IR 05000309/1985026

Safety Insp Rept 50-309/85-26 on 850910-13.No Violation Noted.Major Areas Inspected:Radiation Protection Program During Outage,Including External Dosimetry,Outstanding Items,Training,Surveys & Exposure Control

ML20138C799
Person / Time
Site:	Maine Yankee
Issue date:	10/17/1985
From:	Clemons P, Shanbaky M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20138C779	List: IR 05000309/1985026 ML20138C775
References
50-309-85-26, NUDOCS 8510230047
Download: ML20138C799 (4)

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U.S. NUCLEAR REGULATORY COMMISSION

REGION I

Report N /85-26 Docket N License No. DPR-36 Priority -

Category C

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Licensee: Maine Yankee Atomic Power Company 83 Edison Drive Augusta, Maine 04336 Facility Name: Maine Yankee Nuclear Generating Station Inspection At: Wiscasset, Maine Inspection Conducted: September 10-13, 1985

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Inspectors: /p!/[ .I Fercy Clemons, Radiation Specialist date'

Approved by: S /),/ # C M.~ Shanbaky, Chief ~ 9 dat PWR Radiation Safety Section Inspection Summary:

Inspection on September 10-13, 1985 (Report No. 50-309/85-26

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Areas Inspected: Routine, unannounced safety inspection of the Radiation Protection Program during an outage including; external dosimetry, outstanding items, training, surveys, exposure control and procedure review. This inspec-

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tion involved 38 inspector hours on site by one regionally-based inspecto Results: No violations were identified.

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s i DETAILS

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1.0 Persons Contacte'd'

, 1, .1 Licensee Personnel

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J. -Garrity, Plant Manager D. Sturniolo, Principal Radiological Engineer G. Cochrane, Radiological Controls Section Head

R. Crosby, Quality Assurance Section Head

S. Evans, Licensing Eng%eer

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G. Pillsbury, Assistant to Technical Support Department Manager

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'1.2 NRC Fersonnel s

C. Holden, Senior Resident Insp.ector J. Robertson, Resident Inspector Other licensee and contractor employees were contacted and interviewed during this inspectio l 2.0 j>urpose '

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The purpose of this routine safety inspection was to review the performance of the licensee's radiation protection program during the i 1965 refueling outage with respect to the-following elements:

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procedure: review;

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external dosimetry program;

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training of licensee personnel;

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exposure control; and

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survey '

3.0 Status of Previous Inspection Findings i

(Closed) Violation (309/84-26-01) Failure to follow the requirements of l the Certificate of Compliance (C of C) inasmuch as the licensee did not have cepf es of all drawings referenced in the C of C. The inspector determined that the licensee has copies of all drawings referenced by the C of C.

(Closed) Inspector Follow-up Item (309/84-26-03) Check record keeping on

source inventory and leak test. .The' licensee's records on source i

t'nventory and leak tests were reviewed and found to be acceptable.

L 4.0 External Dosimetry Program The licensee's external dosimetry program was reviewed with respect to .

l' the criteria contained in 10 CFR 20,." Standards For Protection Against Radiation."

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The licensee's implementation of the external dosimetry program was evaluated by the.following methods:

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Interviews of the dosimetry staff; and

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Review of dosimetry records for selected personnel.

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Within the scope of this review, no violations were identified, i 5.0 Training

The licensee's program for providing general employee training for personnel

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was reviewed against criteria contained in 10 CFR 19,12 " Instructions to workers". The. licensee's performance in this area was evaluated by the following methods:

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interviews of training department staff; and

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review of general employee training records for selected radiation

workers.

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Within.the scope of this review, no violations were identified.

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6.0 Surveys

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The licensee's survey program was reviewed against the criteria contained in 10 CFR 20.201, " Surveys". The licensee's performance relative to j these criteria was determined by discussions with a Radiological Control

Foreman and by reviewing record The licensee's surveys appeared to have been conducted in a timely and 1 thorough manner.

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l Within the scope of this review, no violations were identified.

l 7.0 Procedure Review l

The adequacy and effectiveness of the licensee's procedures were reviewed against the criteria contained in Technical Specification 5.8, " Procedures".

The licensee performance relative to these criteria was determined by

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interviewing a_Radiologica1 Control Foreman, reviewing a sample of

. procedures, and by observing ongoing operation Procedures reviewed included:

Procedure No. 9.1.10, " Radiation Work Permits";

Procedure No. 9.1.11, " Radiation Protection Procedure for Refueling Outages"; and Procedure No. 9.1.12, " Issuance and Use of Personnel Monitoring Devices".

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o -4-The licensee's procedures reviewed were adequately detailed and had been reviewed periodically as require Within the scope of this review, no violations were identifie .0 Exposure Control The licensee's Program for area posting and control was reviewed against 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 Areas and from discussions with the staff member Within the scope of this review, no violations were identifie .0 Exit Interview The inspector met with licensee representatives (denoted in paragraph 1)

at the conclusion of the inspection on September 13, 1985. The inspector summarized the scope of the inspection and the finding At no time during this inspection was written material provided to the licensee by the inspector.

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