IR 07100020/2012030

Notice of Violation from Insp on 871020-1230.Violations Noted:On 871114,during Plant Startup,Reactor Pressure Increased Above 150 Psig with RCIC Sys in Secured Status

ML20196A634
Person / Time
Site:	Perry, 07100020
Issue date:	02/02/1988
From:	Forney W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20196A624	List: IR 05000440/1987023 IR 07100020/2012030 ML20196A620
References
50-440-87-23, NUDOCS 8802050109
Download: ML20196A634 (1)

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NOTICE OF VIOLATION

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The Cleveland Electric Illuminating License No. NPF-58 Company

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As a result of the inspection conducted on October 20, 1987 through December 30, 1987, and in accordance with the "General Policy and Procedures for NRC Enforcement Action," 10 CFR 2, Appendix C (1985), the following violations were identified: Technical Specification 3.7.3 requires, in part, that the Reactor Core Isolation Cooling (RCIC) system be operable in Operational Condition 1, 2, and 3 with reactor steam dome pressure greater than 150 psi Exception to the requirements of Technical Specification 4.0.4 is granted, provided that the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the tes Contrary to the above, during a plant startup on November 14, 1987, while in Operational Condition 2 reactor pressure was increased above 150 psig with the RCIC system in secured status. In secured status, the RCIC system was inoperabl This is a Severity Level IV violation (Supplement I). Technical Specification 3.3.1 requires, in part, that with the number of operable intermediate range neutron monitoring system channels less than required by the minimum operable channels per trip system requirement for one trip system, place the inoperable channels and/or that trip system in the tripped condition within one hou ,

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Contrary to the above, on July 3, 4, and 5, 1987, while in Operational Condition 4, the minimum operable channels per trip system requirements for one trip system were not met for periods in exesss of one hour while neither the inoperable channels nor the associated trip system were placed in a tripped conditio This is a Severity Level IV violation (Supplement 1).

With respect to item 1, the inspection showed that action had been taken to ,

correct the identified violation and to prevent recurrence. Consequently, no reply to the violation is required and we have no further questions regarding g this matte O' With respect to item 2, pursuant to the provisions of 10 CFR 2.201, you are 8 required to submit to this office within thirty days of the date of this to Notice a written statement or explanation in reply, including: (1) corrective gz action taken and the results achieved; (2) corrective action to be taken to y' avoid further violations; and (3) the date when full compliance will be h

g achieved. Consideration may be given to extending your response time for good cause show .

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FEB t Dated Q'A L W. L. Forney, Chief

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Reactor Projects Branch (1 3