IR 05000309/1982022
| ML20028C780 | |
| Person / Time | |
|---|---|
| Site: | Maine Yankee |
| Issue date: | 12/22/1982 |
| From: | Plumlee K, Shanbaky M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20028C774 | List: |
| References | |
| 50-309-82-22, NUDOCS 8301140094 | |
| Download: ML20028C780 (12) | |
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k U. S. NUCLEAR REGULATORY COMMISSION
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Region I
Report No. 50-309/82-22-Docket No. 50-309 License No. DPR-36'
Priority
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Category C
Licensee:
Maine Yankee Atomic Power Company 83 Edison Drive Augusta, Maine 04336 Facility Name:
Maine Yankee Inspection At:
Wiscasset, Maine Inspection Conducted:
October 25-28, 1982 Inspectors:
12-M N A K.* E. Plumlee, Radiation Specialist-date signed date signed Approved By:
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M. 'Shanbaky, Chief, FaciWties Radiation dafe sfgned
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Protection Section, RPB Inspection Summary:
Inspection on October 25-28, 1982 (Report No. 50-309/82-22)
Areas-Inspected:
Routine, unannounced safety inspection by a regional based inspector of radiation protection during the Ten year Inservice Inspection of the reactor, including: outstanding items, procedures, advanced planning and preparation, training, exposure control, respiratory protection, posting, radioactive and contaminated material control, surveys, air cleaning systems, transportation of radioactive materials, and independent measurements. This inspection involved 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> onsite by one NRC regional based inspector.
Results:
No items of noncompliance were identified.
9301140094 821229
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DETAILS 1.
-Persons Contacted Maine Yankee Employees W. Brawn,. Plant Services Supervisor
- J. Brinkler, Technical Support Department Head R. Chase, Quality Assurance (QA) Supervisor
- G. Cochrane, Radiological Controls Section Head-D. Day, Engineering Aide R. Forrest, Facilities Section Head
- J. Garrity, Senior. Director, Nuclear Engineering and Licensing i
A. Jordan, Quality Control (QC) Supervisor
- R. Lawton, Director, Quality Assurance G. Pillsbury, Radiological Controls Supervisor P. Radsky, Chemistry Section Head D. Sellers, Hazardous Waste Coordinator F. Setchell, Health Physics Specialist (ALARA)
- D. Sturniola, Assistant to the Plant Manager
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R. Foster, Assistant to Safety and Health Physics Coordinator, Nuclear Power Services (NPS) Energy Services, Inc.
- denotes presence during the exit interview on October 28, 1982.
- Inspection findings were reviewed with the plant manager prior to the exit interview.
2.
Licensee Action on Previously Identified Items (Closed) Inspector Follow Item (79-19-01):
Jewatering of radioactive waste for burial. No liquids have been identified in solidified waste after changing from urea-formaldehyde to cement as the solidifying agent (licensee letter, February 4, 1982).
The inspector verified that approved procedures were provided for operation of the new solidification system.
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The licensee is negotiating the offsite processing of several previously solidified (unacceptable) containers of waste. Untti shipment to the processor, these containers will remain in the waste storage bunker onsite.
(Closed) Inspector Follow Item (81-11-01):
Procedural control of fuel transfer tube shielding. The inspector verified that procedural controls were established in accordance with the understanding of the letter to
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' the licensee, February 13',11982. - Specifically the installation'of: shield- :
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Ling'before transferring spent. fuel is controlled by procedures 9.-l.11,
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"HP for Refueling _and Outages"; 10-1," Core-Reloading"i 13-3," Transfer
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- Machine and Upender Operation"; and_13-4," Refueling Machine Operation".
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Removal.of..the. shielding before resuming reactor operatio'n is:
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' accomplished by a change to procedure 10-1, initiated;0ctober 28,J1982.
'(Closed)'Inspe:: tor' Follow' Item (81-18-01):
Review of-Q'uality Assurance /
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Quality Control (QA/QC) Program for transportation. The inspector.
interviewed personnel and reviewed procedures and recent records to determine the acceptability.of the program._;No violations:of NRC, DOT, or burial site requirements were identified;on this inspectio'n.
.(Closed).Vi_olation(81-27-01): Transfer:of'an unauthorized form of'
radwaste:to the burial site.(excess li_ quid). The, inspector touredithe waste facility,z observed the load _ing and shipment of radwaste, reviewed
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the procedures and shipping records, and discussed the' status of previously solidified radwaste-(see item 79-19-01,above). No remaining'. regulatory 1
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problems were identified.
