ML20245K033

Notice of Violation from Insp on 890603-0707.Violation Noted:On 890621,several Cells of Station Batteries a & B Had Electrolyte Levels Greater than Max Level Mark & Four Unqualified Personnel Assigned Duty on Fire Brigade

ML20245K033
Person / Time
Site:	Crystal River
Issue date:	08/01/1989
From:	Sinkule M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20245K029	List: ML20245K026 ML20245K033 ML20245K042
References
50-302-89-15, NUDOCS 8908180285
Download: ML20245K033 (2)

Text

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ENCLOSURE 1 NOTICE OF VIOLATION Florida Power Corporation Docket No. 50-302 Crystal River Unit 3 License No. DFR-72 During the Nuclear Regulatory Commission (NRC) inspection conducted on June 3 -

July 7, 1989, violations of NRC requirements were identified. In accordance with .l the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 i CFR Part 2, Appendix C, 53 Fed. Reg. 40019 (October 13,1988), the violations are i listed below. ,

1 A. Technical Specification (TS) 3.8.2.3 requires that the "A" and "B" Station Batteries be operable during power operation. Surveillance requirement 4.8.2.3.2.b.3 specifies that for a battery to be considered operable, the l

i electrolyte level of each connected cell must be between the minimum and maximum level indication-marks.

Contrary to the above, on June 21, 1989, with the plant operating at power, several- cells of the "A" Station Battery and several cells of the "B" Station Battery were observed to have electrolyte levels greater than the maximum level mark which rendered both station batteries inoperable.

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

B. TS 6.8.1 requires the implementation of written procedures for those activ-1 ities recommended in Appendix "A" of Regulatory Guide 1.33, November 1972, j and for implementation of the fire protection program.

Regulatory Guide 1.33, Appendix "A"Section I.3.d recommends procedures for the repair or replacement of reactor coolant pump seals.

Maintenance Procedure MP-165, Reactor Coolant Pump Seal Cartridge Removal and Replacement, step 7.2.24 requires that the adjusting cap of the seal be positioned against the pump half coupling.

Administrative Instruction AI-2205, Administration of CR-3 Fire Brigade Organization, Section 4.3, requires in part that the- fire brigade team be composed of four qualified fire brigade team members.

Contrary to the above:

1. On June 10, 1989, step 7.2.24 of procedure MP-165 was signed off as completed even though this step had not been performed. Not performing this step resulted in excessive leakage from a reactor coolant pump seal during a fill and vent of the reactor coolant system.

2. On June 18, 20 and 22, one of the four personnel assigned duty as a fire brigade team member was not qualified.

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

89081002B5 PDR ADOCK 05000*

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• 4 Florida Powdr Corporation 2 Docket No. 50-302 Crystal River Unit 3 License No. DPR-72 Pursuant to the provisions of 10 CFR 2.201, Florida Power Corporation is hereby required'to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN: - Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, Crystal River 3, within 30 days of the date of the letter transmitting this _ 1 Notice. This reply should'be clearly marked as a " Reply..to a Notice of Violation" and should -include for each violation: (1) admission or denial of the alleged violation, (2).the reason for the violation if admitted, (3) the corrective steps

'which have been'taken and the results achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved.. Where good cause is shown.. consideration will be 'given to extending the response time.- If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken.

FOR THE NUCLEAR REGULATORY COMMISSION-

0. s liM. V. Sinkule.

0(. K &wfA.

Reactor Projects Branch 2 Division of Reactor Projects l Dated at Atlanta, Georgia This 1st Day _of August 1989 1

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