ML20212L239

Notice of Violation from Insp on 860601-0731

ML20212L239
Person / Time
Site:	Point Beach
Issue date:	08/08/1986
From:	Guldemond W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20212L226	List: IR 05000266/1986010 ML20212L222 ML20212L239
References
50-266-86-10, 50-301-86-09, 50-301-86-9, NUDOCS 8608250259
Download: ML20212L239 (2)

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l NOTICE OF VIOLATION Wisconsin Electric Power Company Docket No. 50-266 Docket No. 50-301 As a result of the inspection conducted from June 1 through July 31, 1986, and in accordance with the " General Policy and Procedures for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1985), the following violations were identified:

1. Technical Specification 15.6.8.1 states, in part, "The plant shall be operated and maintained in accordance with approved procedures. Major procedures, supported by appropriate minor procedures . . . shall be provided for the following operations where these operations involve nuclear safety of the plant: (1) Normal sequence of startup, operation and shutdown of components . . ."

Contrary to the above, on June 3,1986, at 10:31 a.m. an auxiliary operator attempted to return a white instrument bus inverter to service without the aid of a procedure. This action caused the complete loss of the white instrument buses for both units which resulted in a reactor trip and safety injection on Unit 1 and a five percent runback on Unit 2.

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

2. Technical Specification 15.3.10.D states, in part, "To increase power above 75% with an RCCA more than 7.5 inches indicated out of alignment with its bank demand position when the bank demand position is between 215 s,teps and 30 steps, an analysis shall first be made to determine the hot channel factors and the resulting allowable power level."

Contrary to the above, on June 5,1986, at approximately 4:40 a.m. , two control rods (K07 and C07) were found out of alignment from the bank demard position by greater than 7.5 inches. At the same time, the plant process computer indicated that total reactor power was 76%. On June 29, 1986, during the 2300 to 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> shift, power was increased above 80% without the operator recognizing that rod position deviation alarms were present and without performing the required hot channel factors analysis.

Rods K07 and C07 had an indicated misalignment of +8 inches between the demand position and rod position indication.

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

1 0608230259 860G00 PDR ADOCK 05000266 G PDR

Notice of Violation 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 Notice a written statement or explanation in reply, including for each violation: (1) corrective action taken and the results achieved; (2) corrective action to be taken to avoid further violations; and (3) the date when full compliance will be achieved.

Consideration may be given to extending your response time for good cause shown.

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Dated W. G. Guldemand, Chief WR Tfd ReactorProjectsBranch2 4

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