(Closed) Violation (82-08-01): ~ Failure to. post,. barricade,-and lock-up high radiation areas. The inspector' surveyed several? areas, including:
three levels inside containment,-and-observed the' access controls to the.
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high radiation areas. The corrective actions de' scribed in.the. licensee
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letter, August 13, 1982, were in effect. No problems were identified.
(Closed) Violation (82-08-02):
Inadequate survey'to control a high radiation area. The inspector reviewed ~the recent survey records and
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radiation work permits,-and also observed the. areas and the' conduct of work, to' verify the completion of corrective' actions described in the licensee letter, August 13, 1982. No violations were identified.
(Closed) Unresolved Item (82-08-03): Adherence to stepoff pad procedures.
The inspector observed workers crossing 25 stepoff pads, in several parts of the facility. No improper crossings were witnessed. One.stepoff pad'
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was not stocked with rubbers, but required anyone crossing in either
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direction to change rubbers. The licensee promptly provided rubbers, to
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permit proper use of this stepoff pad. The check for contamination of l
the pad was negative.
(Closed). Unresolved Item (82-08-04): Application of ALARA controls to
all high radiation areas. The licensee stated certain activities were
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being accomplished, e.g. shielding, equipment flushing, and area decon-tamination. The inspector verified these actions during facility tours.
(Closed) Unresolved Item (82-08-06): Adequacy of the organization -
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radwaste coordinator reports to the' facilities section head instead of to j
.the radiological controls section head. The inspector reviewed the l
organization chart (figure 1), job descriptions, training records, and
personnel availability to determine the status of the radwaste
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transportation program. 'The radwaste coordinator, his supervisor, and an
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4-alternate, appeared to have adequate qualifications,'i.e.,had attended offsite seminars and workshops to prepare for this responsibility.
3.
Radiation Protection Procedures
.The licensee representative stated that no changes were necessary in the established radiation protection procedures, because of.this outage. -The licensee recently audited the procedures.
The inspector reviewed the current radiation work permits for consistency with the procedures, and toured the facility to observe adherence to procedures.
No violations were identified.~
4.
Advanced Planning and Preparation 4.1 Increased Health Physics Staff The licensee representative stated that the following temporary employees were hired before or during the outage to assist with outage preparations and the increased work load during the outage:
1 Site Coordinator (NSS)
3 Supervisors (NSS)
29 Senior Health Physics Technicians (NSS)
21 Junior Health Physics Tecnnicians (NSS)
4 Record technicians (NSS)
7 Clerks (NSS)
1 Safety and Health Physics Coordinator (NPS)
1 Assistant to the Safety and Health Physics Coordinator (NPS)
The inspector reviewed the resumes and training records of 10 senior health physics technicians to determine that they had the qualifications required by the Technical Specifications, Section 5.3.11 ANSI N18.1, 1971, " Selection and Training of Nuclear Power Plant Personnel ";and plant procedures.
Additionally, the inspector interviewed the Site Coordinator, a supervisor, ten technicians, three clerks, and the Assistant Rafety and Health Physics Coordinator, to informally verify their. te-specific training, experience, and educational background, as well as their concept of their assignments.
No violations were identified in this area.
4.2 Mockups and Special Training and Equipment The licensee representative stated that a steam generator mockup was available and used for training. Specially trained personnel were contracted to perform steam generator tube eddy current tests, tube
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/ plugging -welding',;and radiography.- Remotely' operated in-service in-
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- spection equipment and viewers'were used.
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.The licensee also utilized hydrolasingiequipment-to reduce the surface-contamination. levels.
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' Containments'andfair-cleaning systems were used to control'the contamina-tion resulting' from cleaning, brushing,' grinding and welding operations.
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No violations were identified in'this area ~.
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4'3 Supplies-and Equipment used for Radiation Protection-
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- The, inspector toured the ' facility to: review the availability'and 'use-of ' '
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survey instruments,' protective' clothing,~ respirators, shielding, decon-tamination materials, and special equipment.
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- No survey instruments:were identified as inoperative'or overdue for
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calibration.
Further, the review indicated no apparent delays'in-obtaining
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instruments and equipment and no shc,rtages during this inspection. The i
licensee corrected two off-scale frisker trip points, identified by-the inspector,.during this' inspection.
