ML20090A118

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Responds to NRC Re Violations Noted in IE Insp Rept 50-220/84-05.Corrective Actions:All Items Identified as Having Not Been Surveyed at Time of Removal from Spent Fuel Pool Subsequently Surveyed
ML20090A118
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 06/12/1984
From: Mangan C
NIAGARA MOHAWK POWER CORP.
To: Martin T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20090A105 List:
References
NMP-8579, NUDOCS 8407110241
Download: ML20090A118 (3)


Text

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NIAGARA MOHAWK POWER CORPORATION NMP-8579 NIAGARA MOHAWK 300 ERIE BOULEVARD. WEST SYRACUSE. N. Y,13202 June 12, 1984 1

Mr. Thomas T. Martin, Director Division of Engineering and Technical Programs United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Re: Docket No. 50-220 Inspection Report 84-05

Dear Mr. Martin:

This refers to the routine Safety Inspection conducted by Mr. R. Nimitz of your staff on April 10-13, 1984, at Nine Mile Point Unit #1, Scriba, New York of activities authorized by NRC License No. DPR-63, and to the discussions of your findings held by Mr. Nimitz with Mr. T. Perkins of our staff at the conclusion of the inspection.

ITEM A Technical Specification 6.11 requires that procedures for personnel radiation protection be prepared and adhered to for all operations involving personnel radiation exposure.

1.

Radiation Protection Procedure RP-2, Revision 2, requires, in part, in Section 5.4 that the instructions on the radiation work permit (RWP) be strictly adhered to.

Radiation Work Permit No. 4209, dated April 11, 1984, requires that radiation protection personnel survey all items prior to removal from the reactor vessel or spent fuel pool.

Contrary to the above, during conduct of radiological operations under RWP4209 on April 11, 1984, at about 2:30 p.m., contaminated items including a television camera, lighting cable and low power range monitor (LPRM) handling tool cables were removed from the reactor vessel and were not surveyed.

2.

Radiation Protection Procedure RP-10, Revision 3, requires, in part, in Section 7.4 that the regulator for the Scott Full Face Respirator with airline be set at 75 + 5 psig.

Contrary to the above, on April 11, 1984, at about 3:30 p.m.,

two individuals, cleaning reactor stud bolts on the refueling floor, were using Scott Full Face Respirators with airlines with the regulator set at 100 psig.

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1 Page 2 Inspection Report 84-05 RES PONSE ITEM A-1 Due to an oversight on the part of a limited number of personnel on the refuel floor, some contaminated items including a television camera, lighting cable and LPRM handling tool cables were removed from the spent fuel pool and were not promptly surveyed, during the conduct of operations under RWP 4209 on April 11, 1984, at about 2:30 p.m.

On April 11, 1984, all items identified by Mr. Nimitz as having not been surveyed at the time of removal from the spent fuel pool were subsequently surveyed, and all were found to have no abnormal activity.

The following corrective action was taken to reduce the chance of another violation of this type occurring in the future.

Immediately after learning of the violation, the Station Shift Supervisor on duty went to the refueling floor to discuss with the operating shift, which was to start working on the LPRM's, the importance of having the Radiation Protection Technicians monitor anything coming out of the water on the refuel floor.

Following this action, the Operations Supervisor held a meeting with the shif t involved with the LPRM replacement incident to stress the importance of proper monitoring. Also, the night orders of 4/12/84 stressed to all Operations Department personnel the importance of properly monitoring anything coming out of the water on the 340' elevation.

These actions were documented by Nonconformance Event Transmittal 84-85, in accordance with station procedures.

ITEM A-2 Two individuals cleaning reactor stud bolts on the refueling floor were using Scott Full Face Respirators with airlines with the regulator set at 100 psig.

Corrective action taken by Radiation Protection Technician was to adjust the pressure to the 75 psig i 5 psig requirement.

Follow-up corrective action was the sending of a memorandum to the Radiation Protection Technicians which reminded them of their responsibility to monitor usage of respiratory equipment so as to assure compliance with the requirements of procedures, and to reduce the chances of another violation of this nature from occurring.

W Page 3 Inspection Report 84-05 Additional action to prevent further violation consisted of incorporation of the details and corrective actions involved in this violation in a Feedback to Training memorandum for review with the General Ehiployee Training instructors for emphasis in their training sessions.

Very truly yours, C. V. Mangan Vice President Nuclear Engineering and Licensing CVM/cma n) c.

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