IR 05000334/1983011
| ML20024B772 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/20/1983 |
| From: | Clemons P, Shanbaky M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20024B768 | List: |
| References | |
| 50-334-83-11, NUDOCS 8307110366 | |
| Download: ML20024B772 (5) | |
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U. S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No. 50-334/83-11 Docket No. 50-334 License No. DPR-66 Priority Category C
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Licensee: Duquesne Light Company P. O. Box 4 Shippingport, Pennsylvania 15077 Facility Name: Beaver Valley Power Station, Unit No. 1 Inspection At: _Shippingport, Pa.
Inspection Conducted: May 24 - 27, 1983 Inspectors:
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'P. Clemons, Radiation Specialist
/datd Approved by: M-I#
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M. 'ShanbaQ/, Chief, Fackrities Radiation
' dat Protection Section, Radiation Protection Branch Inspection Summary:
Inspection on May 24 - 27,1983 (Report No. 50-334/83-11)
Areas Inspected: Routine, unannounced safety inspection of the Radiation Protection Program, including: outstanding items, outage advanced planning and preparation, procedures, training, posting and control, exposure control, source leak test, and the radiation monitoring system.
The inspection involved 32 inspector-hours onsite by one regional based inspector.
Results: No violations were identified.
8307110366 830622 PDR ADOCK 05000334
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Details 1.
Persons Contacted 1.1 Licensee Personnel
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- Mr. K. Grada, Superintendent of Licensing
- Mr. J. Starr, Station Engineering Supervisor
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- Mr. J. Kosmal, Radiological Controls Operations Coordinator
- Mr. F. Lipchick, Senior Compliance Engineer Mr. E. Schnell, Radiological Controls Supervisor
- Mr. E. Cohen, Senior Health Physics Specialist
- Mr. W. Canan, Senior Health Physics Specialist
- Mr. J. Nipur, Radiological Controls Foreman 1.2 NRC Personnel Attending the Exit Interview
- Mr. W. Troskoski, Resident Inspector
- Attended the Exit Interview on May 27, 1983.
Other licensee and contractor personnel were contacted and inter-viewed during this inspection.
2.
Purpose The purpose of this routine inspection was to review the licensee's radiation protection activities with respect to the following elements:
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Status of Previously Identified Items;
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Review of Advanced Planning and Preparation for Major Outage Tasks; Review of Procedures;
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Review of Personnel Training;
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Review of Posting and Control; Review of Exposure Control;
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Review of Source Inventory and Leak Test; and,
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Review of the Radiation Monitoring System.
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Status of Previously Identified Items (Closed) Inspector Follow-up Item (81-32-06). Complete review of the licensee's respiratory protection program. The licensee currently does r
l not take crertit for respirator protection; therefore, there is no require-ment to have a respiratory protection program.
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Advanced Planning and Protection l
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The licensee's efforts in advanced planning and preparation for major outage tasks were reviewed against the criteria contained in 10 CFR 20.201, " Standard for protection against radiation", ANSI 18.1, " Selection
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and training of nuclear power plant personnel", Regulatory Guide 8.27,
" Radiation protection training for personnel at light-water-cooled nuclear power plants", and Regulatory Guide 1.33, " Quality assurance program requirements (operation)," and applicable station procecures.
The licensee's performance relative to these criteria was determined from discussions with the Radiological Controls Supervisor and other senior staff members.
The major tasks discussed were the Steam Generator operation, the Split Pin operation, and the Snubber operation. These operations are considered as the operations where the major exposures are most likely to occur. An ALARA (As-Low-As-Reasonably-Achievable) review of the Split Pin operation had been completed by the contractor who will do the work and submitted to the licensee. Documented ALARA reviews had not been completed for the other major operations at the time of this inspection.
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According to the Radiological Controls Supervisor, the health physics staff will be increased by more than 100 contractor personnel. The additional people will include Foremen and junior and senior technicians.
Some of these contractor personnel have worked at the site continuously for several years. Most of the contractor Foremen will be selected from this group.
Resumes of approximately 10 contractor personnel were reviewed.
The resumes were for Foremen and junior and senior technicians.
Within the scope of this review, no violations were identified.
5.
