IR 05000309/1985017

Insp Rept 50-309/85-17 on 850812-16.No Violation Noted.Major Areas Inspected:Radiation Protection Program,Including Training & Qualification of Contractor Personnel,Posting & Labeling & Respiratory Protection

ML20132D734
Person / Time
Site:	Maine Yankee
Issue date:	09/06/1985
From:	Clemons P, Shanbaky M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20132D720	List: IR 05000309/1985017 ML20132D716
References
50-309-85-17, NUDOCS 8509300275
Download: ML20132D734 (4)

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l U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /85-17 Docket N License N DPR-36 Priority --

Category C Licensee: Maine Yankee Atomic Power Company

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83 Edison Drive Augusta, Maine, 04336 Facility Name: Maine Yankee Nuclear Generating Station Inspection At: Wiscasset, Maine Inspection Conducted: August 12-16, 1985 Inspector: Nhd P. Clemons, Radiation Specialist f/dddte .5 Approved by: e_ _ 9,(2?,.ze j M $

M. Shanbaky, Chief, PWJif' '

date Radiation Safety Section Inspection Summary: Inspection on August 12-16, 1985 (Report No. 50-309/85-17).

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Areas Inspected: Routine, unannounced pre-outage safety inspection of the Radiation Protection Program including: training and qualification of con-tractor personnel, planning and preparation, posting and labeling, respiratory protection, and the low level waste storage facility. This inspection involved 33 inspector hours on site by one regionally based inspecto Results: No violations were identifie ,.

8509300275 850924 PDR ADOCK 05000309 G- PDR

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DETAILS 1.0 Persons Contacted  !

1.1 Licensee Personnel J. Garrity, Plant Manager E. Boulette,. Assistant Plant Manager / Manager Technical Support G. Whittier, Manager, Nuclear Engineering and Licensing G.~Cochrane, Radiological Control Section Head

' G. Pillsbury, Assistant to Manager, Technical Support R. Cosby, Quality Assurance Section Head

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1.2 NRC Personnel C. Holden, Senior Resident Inspector K. Ferlic, Project Engineer Other licensee employees were contacted and interviewed during this inspectio .0 Purpose The purpose of this routine pre-outage inspection was to review the licensee's radiation protection activities with respect to the following elements:

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Review of training and qualifications of contractor personnel;

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Review of planning and preparation;

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Review of posting and labeling;

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Review of low level waste storage facility; and

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Review of respiratory protectio '3.0 Selection, Training and Qualification of Contractor Personnel The licensee's selection, qualification, and training of contractor personnel for this outage were reviewed against criteria contained in 10 CFR 19.12, " Instructions to Workers", and ANSI 18.1 - 1971, "Selec-

~ tion and Training of Nuclear Power Plant Personnel".

l The, licensee performance relative to these criteria was det7 eined by l

discussion with the Indoctrination Coordinator, the Assistant to the Manager, Technical Support, the Contractor Site Coordinator, and by reviewing record '

Within the scope of this review, the following was identifie .The licensee intends to employ about forty people in the Radiation Control Section and the Instrument and Control Group. Three of the contractors will be Supervisors; about twenty of the contractors will be

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2 Senior Radiation Control Technicians, and the remainder will be Junior Technicians, Instrument Repair Technicians, and Clerks. The licensee has also added personnel to its contractor Security Forc At the time of this inspection, most of the contractor radiation safety personnel were onsite, and the documentation reviewed indicated that the contractor personnel had successfully completed the licensee's qualifi-cation requirement The inspector determined that the licensee does not provide actual " hands-on" training in the practical factors training provided to personnel. The practical factors training is " demonstrated" to personnel. The inspector was informed by a licensee representative that the training program will be revised to include the actual " hands-on" training. This item will be reviewed in a subsequent inspection (309/85-17-01).

Within the scope of this review, no violations were identifie .0 Planning and Preparation The licensee's efforts in advanced planning and preparation for the upcoming outage were reviewed against the criteria contained in-10 CFR 20.101,

" Surveys", Regulatory Guide 8.8," Information Relevant To Ensuring That Occupational Radiation Exposures At Nuclear Power Stations Will Be As Is Reasonab1;,, Achievable", and Regulatory Guide 8.10 " Operating Philosophy For Maintaining Occupational Radiation Exposures As Low As Reasonably Achievable."

The licensees performance relative to these criteria was determined by discussions with a Radiological Control Specialist, and by reviewing document The major tasks reviewed included: Replacing reactor coolant pump motor; i Steam generator sludge lancing / sludge removal; Steam generator eddy current testing; Valve repacking and repair; and Steam generator nozzle dam installation and remova '

.It is apparent that the Radiological Control ALARA group has been exten-sively involved in the outage planning and preparatio Within the scope of this review, no violations were identifie .0 Posting and Labeling The licensee's program for area posting and control was reviewed against

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the criteria in 10 CFR 20.203, " Caution signs, labels, signals and controls."

The licensee's performance relative to these criteria was determined from a tour of the Controlled Area, and from discussions with staff member Within the scope of this review, no violations.were identifie .0. Low Level Waste Storage Facility The licensee is constructing a facility for the storage of low level

. radioactive waste at its Wiscasset, Maine sit The facility is located outside of the Protected Area,-but within the Owner Controlled Area. The facility is designed for the storage of waste, assuming the generation rates for five years, based on actual historical data covering a five year period. The facility will be completed during the Fall of 198 The waste stored in the facility will be dry active waste in 55 gallon drums or 4' x 4' x 8' containers, and waste that has been solidified in liner Within the scope of this review, no violations were identifie .0 Exit Iz.*.erview The inspector met with licensee representatives (denoted in paragraph 1)

at the conclusion of the inspection on August 16, 1985. the inspector summarized the purpose and scope of the inspection, and the inspectjon_

findings. At no time during this inspection was written material given to the license _ . . _ _ . . _ . . _ _ _ _ . . - . - - - _ . _ - - - _ - . . . _ - . . _ _ _ _ _ - _ _ - __-_w