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n No violations were identified in this area.
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Training
5.1 Escorted Personnel
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Untrained personnel, such as short term visitors or new arrivals who had not yet completed their training for unescorted access, were sscorted in the controlled area.
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The licensee also used page system announcements, posted information, 1'
signs, local warning lights and alarms, and maintained an evacuation
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alarm system to inform all personnel of circumstances requiring action.
No violations were identified in this area.
1-5.2 General Employee Indoctrination Review of the. general employee indoctrination, provided to cociply with 10 CFR.19.12, indicated that qualified contract instructors provided personnel
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training. The training included the use of a lesson plan, radiation l
protection manual, visual aids, video tapes, lecture sessions, and'a l
l written examination. The Training Department conducted this training.
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- The inspector observed part of the training, and contacted 10 workers at i
various times during the inspection to verify their completion of 'indoc-trination and the effectiveness of the training.
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6-No violations were identified in this area.
5.3 Contract Health Physics Technician Training Review of Procedure No. HP 9.237, " Health Physics Department Training Program", Section 8.0, Contractor-Technician Health Physics Training, and records'of training conducted pursuant to the procedure, indicated that these personnel' received the following training:
General employee indoctrination; Familiarization tour of the radiological control area (RCA);
A review of HP procedures, policies and administrative limits; and, On-the-job training and evaluation.
The inspector contacted ten temporary technicians during inspection tours and verified that their qualifications and training were adequate for-their actual job assignments. The review of training records and resumes (Paragraph 4.1) did not identify any inconsistencies with their assignments.
No violations were identified in this area.
6.
Exposure Control 6.1 ALARA Program Review during this outage included observation of the licensee's and individual worker's adherence to the ALARA program.
The inspector verified that:
The ALARA program was included in each worker's indoctrination training; Procedure No. HP 9.1.10 required a full ALARA review for every job having a potential to exceed a total of 5 man-rem exposure; Personnel dosimetry results were kept up to date during the outage, by the use of an onsite TLD reader; Shielding, ventilation / filtration systems, enclosures, and remote operated equipment were provided as needed; and Work areas were frequently decontaminated, and radwaste was not allowed to accumulate.
No violations were identified in this area.
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6.2' Personnel Dosimetry Practices The inspector reviewed the licensee's dosimetry practices to verify
' compliance with the requirements of 10~CFR 20.101, " Radiation dose standards..."; 10 CFR 20.102, " Determination of prior dose"; 10 CFR 20.202, " Personnel monitoring";, 10 CFR 20.401, " Records of surveys, radiation monitoring, and disposal"; 10 CFR 20.408, " Reports of personnel monitoring on termination..."; 10 CFR 20.409, " Notifications and reports to individuals";.and 10 CFR 19.13, " Notification and reports to t
individuals." This review included:
Tours of the reactor building, process auxiliary building, fuel handling building, radwaste facilities, turbine building, and the grounds within the inner security fence, to evaluate the dosimetry practices on several modifications, maintenance activities, in-service inspections, and waste handling operations; Examination of 20 RWPs to review the instructions for special dosimetry; Examination of the daily cor.puter printout of dosimetry records to identify any unusual personnel exposures; Examination of the record files of ten individuals, authorized to exceed 1 1/4 rems during a calendar quarter, to verify that their Form NRC-4s vere completed; Examination of the record files of ten previously terminated indi-viduals to verify that dosimetry reports were routinely provided to the terminated workers and to the NRC; and Contacts with five individuals who were terminating to verify that written dosimetry estimates were routinely provided on termination.
No violations were identified in this area.
7.
Respiratory Protection Practices 7.1 Internal Exposure Limits Observation of working conditions during this inspection, and review of records of work permits, air samples, contamination surveys, nasal swipes, skin contamination, and whole body counts did not identify any exposure to airborne radioactive materials in excess of 10 CFR 20.103 limits.
No violations were identified in this area.
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~7.2 Engineering Controls The inspector verified that exposures to airborne radioactive materials were controlled in compliance with 10 CFR 20.103 by decontamination of the surfaces, use of plastic: covers and tents to prevent spreading contamination, and use of controlled ventilation systems to prevent exposures to unacceptable concentrations of airborne radioactive mate-rials.
'No violations were identified in this area.
7.3 ' Licensee Evaluation of Controls
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The inspector noted that the RWP records and the licensee evaluations indicated the' selection of acceptable' equipment, the use of authorized protection factors, and the application of preventive measures.
