IR 05000701/2008018

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Notice of Violation from Insp on 850701-0818
ML20133H399
Person / Time
Site: Oyster Creek, 05000701
Issue date: 10/07/1985
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20133H397 List:
References
50-219-85-23, NUDOCS 8510170150
Download: ML20133H399 (2)


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APPENDIX A NOTICE OF VIOLATION GPU Nuclear Corporation Docket No. 50-219 Oyster Creek Nuclear Generating Station License No. OPR-16 As a result of the inspection conducted on July 1 - August 18, 1985, and in accordance with the NRC Enforcement Policy (10 CFR 2, Appendix C), published in the Federal Register on March 8, 1984 (49 FR 8583), the following violations were identified: Technical Specification 6.8.1 requires, in part, that written procedures be established, implemented, and maintained. Station Procedure 700.2.014, "Backseating and Unbackseating Valves V-14-36, V-14-37, and V-16-1 (Electrically)," provides instructions for unbackseating a containment isolation valve without making the automatic isolation function inoperabl Contrary to the above, during a plant shutdown conducted on February 2, 1985, operators failed to follow procedure 700.2.014 while unbackseating a reactor water cleanup system containment isolation valve. This

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deviation from the procedure made the automatic isolation function of a containment isolation valve inoperable when it was required to be operabl This is a Severity Level IV violation (Supplement I). Technical Specification 6.8.1 requires, in part, that written procedures i be ,stablished, implemented and maintained. Station Procedure 312

" Reactor Containment Integrity and Atmosphere Control," provides detailed i instructions for the inerting of the drywell and torus. These instructions include: (1) a prerequisite to calibrate the drywell and torus oxygen analyzers, (2) instructions to use 150" of nitrogen from the nitrogen storage tank, (3) i note to inert until both drywell and torus are less than 3*4 oxygen, (4) instructions to ignore the oxygen analyzer ,

readings until they are ca',1brated with the containment less than 4'.

oxygen. Also, Station P Needure 201.2, " Plant Heatup to Hot Standby,"

and the Technical Spe::ifications require containment be inerted to less than 4*4 oxygen within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after placing the reactor in the RUN mod Contrary to the above, during a startup conducted on August 4, 1985, Station Procedures 312 and 201.2 were not fully adhered to in that: (1) a prerequisite which required an oxygen analyzer calibration was not completed prior to initiating inerting, (2) less than 150" of nitrogen i was utilized during inerting, (3) the drywell and torus were not inerted to less than 3*. oxygen, (4) specific instructions to ignore oxygen I

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l analyzer readings were not followed, and (5) operation was conducted 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after placing the mode switch in RUN with the drywell oxygen

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concentration at 4%.

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

Pursuant to the provisions of 10 CFR 2.201, GPU Nuclear Corporation is hereby required to submit to this office, within 30 days of the date of the letter which transmitted this Notice, a written statement or explanation in reply, including: (1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further violations; and (3) the date when full compliance vill be achieved. Where good cause is shown, consideration will be given to extending this response tim i