IR 05000626/2007026

Notice of Violation from Insp on 850626-0726

ML20134J723
Person / Time
Site:	Crystal River, 05000626
Issue date:	08/14/1985
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20134J714	List: IR 05000302/1985029 IR 05000626/2007026 ML20134J712
References
50-302-85-29, NUDOCS 8508290459
Download: ML20134J723 (2)

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l ENCLOSURE 1 l -NOTICE OF VIOLATION

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j Florida' Power Corporation Docket No. 50-302

Crystal River 3 License No. DPR-72

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- The .following , violations were identified during an inspection conducted on

, June 26 - July 26,1985. The Severity Levels were assigned.in accordance with theNRCEnforcementPolicy(10CFRPart2,AppendixC). . Technical Specification 6.8.1.j recuires adherence to the procedures-delineatedintheOffsiteDoseCalcu'ationManual(00CM).

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' The ODCM building (RB Rep)resentative Sampling purge exhaust funs Method to be operating No. 3.1-5 whenever bothrequires the . RBthe reactor personnel and equipment hatches are ope Contrary to the above. during the period from 10:20 a.m. on July 13, 1985, to 7:10 p.m. on July 15, 1985, the RB personnel and equipment hatches were open while the RB purge exhaust fans were inoperabl This is a Severity Level IV violation (Supplement I). Technical Specification 6.8.1.a requires adherence to procedures recommended in Appendix A of Regulatory Guide 1.33, November 197 Regulatory Guide 1.33, Appendix A requires administrative procedures for bypassing of' safety functions and jumper control, and requires procedures for performing maintenanc Compliance procedure CP-113, Handling and Controlling Work Requests and Work Packaps, requires electrical jumpers to be logged and independently verif< ed on Enclosure 5. Equipment Alteration Log, and requires that when work is complete, that the equipment be restored to the designed condition and independently verified. Procedure CP-113 also requires that equipment

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left in an altered condition following work must have an approved Modifica-tion Approval Recor Maintenance procedure MP-1088, Control Rod Drive Handling; Mechanical, requires verification that the reactor vessel water leve is between 2-6 inches below the reactor vessel flange prior to control rod drive installatio ,

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'- Florld'a Power Corporation Docket No. 50-302 Crystal River 3 2 License No. DPR-72

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Contrary to the above:

- On' July 11, 1985, a jumper was installed for troubleshooting in the control circuit for the "B" Emergency Diesel Generator Room Fan (AHF-22D)'without completion of the Equipment Alteration Lo This

. jumper was left in place following troubleshooting to allow for fan operation without the completion of a Modification Approval Record until July 12, 1985. ,

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- Between July 20-23, 1985, the control rod drive motor tubes were reinstalled with a reactor vessel level of 4 feet 2 inches below the

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reactor vessel flang This is a Severity Level IV violation (Supplement I). Technical Specification 4.9.2 requires a channel functional test of each l

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source range neutron flux monitor once per 7 day ;

Contrary to the above, durirg the period June 21 - July 4,1985, neither source range neutron flux monitor had been functionally tested, j ThisisaSeverityLevelIVviolation(SupplementI).

Pursuant to 10 CFR 2.201, you are required to submit to this office within 30 days of the date of this Notice, a written statement or explanation in reply, including: (1) admission or denial of the alleged violations; (2) the reasons for the violations if admitted; (3) the corrective steps which have been taken and the results achieved; (4) corrective steps which will be taken to avoid further violations; and (5) the date when full compliance will be achieve Security or safeguards information should be submitted as an enclosure to facilitate withholding it from public disclosure as required by 10 CFR 2.790(d)

or 10 CFR 73.2 ,

Date: M 141985 i