IR 05000271/1978028
| ML19261B822 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 01/12/1979 |
| From: | Crocker H, Thonus L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19261B819 | List: |
| References | |
| 50-271-78-28, NUDOCS 7903070294 | |
| Download: ML19261B822 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-271/78-28 Docket No. 50-271 License No. npp-79 Priority
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Category c
Licensee:
Vermont Yankee Nuclear Power Corocration 20 Turnoike Road Westborouah, Massachusetts 01581 Facility Name:
Vermont Yankee Nuclear Station Inspection at:
Vernon, Vermont Inspection conducted December 11-15, 1978 Inspectors:
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L. H. Thonus, Radiatie'n Specialist
'[ date~ signed date signed date signed
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Approved by: h[
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H.W.Crocker,ChYf,RadiationSupport
// date signed Section, FF & MS Branch Inspection summary:
Inspection on uecember 11-15, 1978 (Report No. 50-271/73-28)
Areas Inspected: Routine, unannounced inspection of radiation protection during operations by a regional based inspector including followup of a circular and previous inspection findings, training, procedures, exposure control, instruments and equipment, notifications and reports, surveys, and facility tours.
Upon arrival at approximately 6:00 p.m. on December 11, 1978, a tour of the radiation control area was conducted to observe radiation safety practices.
The inspection involved 33 inspector-hours onsite by one NRC regional based inspector.
Results:
No items of noncompliance or deviations were observed.
R Apr 7)
7803070X ff'
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DETAILS 1.
Persons Contacted Mr. W. Anson, Training and Document Control Supervisor
- Mr. E. Bowles, Operations Training Supervisor
- Mr. L. Bozek, Y.A.E.C. 0QCA
- Mr. F. Burger, QA Coordinator
- Mr. R. Burke, Engineering Support Supervisor
- Mr. W. Conway, Plant Superintendent
- Mr. R. Donald, QA Technical Assistant
- Mr. D. Girroil, Engineering Assistant
- Mr. B. Leach, Health Physics Mr. J. McCarthy, Health Physics Assistant
- Mr W. Murphy, Assistant Plant Superintendent Mr. M. Prystupa, Health Physics Assistant Mr. P. Pulaski, Health Physics Assistant Mr. S. Skibniowsky, Health Physics Assistant Mr. A. Thomas, Document Control Coordinator Mr. D. Tolin, Health Physics Assistant
- Mr. G. Weyman, Chemistry and Health Physics Supervisor The inspector also contacted ten other individuals including health physics technicians, clerks, auxiliary operators, and members of the security force.
- denotes those present at the exit interview.
2.
Licensee Action on Previous Inspection Findinas (Closed) Unresolved Item (50-271/78-26-01): Posting of radiation control area.
The inspector found that the doorway to the radiation control area (RCA) via the switchgear room was posted such that a person entering the RCA would see the posting prior to entry.
Additionally, directions requiring the use of a frisker prior to exiting the RCA were posted sucn that they would be seen by persons exiting the area through the above doorway.
Independent measurements made by the inspector indicated that radiation levels in the unrestricted portion of this area were within the limits of 10 CFR 20.105.
The inspector had no further questions at this time.
No items of noncompliance were identifie.
3.
Licensee Action on IE Circular 78-03 Packagino greater than type A auantities of low specific activity material for transpoi t.
The inspector reviewed the licensee certificates of compliance and supporting documentation used to fulfill the requirements of a general license in accordance with 10 CFR 71.12(b).
The licensee had provided the Director of Nuclear Material Safety and Safeguards with the information required by 10 CFR 71.12(b).
The licensee is applying his NRC approved 10 CFR 50 Appendix B quality assurance program to radioactive material transport packages.
The inspector had no further questions at this time.
No items of noncompliance were identified.
4.
Tra ining a.
General Emoloyee and Radiation Worker Trainina The licensee's general employee and radiation worker training program was reviewed against the criteria given in 10 CFR 19.12, ANSI N18.1-1971, and procedure AP-0720.
Training records and examinations given at the end of training were reviewed for 10 employees.
Color coded security badges of 8 employees were examined at the guard house to verify that they matched the level and status of training of the individuals.
The group selected included radiation workers, non-radiation workers, and radiation workers who's training had expired (i.e. terminated or retraining not performed).
No discrepancies were noted, the workers with expired training no longer had access to the site; the other workers' badges matched their level of training.
b.
Auxiliary Operator Training The licensee utilizes auxiliary operators as persons " qualified in radiation protection procedures" on back shifts.
The inspector reveiwed the licensee radiation protection training and retraining for auxiliary operators as outlined in procedures AP-0720 and DP-0160.
Training and retraining records of four auxiliary operators were examined.
The inspector interviewed an auxiliary operator to verify that the requirerents of Technical Specification (TS) 6.1.D.1 were me.
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5.
