ML20054K362

Notice of Violation from Insp on 811024-1202

ML20054K362
Person / Time
Site:	Crystal River
Issue date:	01/29/1982
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20054K339	List: IR 05000302/1981023 IR 05000302/1982023 ML20054K338 ML20054K343 ML20054K350 ML20054K354 ML20054K358 ML20054K359 ML20054K360 ML20054K362 ML20054K364
References
50-302-81-23, NUDOCS 8207010473
Download: ML20054K362 (2)

Text

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APPENDIX A NOTICE OF VIOLATION Florida Power Corporation Docket No. 50-302 Crystal River 3 License No. DPR-72 As a result of the inspection conducted on October 24 - December 2,1981, and in accordance with the Interim Enforcement Policy, 45 FR 66754 (October 7,1980),

the following violations were identified.

A. Technical Specification 4.3.1.1.1 requires a channel calibration of reactor coolant system (RCS) outlet temperature every 18 months.

Technical Specification Definition 1.9 requires a channel calibration to encompass the entire channel including the sensor.

Contrary to the above, as of November 12, 1981, the procedure used to calibrate RCS outlet temperature did not encompass the channel sensor (resistance temperature detector).

This is a Severity Level IV Violation (Supplement I.D.3.).

B. Technical Specification 6.8.1 requires the following of procedures that cover the activities listed in Appendix A of Regulatory Guide 1.33, 1972.

Regulatory Guide 1.33, Appendix A,1972 requires procedures for log entries and for operation of the shutdown cooling system.

Procedure AI-500, Conduct of Operations, requires adherence to the implementing procedures of the Operations Section Implementation flanual (OSIM). The OSIri, in section III.E.2. A and B requires log entries in the Nuclear Shift Supervisor's Log and the Nuclear Operator's Log for any unusual occurrences or unusual trends or conditions observed.

Procedure OP-404, Decay Heat Removal System (the facility's shutdown cooling system), requires the closure of the borated water storage tank suction valve (DHV-34) in paragraph 8.2.1.1 prior to starting the "A" decay heat train in paragraph 8.2.1.3.

. Contrary to the above, the following events occurred due to failure to

! fo.llow the OSIll and procedure OP-404:

(1) On October 1,1981, steam flashing in the hot legs of the reactor coolant system, an unusual occurrence and trend, was not logged in the Nuclear Shift Supervisor's Log nor the Nuclear Operator's Log.

(2) On November 6,1981 at 2013, the "A" decay heat train was started without closing the borated water storage tank suction valve (DHV-34).

7 8207010473 820618 PDR ADOCK 05000302 G PDR

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Florida Power Corporation 2 Docket No. 50-302 Notice of Violation License No. DPR-72 Failure to close this valve resulted in the overflow of approximately 1650 gallons of reactor coolant system water into the reactor building.

This is a Severity Level V Violation (Supplement I.E.).

C. Technical Specification 6.11. quires procedures prepared to meet the requirements of 10 CFR, Part 20 be adhered to for all activities involving personnel radiation exposure.

Chemistry and Radiation Protection Procedure, RP-101, section 4.8.2 requires:

1. An individual entering a contaminated area to wear proper clothing and devices necessary for contamination control.

2. ChemRad personnel are to be contacted to specify the clothing require-ments for entering a contaminated area covered by a standing radiation work permit (SRWP). RP-101, section 4.4 requires work t1 be conducted in a manner consistent with maintaining a minimum of conteination spread.

Contrary to the above, on December 1,1981 at approximately 1350, a person was observed in a contaminated area, covered by an SRWP, without consulting ChemRad personnel for clothing requirements and without the proper clothing requirements that would have been specified for the area. In addition, this person was observed leaving the contaminated area with a bundle of con-taminated rope without proper contamination controls (rope not bagged and/or gloves worn) resulting in contamination of the individual's hands of approximately 1000 dirintegrations per minute (DPli).

This is a Severity Level VI Violation (Supplement IV.5.).

Pursuant to the provisions of 10 CFR 2.201, you are hereby required to submit to '

this office within thirty days of the date of this Notice, a written statement or explanation in reply, including: (1) admission or denial of the alleged viola-tions; (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 achieved. Consideration may be given to extending your response time for good Cduse shown. Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation.

Date:

JAN 2 91982

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