IR 07100020/2012030
| 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: |
| References | |
| 50-440-87-23, NUDOCS 8802050109 | |
| Download: ML20196A634 (1) | |
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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:
1.
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 psig.
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 test.
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 inoperable.
This is a Severity Level IV violation (Supplement I).
2.
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 hour.
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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 condition.
This is a Severity Level IV violation (Supplement 1).
With respect to item 1, the inspection showed that action had been taken to
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correct the identified violation and to prevent recurrence. Consequently, no reply to the violation is required and we have no further questions regarding this matter.
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With respect to item 2, pursuant to the provisions of 10 CFR 2.201, you are
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
achieved. Consideration may be given to extending your response time for good g
cause shown.
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Dated W. L. Forney, Chief Reactor Projects Branch (1 3