Radiation Protection Procedures The following procedures were reviewed against the criteria given in ANSI N18.7-1972, Regulatory Guide 1.33 (1972) and procedure AP-0001 " Plant Procedure:"
AP-0506, " Personnel Monitoring," Revision 3, October 2,1978
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AP-0520, " Personnel Decontamination Procedure," Revision 5, October 5, 1978
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OP-2511, "Radwaste Cask Handling," Revision 4. July 13,1978 OP-2520, " Operations of Victoreen Monitors," Revision 5.
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November 17, 1978 OP-4511, " Source Calibration of Process Radiation Monitoring
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System," (PRMS)," Revision 7, March 3, 1978 RP-4520 " Source Calibration of Area Radiation Monitoring
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System, Revision 3, November 17, 1978 DP-4540, " Calibration of HP Portable and Laboratory Radiation
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Detection Instruments," Revision 6, October 5, 1978
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OP-4543, " Calibration of Teletector Model #6112," Revision 4, October 5, 1978 DP-4545, " Calibration of Model 3006 Mini-Rad," original,
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October 5, 1978 DP-4550, " Calibration of Portal Monitor," Revision 5, October
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5, 1978 DP-4552, " Calibration of PAC-40G," Revision 3, September 22,
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1978 DP-4553, " Calibration of Hand and Foot Monitor," Revision 4,
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October 2, 1978 DP-4555, " Calibration of the Model 6122 Atometer," Revision 4,
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September 22, 1978
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DP-4558, " Calibration of Eberline Rad-0wl," Revision 1, January 17, 1978
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DP-4560, " Calibration of RM-16," Revision 1, January 17, 1978
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No items of noncomplianc were identified.
6.
Instruments and Equipment The licensee's radiation monitoring instruments and equipment were reviewed against the criteria in procedures OP-4511, RP-4520, and DP-4540.
The inspector examined the licensee's portable instruments available for use to verify that they had the capability of measuring alpha, beta, gamma, and neutron radiation, airborne activity and surface contamination over a suitable range.
Independent measure-ments were made to check area radiation monitors.
Results of the measurements were compared with local readout, control room readout, and results recorded on strip chart recorders.
Calibration results and records were examined for 13 instruments including air samplers, portable survey instruments, and area radiation monitors.
Calibration stickers of approximately 15 portable instruments in use in the field were checked.
No items of noncompliance were identified.
7.
Excosure Control Exposure records of five individuals were reviewed to verify that form NRC-4 had been completed prior to exceeding the limits of 10 CFR 20.101(b).
Form NRC-5's of nine individuals were examined against the requirements of 10 CFR 20.401.
Second and third quarter 1978 exyosures of approximately 100 contractors and station personnel were reviewed against the requirements of 10 CFR 20.101.
Bioassay data (whole body counting) of five individuals indicated less than 5% body burden for all of the individuals.
No items of noncompliance were identified.
8.
Notifications and Reports The inspector examined the records of the licensee's notifications and reports for compliance with 10 CFR 20.405 and 10 CFR 20.408 and 10 CFR 20.409.
No overexposures, excess levels, or concentrations had occurred which would have required reporting in accordance with 10 CFR 20.405.
The inspector examined termination reports of five individuals who had terminated after the 1978 torus modification and refueling outages for compliance with 10 CFR 20.408 and 10 CFR 20.409 No items of noncompliance were identifie,-.
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9.
Surveys The inspector reviewed licensee radiation contamination and air-borne surveys against the criteria in 10 CFR 20.103, 10 CFR 20.201, licensee procedure DP-4530, " Dose Rate Radiation Surveys," procedure DP-4531, " Radioactive Contamination Surveys," and procedure DP-4533,
" Airborne Radioactivity Concentration Determination."
The surveys reviewed included routine weekly surveys of the radwaste building during November and December 1978, and routine surveys of the 345 ft. and 280 ft. elevations of the reactor building from July thru October 1978.
Surveys taken to evaluate potential radio-logical hazards associated with radiation work permits 1778, 1793, 1791, and 1814 were also examined.
Independent radiation and contamin-ation surveys were made to verify selected recent licensee surveys and posting.
No items of noncompliance were identified.
10.
Facility Tours Upon arrival, approximately 6:00 p.m., on December 11, 1978, a tour was conducted of the ' radiation control area to observe radiation safety practices.
Two additional tours were performed during the course of the inspection.
Current Radiation Work Permits (RWP's)
were reviewed to verify that they provided an adequate level of protection for workers.
Several job sites were visited to observe adherence to RWP requirements by workers.
The health physics log-book was excmined for selected portions of September, October, and December 1978.
No items of noncompliance were identified.
11.
Exit Interview The inspector met with licensee management representatives (denoted in Paragraph 1) at the conclusion of the inspection on December 15, 1978.
The inspector summarized the purpose and scope of the inspec-tion and the inspection findings.
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