ML20148D834

Notice of Violation from Insp on 880208-12.Violation Noted: on 871112,entrance to Fuel Pool HX Room,High Radiation Area W/Levels Exceeding 1,000 M/H,Unlocked & Left Unattended

ML20148D834
Person / Time
Site:	Brunswick
Issue date:	03/16/1988
From:	Dan Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20148D819	List: ML20148D814 ML20148D834 ML20148D842
References
50-324-88-09, 50-324-88-9, 50-325-88-09, 50-325-88-9, NUDOCS 8803240345
Download: ML20148D834 (3)

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EHCLOSURE 1 NOTICE OF VIOLATION Carolina Power and Light Company Docket Hos. 50-325, 50-324 Bruncwick Plant License Nos. DPR-71, DPR-62 During the' Nuclear Regulatory Comission (NRC) inspection conducted on February 8-12, 1988, violations of NRC requirements were' identified. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1987), the violations are listed below:

A. Technical Specification 6.12.2 requires that each high radiation area, in which the intensity of radiation is greater than 1,000 millirem per hour, be provided with locked doors to prevent unauthorized entry into such areas.

Contrary to the above, on November 12, 1987, an auxiliary operator (A0) while performing daily rounds of plant systems unlocked the entrance to the Unit 2, 80 foot east fuel pool . heat exchanger room, a high radiation area with radiation levels in excess of 1,000 millirem per hour, and left the area unattended.

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

B. Technical Specification 6.8.1 requires that written procedures be established, implemented, and maintained covering the activities e recommended in Appendix A of Regulatory Guide 1.33, November 1972.

Regulatory Guide 1.33, Appendix A. Section 1.3, recommends that procedures for the repair or replacement of equipment be prepared; Section G.5 recommends that procedures for personnci radiation monitoring and special work permits be prepared; and Section 1.5.b recommends that factors be taken into account, including the necessity for minimizing radiation exposure to workmen, in preparing detailed procedures.

Technical Specification 6.11.1 requires that procedures for personnel radiation protection be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained, and adhered to for all operations involving radiation exposure.

Plant Procedure ENP-46, SRM/IRM Dry Tube Replacement, covers the removal, transfer, and storage of startup source range monitor dry tubes.

Radiation Control and Protection Procedure, Volume VIII, Section 6.6.2 requires that personnel dosimeters shall be worn at all times and that 8803240345 880316 PDR ADOCK 05000324 O DCD

Carolina Power and Light Company Docket Nos. 50-325, 50-324 Brunswick Plant 2 License Nos. DPR-71, DPR-62 self reading -pocket dosimeters should be c5 served at periodic intervals when working in radiation or high radiation areas.

Radiation Control and Protection Procedure, Volume VIII, Section 6.6.3 specifies that required items of protective clothing shall be worn by all personnel while in radiation controlled areas.

Contrary to the above, the licensee failed to establish adequate radiation protection procedures concerning handling of irradiated dry tubes and using personnel monitoring devices, and to adhere to a radiation control procedure in that:

1. On November 12, 1987, an auxiliary operator, while making daily rounds of plant systems, failed on two occasions to wear the required protective clothing while in radiation controlled areas.

2. On January 23, 1988, a licensee individual was preparing a feedwater nozzle for inservice inspection. The worker failed to monitor his self-reading pocket dosimeter (SRPD) during the time spent in the high radiation area and received an exposure of 800 millirem. Plant procedure VIII Section 6.6.2 was inadequate in that the procedure did not require the worker to frequently read his SRPD while working in a high radiation area.

3. On January 31, 1988, while transferring a startup source range monitor dry tube to a storage location in the spent fuel pool, a section of the dry tube broke the surface of the water (shielding) and exposed workers for a very short time period to high levels of radiation. Plant procedure ENP-46 used during the operation did not contain adequate instructions and precautionary steps to ensure that the dry tube remained under water and radiation exposure to personnel I were minimized.

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

Pursuant to the provisions of 10 CFR 2.201, Carolina Power and Light is hereby required t.o submit a written statement or explanation to the Nuclear Regulatory Comission, ATTN: Document Control Desk, Washington, DC 20555, with a copy to l the Regional Administrator, Region II, and a copy to the NRC Resident inspector, within 30 days of the date of the letter transmitting this Notice.

This reply should be clearly marked as a "hply to a Nc,tice of Violation" and should include for each violation: (1) admusion or denial of the 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 l extending the response time. If an adequate reply is not received within the 1

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Carolina Power and Light Company Docket Nos. 50-325, 50-324 Brunswick Plant 3 License Nos. DPR-71, DPR-62 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 C0!NISS10N lMN!

Douglas M. Collins, Chief Emergency Preparedness and Radiological Protection Branch Division of Radiation Safety and Safeguards Dated at Atlanta, Georgia this //,Aday of Marcn 1988 1

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