Procedure Review The adequacy and effectiveness of the licensee's procedures were reviewed against the criteria contained in:
10 CFR 20.103, " Exposure of Individuals to Concentrations of Radioactive Materials in Restricted Areas,"
Technical Specification 6.8, " Procedures," and Technical Specification 6.11, " Radiation Protection Program."
Procedures reviewed included:
" Area Entry Requirements", Radcon Procedure No. 2.1
" Radiological Work Monitoring", Radcon Procedure No. 2.2
" Decontamination Control", Radcon Procedure No. 2.3
" Area Posting", Radcon Procedure No. 2.4
" Contaminated Area Control", Radcon Procedure No. 9.1
" Radiation Area Control", Radcon Procedure No. 9.2
" Pocket Dosimeters - Reading and Charging", Radeon Procedure No. 4.3
" Pocket Dosimeters - Controlling", Radcon Procedure No. 4.5
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" Radiation Clearance", Radcon Procedure No. 8.2
" Containment Radiation Barrier Key Control - Shutdown and Major Maintenance", Radcon Procedure No. 8.3
"GM Survey Meter - Model E 530", Radcon Instrument Procedure No. 3.2
"Teletector 6112 Survey Meter", Radeon Instrument Procedure No. 3.5
" Area Contamination Survey", Radcon Procedure No. 7.1
" Area Radiation Survey", Radcon Procedure No. 7.2
" Air Sampling, Field Evaluation and Sample Assessment of Radioactive Particulates, Iodines and Noble Gases", Radcon Procedure No. 7.3
" Portable High Volume Air Sampler - Staplex", Radcon Instrument Procedure No. 6.4
" Anti-Contamination Clothing Use", Radcon Procedure No. 9.4
" Material Monitoring", Radcon Procedure 3.1
" Labeling and Packaging Radioactive and/or Contaminated Material",
Radcon Procedure No. 3.2
" Drumming of Solid Waste", Radcon Procedure No. 3.17
" Radiological Work Permit", Radcon Procedure No. 8.1 Within the scope of this review, no violations were identified.
6.
Personnel Training Personnel training was reviewed against criteria contained in 10 CFR
19.12, " Instructions to Workers" and Regulatory Guide 8.27, " Radiation Protection Training for Personnel at Light Water Cooled Nuclear Power Plant."
The licensee's performance relative to these was determined from discus-sions with the Radiological Controls Supervisor and other staff members, review of training records for approximately 25 employees (contractors),
and direct observation of training in' progress at the time of this inspec-tion.
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Within the scope of this review, no violations were identified.
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Posting and Control The licensee's program for posting and control was reviewed against the
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criteria in 10 CFR 20.203, " Caution signs, labels, signals and controls."
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The licensee's performance relative to these criteria was determined from l
several tours of the Controlled Areas and from discussions with the l
Radiological Controls Supervisor and other staff members.
It was noted that the licensee locks all areas exceeding 100 millirem per hour.
Within the scope of this review, no violations were identified.
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Source Leak Test The source leak test was reviewed against criteria contained in Technical Specification 3/4.7.9. The licensee's performance relative to these criteria was determined from discussion with the responsible Health Physicist and review of appropriate records.
Within the scope of this review, no violations were identified.
10.
Radiation Monitoring System On May 25, 1983, as the inspector toured the Primary Auxiliary Building (PAB) on the 752' elevation, it was noted that numerous radiation monitors were located on this evalation. The units are used to monitor the Primary Stack effluents, the Auxiliary Building ventilation effluents, and several other locations.
It was observed in each monitor that there were elbows, bends and long lengths of pipe (distance unknown) going from the sampling point to the detectors. The inspector asked if any of the monitors monitoring gaseous and particulate discharges had been evaluated to determine if the monitors were providing representative samples of effluent pathways.
The inspector was provided documentation of tests of the Radiation Monitoring System that were performed during 1975, but this documentation did not verify that the tests were performed to assure that the various monitoring systems were providing representative samples of effluent pathways.
On June 7, 1983, the Radiological Controls Operations Coordinator was informed that the documentation provided was inadequate and that sometime during the pending outage, the representative sampling capability of the Radiation Monitoring System would be a'ddressed again.
This item will remain as an unresolved item until that time (83-11-01).
11.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on May 27, 1983.
The inspector summarized the purpose and scope of the inspection, and the inspection findings.
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