Contrary to the above, the test of battery capacity conducted on October 15, 1987, did not demonstrate acceptability of the battery in that it did not account for a long test interruption, which affected the apparent battery capacity.

This is a Severity Level IV violation. (Supplement I) (482/8908-03)

Pursuant to the provisions of 10 CFR 2.201, Wolf Creek Generating Station is hereby 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 Violations A and B: (1) the reason for the violation if admitted t (2) the corrective steps which have been taken and the results achieved, (3) the corrective steps which will be taken to avoid further violations, and (4) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time.

No response is required for Violation C, in that your corrective actions were reviewed during the inspection (paragraph 2.2.7) and found to be acceptable.

Dated at Arlington, Texas, this gM day of Q g d 1989

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