The inspector verified that internal exposures were evaluated in accor-dance with a written, approved procedure, HP 9.1.22.
No violations were identified in this area.
7.4 Respiratory Protection Training and Respirator Fitting and Testing The inspector verified that determination of physical ability and fitting.
and training of personnel using respirators was documented; and that the applicable procedures, HP 9.1.2, 9.1.3, 9.1.13, 9.1.21, and 9.1.23 were fully implemented.
No violations were identified in this area.
7.5 Respirator Use, Cleaning and Disinfection, and Maintenance The inspector observed the conduct of each of the following activities to verify it was conducted in compliance with the requirements of 10 CFR 20.103 and 10 CFR 20, Appendix A:
Selection of respirators; Issue of respirators; User's check of the respirator on receipt; User's fit test of the respirator when donned; Wearing of respirators on the job; Removal of respirators on leaving the job; i
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i Collection-of' respirators to be cleaned and reissued;-
Cleaning, disinfection, and maintenance of respirators; Storage of respirators; and, Supply of respirable air 'to atmosphere-supplying respirators.
No violations were identified in this. area.
7.6 Procedural Controls on Nonconforming Uses of Respirators-The inspector verified that the procedures, in order to comply with 10 CFR 20.103 and 10 CFR 20, Appendix.A, prohibit the following misuses of respirators:
Wearing of air purifying respirators in. oxygen-deficient atmo-spheres; Use of cannisters in atmospheres for which the cannisters are not approved; and, Wearing of-respirators over glasses, beards or articles of clothing that ceuld interfere with the respirator.' seal.
No violations were identified in this' area.
8.
Posting and Control of Radiation Areas, Airborne Radioactivity Areas, and Contaminated Areas The inspector toured the facility to verify compliance with the require-ments of 10 CFR 20.203, " Caution signs, labels, signals, and controls."
This tour involved the following:
Confirmatory surveys to verify the adequacy of the posted informa-tion, container labels, and barricades, at several locations about the facility; Verification of licensee adherence to procedure HP 9.1.6,
" Establishing and Posting Controlled Areas";
Checks of ten locked doors controlling entrances to High Radiation Areas; and, Review of the facility radiation monitors and air monitors having remote readouts in the control room.
No violations were identified in this area.
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~10 9.
Radioactive and Contaminated Material Control During the tours described above,:the _ inspector verified by surveys:and observation that:
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' Radioactive and. contaminated material was' collected in properly labelled containers; Used protective clothing, respirators, tools, parts and radioactive waste were systematically collected and routed to the appropriate disposition such as. shipment to an offsite laundry, respirator cleaning and maintenance onsite, decontamination, storage, or preparation for shipment offsite;_
Radioactive waste reduction program was implemented; and, Noncontaminated waste was maintained in separate receptacles from contaminated materials and was surveyed to verify its proper dispo-sition upon release from the controlled areas.
The inspector observed the preparations for one shipment of radioactive waste to a burial site,'and reviewed the QA records and shipping records.
No violations were identified in this area.
10. Surveys The inspector reviewed and verified survey information as reported in preceding paragraphs 2, 4.3, and 8.
No violations were identified in this area.
11. Air-Cleaning Systems 11.1 Filter Efficiency Tests The licensee stated that the most recent results were not yet certified in writing for the HEPA and charcoal filter system surveillance tests.
The results were stated to be acceptable.
The filter test certificates will be reviewed on a routine inspection.
(82-22-01)
11.2 Review of Ventilation Systems Status
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The inspector conducted a visual examination of the ventilation systems.
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'f ailed belts, cracks, or penetrations were apparent. The inspector noted that the injection, sampling and drain pcrts were closed.
No violations were identified in this area.
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i-11 12. Receipt and Preparation of Radioactive Materials for Transport -
The inspector verified that the radwaste coordinator maintained strict controls over-the receipt and the shipment of radioactive materials. The procedures, records, and the QC and-audit' reports-indicated there were.
routine examinations of the activity.
I No violations were identified in this area.
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Independent Measurements.
. Independent measurements are described in preceding paragraphs 2, 8 and 9, of this report.
No violations were identified in this area.
14.
Exit Interview The inspector _ met with the licensee representatives, denoted in paragraph 1, at the conclusion of the inspection.
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The inspection findings were reviewed.
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