IR 05000309/1986009
| ML20203E324 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 07/16/1986 |
| From: | Clemons P, Kaminski M, Shanbaky M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20203E297 | List: |
| References | |
| 50-309-86-09, 50-309-86-9, NUDOCS 8607240129 | |
| Download: ML20203E324 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-309/86-09 Docket No.
50-309 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 Stat;on Inspection At: Wiscasset, Maine
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Inspection Conducted: June 2-6, 1986 Inspectors:
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/6[?6 pP. Clemons, Radiation Specialist
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gl&leb M. Kaminski, Radiation Specialist
' date Approved by:
M 78//k'd M. Shanbat9,' Chief, Pac 111 ties Radiation date Protection Section, Emergency Preparedness and Radiological Protection Branch Inspection Summary:
Inspection on June 2-6, 1986, (Report No. 50-309/86-09).
Areas Inspected:
Routine unannounced inspection of the licensee's Radiation Protection and Security Programs including: procedures, surveys, training, source inventory and leak tests, organization, radiation work permits, and respiratory protection,.
Results: No violations were identified.
8607240129 860716 PDR ADOCK 05000309 g
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DETAILS 1.
Persons Contacted 1.1 Licensee Personnel J. Garrity, Plant Manager E. Boulette, Assistant Plant Manager G. Cochrane, Radiological Control Section Head B. Castongnay, Administration Manager G. Pillsbury, Assistant to Manager, Technical Support L. Lawson, Quality Assurance Section Head B. Marshall, Security Director S. Evans, Licensing Engineer J. Hummer, Health Physics Supervisor H. Toberg, Security Supervisor 1.2 NRC Personnel C. Holden, Senior Resident Inspector Other licensee personnel were contacted and interviewed during the inspection.
2.
Purpose The purpose of this routine inspection was to review the licensee's basic radiation protection program with respect to the following elements:
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Review of procedures
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Review of survey data Review of training
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Review of source inventory and leak tests
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Review of organization and qualifications Review of radiation work permits
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Review of respiratory protection
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Review of site access criteria
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3.
Status of Previously Identified Items (Closed) Inspector Followup Item (309/84-17-02) Flow to the sample bomb of the Containment Air Sampling System has not been demonstrated.
The system has been designed eliminating the sample bomb, and the system has been demonstrated to be operable.
(Closed) Inspector Followup Item (309/84-17-02) Pressure and temperature indicators are not located in system. A pressure indicator has been installed in the system and provisions for a " Hand-held" temperature indicator have also been provided.
Procedure No. 7.1.2, " PASS Contain-ment Atmosphere Grab Sample" has been revised and it contains appropriate informatio l
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6 (Closed) Inspector Followup Item (309/84-17-02) Fluid may collect in sample bomb. The sample bomb has been removed from the system eliminating the possibility of water collecting in the system.
(Closed) Inspector Followup Item (309/84-17-02) Particulates and iodine samples may build up in the sample bomb.
The sample bomb has been removed from the system and replaced with a valve and septum arrangement.
(Closed) Inspector Followup Item (309/84-17-06) Complete arrangements for use of an on-site laboratory for backup capabilities.
Procedure No. 7.1.9, " PASS Isotopic Analysis", has been revised to incorporate two alternate on-site laboratories as backup facilities.
(Closed) Inspector Followup Item (309/84-17-06) Upgrade range capability of survey instruments used.
Procedure No. 7.1," Post Accident Sampling,"
has been revised, incorporating the PIC-6 :urvey meter as the instrument to be used for post-accident sampling and analysis monitoring.
(Closed) Inspector Followup Item (309/84-17-06) Modify data sheet. The Post Accident Sampling data sheet has been revised to include entries for all basic information required.
The licensee is in the process of soliciting bids from commercial vendors to assist them in completing all of the NUREC-0737 requirements.
4.
Procedure Review 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 interviewing a Radiological Control Foreman, reviewing a sample of procedures, and by observing ongoing operations.
Procedures reviewed included:
Procedure No. 0-00-06, " General Plant Training Program".
Procedure No. 9.1.1, " Plant Radiological Surveys".
Procedure No. 9.1.5, " Radioactive Source Inventory and Leak Test".
Procedure No. 9.1.12, " Issuance and Use of Personnel Monitoring Devices".
Procedure No. 9.200, " Radiological Controls Department Training Program".
Procedure No. 9.307, " Operation and Calibration of the Eberline PIC-6A".
Procedure No. 9.313, " Operation and Calibration of the Eberline RM-14 Radiation Monitor".
Procedure No. 9.316, " Pocket Dosimeter Calibration and Leak Testing".
The procedures reviewed were adequately detailed, and had been reviewed periodically as required.
