ML19256D045
| ML19256D045 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/17/1974 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19256D033 | List: |
| References | |
| 50-289-74-35, NUDOCS 7910160770 | |
| Download: ML19256D045 (2) | |
Text
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ENCLOSURE DESCRIPTION OF VIOLATIONS Metropolitan Edison Company Docket No. 50-289 License Nn. DPR-50 Certain activities under your license appear to be _. violation of AEC requirements. These violations are considered to be of Category II and Category III severity.
Category II Violation 1.
Technical Specification 3.5.2.4.b.1 states in part:
"Within a period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, the quadrant power tilt shall be reduced to less than 4 percent..., or the following adjustments in set-points and limits shall be made:
1.
The protection system reactor power / imbalance envelope trip setpoints shall ha reduced 2 percent in power for eacit 1 percent tilt."
10 CFR 50.36(c)(2) states in part: "When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action per-mitted by the technical Specification until the condition can be met."
Contrary to the above, facility records indicated that fol-loving the dropped rod occurrence on November 17, 1974 which produced a quadrant power tilt in excess of 4 percent, the tilt was not reduced below the required limit or the reactor power /
imbalance trip setpoints were not reduced to the required set-point within the required period of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Actual trip set-point adjustments for the 4 channels were accomplished over a period of about 6-10 hours following the existence vr the ex-
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cessive tilt condition. Additionally, when Technical Specifi-cation 3.5.2.4.b.1 (a limiting condition for operation) could not be met, the reactor was not shutdown in a time period commensurate with the above requirements, i.e.,
after reducing trip setpoints to the extent capable by design, but which were still in excess of the required limit, reactor operation con-tinued for about 5.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> before a shutdown was initiated.
(Nonroutine Report 74-06, Telegram to RO:I dated November 18, 1974 and Met Ed letter dated November 29, 1974).
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Category III Violation 2.
Technical Specification 6.7.2.a.4 states: " Events requiring notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone or telegraph to the Director of Regulatory Operations, Region I, followed by a written report within 10 days to the Director, Directorate of Licensing, USAEC, Washington, D.C.
20545; with a copy to tha Director of the Regional Regulatory Operations Office, shall include:
4.
Incidents or conditions which prevented or could have pre-vented the performance of the intended safety function of an engineered safety feature or of the reactor protection system,"
Contrary to the above, the premature tripping of the 1B Engin-eered Safeguards Motor Control Center feeder breaker due to a faulty overcurrent trip device, which was corrected by Work Request No. 5213 completed on November 6,1974, was not re-ported to the AEC, as required.
We note that subsequent to this inspection, you reported this occurrence as A0 74-26 (Telegram to RO:I dated December 2,1974 and Met Ed letter dated December 10, 1974.)
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