ML20211A967
| ML20211A967 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 02/04/1987 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20211A920 | List: |
| References | |
| 50-410-86-56, EA-87-009, EA-87-9, NUDOCS 8702190274 | |
| Download: ML20211A967 (2) | |
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NOTICE OF VIOLATION Niagara Mohawk Power Corporation License No. 50-410 Nine Mile Point, Unit 2 License No. NPF-54 EA 87-09 During an NRC inspection conducted between 0;tober 1 and November 16, 1986, NRC inspectors reviewed the circumstances associated with two violations of technical specification limiting conditions for operation (LCO) which were identified by the licensee and reported to the NRC.
Further, a third violation was identified by the inspector.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (Enforcement Policy) (1986), the violations are set forth below:
A.
Technical Specification LCO 3.9.2 requires that whenever the reactor is in the refueling mode, at least two Source Range lionitor (SRM) channels shall be operable and inserted to the normal operating level with one of the required SRM detectors located in the quadrant where core alterations are being performed and the other required SRM detector located in an
. adjacent quadrant.
If this LCO is not satisfied, the LCO Action Statement requires the immediate suspension of all operations involving core alterations.
Contrary to the above, between 7:08 p.m. and 11:58 p.m. on November 7, 1986, while the reactor was in the refueling mode, core alterations were made in the C quadrant involving the loading of 19 new fuel bundles into the reactor, and during that time, the SRM channel for the C quadrant was inoperable in that its reactor scram function had been bypassed.
This is a Severity Level IV Violation (Supplement I).
B.
Technical Specification Limiting Condition for Operation (LCO) 3.3.6.b and Table 3.3.6-1 require that whenever the reactor is in the refueling mode, a minimum of two Source Range Monitor (SRM) downscale Rod Block Monitor (RBM) channels per trip function shall be operable.
If none of these channels are operable, the Technical Specification LCO Action Statement requires that at least one of the inoperable channels must be placed in the tripped condition within one hour.
Contrary to the above, between 1:10 p.m. and 3:35 p.m. on November 4, 1986, while the reactor was in the refueling mode, all four SRM downscale rod block channels were inoperable, and during that time, none of these channels were placed in the tripped condition.
This is a Severity Level IV Violation (Supplement I).
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C.
10 CFR 50.72(b)(2)(ii) requires that the NRC be notified as soon as practical and in all cases, within four hours, of the occurrence of any event that results in the unplanned automatic actuation of the Reactor Protection System.
Contrary to the above, at 12:42 a.m. on November 5, 1986, a high water level in the scram discharge instrument volume actuated the Reactor Pro-tection System causing a reactor scram; however, the NRC was not notified of this unplanned actuation.
This is a Severity Level V violation.
(Supplement I)
Pursuant to the provisions of 10 CFR 2.201, Niagara Mohawk Power Corporation is hereby required to submit to this office within thirty days of the date of the letter which transmitted this Notice, a written statement or explanation in reply, including for each alleged violation:
(1) admission or denial of the violation; (2) the corrective steps which have been taken and the results achieved; (3) 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 this response time.
Dated at King of Prussia, Pennsylvania this day of February 1987
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