Within the scope of this review, no violations were identified.
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5.
Surveys The licensee's survey program was reviewed against the criteria contained in 10 CFR 20.201, " Surveys".
The licensee's performance relative to these criteria was determined by discussions with a Radiological Contr ol Foreman and by reviewing records.
Within the scope of this review, the following was identified:
Procedure No. 9.1.1 " Plant Radiological Surveys", Section 8.0, dated December 11, 1985, specifies that completed surveys be sent to a Radio-logical Control Supervisor for review.
The inspectors determined that while this review does take place it is not well documented.
The licensee stated that future survey reviews will be initialed and dated by a Radiological Control Supervisor.
This documentation will be reviewed during a subsequent inspection (86-09-01).
Within the scope nf this review, no violations were identified.
6.
Training Radiological Control personnel training was reviewed against criteria con-tained in 10 CFR 19.12, " Instructions to workers" and Procedure No. 9.200,
+= " Radiological Controls Department Training Program". The licensee's performance relative to these' criteria was determined by interviewing a Radiological Controls Foreman, the Radiological Controls Supervisor, and by reviewing appropriate documents.
Within the scope of this review, the following was identified:
It was determined that the self-monitoring training given to certain licensee employees appeared to be inadequate. At the General Employee Training (GET) personnel are given brief training in the operation of a PIC-6 survey meter. This training involves training the instrument on and off, checking the battery, and checking the calibration date. After this minimal training, an individual is considred to be qualified to be a self-monitor using many survey meters. The inspector noted that a recently hired employee has been issued at least one survey meter, and this individual did not answer correctly the GET examination question having to do with survey meters.
The licensee stated that a new training program, due March 15, 1986 is still awaiting approval. The new training program will be reviewed during a subsequant inspection (86-09-02).
I Within the scope of this review, no violations were identified.
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Source Inventory and Leak Test Source inventory and leak tests were reviewed against the criteria con-tained in Technical Specification 4.2.12, " Surveillance Requirements" and Procedure No. 9.1.5, " Radioactive Source Inventory and Leak Test".
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The licensee's performance relative to these criteria was satisfactory.
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This was determined by discussions with a Radiological Control Foreman,
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Radiological Control Technicians, by reviewing appropriate documents, and by observation.
Within the scope of this review, no violations were identified.
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Organization and Staffing The licensee's organization and staffing were reviewed against criteria contained in the following:
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Technical Srecification 5.3 " Facility Staff Qualifications" The Salaried Employee Handbook
Radiological Controls Section Head, job description
Radiation Protection Supervisor, job description The inspector examined the job descriptions for several positions. These were found to be of adequate depth and detail.
Within the scope of this review, no violations were identified.
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Radiation Work Permits Radiation work permits were reviewed against criteria contained in the following:
10 CFR 19.12 " Instructions to Workers" Procedure No. 9.1.10 " Radiation Work Permits"
The licensee's performance relative to these criteria was determined
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from discussion with the Radiological Controls Foreman, and by reviewing
appropriate documents.
l The following radiation work permits were randomly selected for examination:
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i 86-1-1 " Operations /NSE Quarterly"
l 86-1-35 " Containment - Troubleshoot RTD" 86-1-51 " Containment - Change Out Hardware of LPMS System; Check
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i Voltage" The radiation work permits were found to be of sufficient depth and scope.
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Within the scope of this review, no violations were identified.
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10. Sand Removal Project The licensee discovered a small leak in an underground section of primary component cooling pipe outside the containment building. This pipe was dug up in order to prevent the leakage of chromated water into the nearby river. Approximately fifty cubic yards of sand accumulated as a result of this digging. This sand was placed in an area that was known to be radio-actively contaminated. This contamination was due to leakage from boxes l
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of waste that had been previously stored in the area. As a result of
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sitting in this area, some of the sand had become radioactively contam-
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Isotopic analysis showed this contamination be to 1 to 5x10 pCi/g of cesium-137.
These low activity levels are well below the value specified in 10 CFR 20, Appendix B.
The licensee is now segregating the contaminated sand. This is being accomplished by passing the sand through a monitoring system improvised by the licensee and storing contaminated sand in fifty-five gallon drums for future disposal. Noncontaminated sand is being piled inside the protected area near one of the guard towers.
The inspector observed the sand removal project and determined that the radiological controls were well planned.
Improved documentation of these
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controls was discussed with the licensee. This documentation will be reviewed during a subsequent inspection.
11.
Exit Interview The inspector met with the licensee's representatives (denoted in para-graph 1) at the conclusion of the inspection on June 6, 1986. The inspectors summarized the purpose and scope of the inspection, and iden-tified findings as described in this report.
At no time during this inspection was written material provided to the licensee by the inspectors.
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