ML20196E204

Notice of Violation from Insp on 880916-1021.Violation Noted:Procedure MP-101 Inadequate in That Procedure Did Not Require Sys Leak Test Be Conducted at Normal Operating Pressure Following Replacement of Thermowell in RCS

ML20196E204
Person / Time
Site:	Crystal River
Issue date:	11/21/1988
From:	Wilson B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20196E200	List: IR 05000302/1988029 ML20196E195 ML20196E204
References
50-302-88-29, NUDOCS 8812090291
Download: ML20196E204 (2)

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ENCLOSURE  !

NOTICE OF VIOLATION Florida Power Corporation Docket No. 50-302 Crystal River Unit 3. License No. OPR-72 During' the Nuclear Regulatory Commission (NRC) inspection conducted on f September 16 - October. 21, 1988, violations of NRC requirements were identi- ,

fled. In accordance with the "General Statenent of Policy and Procedure for t NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1988), the violations are listed below:

A. Technical. Specifications (TS) 6.8.1.a requiras that procedures established  !

as recommended in Appendix "A" of Regulatory Guide 1.33, November 1972, be adequate for the cause.

Regulatory Guide 1.33, Appendix "A",Section I.3, recommends the estab-lishment of procedures for.the repair or replacement of equipment.

Maintenance procedure MP-101, Removal and Replacement of Reactor Coolant System RTDs and Thermowells, was written to meet the requirements of Regulatory Guide 1.33 and specifies in section 8 the post maintenance  ;

testing required after RTD and thermowell replacement.

Contrary to the above, on October 20, 1988, procedure MP-101 was found to be inadequate in that this procedure did not require that a system leak test be conducted ct normal operating pressure following the replacement of a thermowell in the reactor coolant system.

This is a Severity Lriel IV Violation (Supplemen I).

8. TS 3.8.2.3 states:

The following 0.C. bus trains shall be energized and operable: Train dB" consisting of 250/125 volt 0.C. bus No. 3B, 250/125 volt 0.C. battery bank No. 3B, and two Slit capacity chargers. Applicability Modes 1, 2, 3, and 4.

Action: b. With one 250/125 volt D.C. battery and/or a charger inoperable, restore the inoperable battery and/or charger to operable status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> or be in at least hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

8812090291 08))pj gDR ADOCK 05000302 PNU

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Florida Po*er w Corporation 2 Docket No. 50-302 Crystal River Unit 3 License No. DPR-72 Contrary to the above, from 0753 on Saptember 17, 1988 until 0323 September 18, 1988, Crystal River Unit 3 was operated in Mode 1 with "B" battery charger in the "B" train inoperable and the "F" (swing) charger paralleled with the "D" charger. This alignment was equivalent to only one operable 50% capacity battery charger in the "B" train. The action statement for TS 3.8.2.3 was not entered. The misalignment of the "B" train battery chargers occurred when clearance 88-09-71 was issued and improperly executed. The misalignment was not recognized until the clearance was restored.

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

C. TS 6.8.1.c states that written procedures shall be established, implemented and maintained covering surveillance and test activities of safety related equipment.

- Contrary to the above, on October 14, 1988, with the plant in the cold shutdown condition, procedure SP-132, Engineered Safeguards Channel Calibration, was not properly implemented in that a second channel cali-

! bration was started prior to completion of the previous channel. This action resulted in an inadvertent actuation of the Engineered Safeguards System.

! This is a Severity level IV Violation (Supplement I).

1 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 Fegional Administrator Region II, and a copy to the NRC Resident Inspector, trystal River, within 30 days of the d.tte of the letter transmitting t.hi s Motice. This recly should be clearly marked as a "Reply to a Notice of

Violation" and should include for each vielation

(1) admission or dental of the alleged violation, (2) the reason for the viol A(, ion if admitted, (3) the corrective steps which have been taken and the results achieved, (4) the corrective steps wh1ch will be taken to avoid further violations, and (5) the date when full cwpliance will be achieved. Where good cause is shown, c m

!' sideration will be given to extending the response time. If an adequate reply is not received within the time specified ir, this Notice, an order may be issued to show cause why the license should not be modified, suspended, or j reveked or why such other action as may be proper should not be taken.

FOR THE NUCLEAR REGULATORY COMMISSION g -

m uce A. Wilson, Chief eactor Projects Branch 2 Division of Reactor Projr. cts Dated at Atlanta, Georgia thisib r day of November 1988