IR 05000333/1993009
| ML20036A295 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/26/1993 |
| From: | Eckert L, Joseph Furia, Pasciak W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20036A291 | List: |
| References | |
| 50-333-93-09, 50-333-93-9, NUDOCS 9305110058 | |
| Download: ML20036A295 (9) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-333/93-09 Docket No.
50-333 License No.
DPR-59 Licensee:
New York Power Authority Post Office Box 41 Lycoming. New York 13093 Facility Name:
James A. FitzPatrick Nuclear Power Plant Inspection At:
Lycoming. New York Inspection Conducted:
Anril 12-16.1993
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Inspector:
9-e 'B J. Fdrfa, Senior RIdiation Specialist, date Facilities Radiation Protection Section (FRPS),
Facilities Radiological Safety and Safeguards Branch (FRSSB), Division of Radiation Safety and Safeguards (DRSS)
w fJg v-w-n L. Eckert,4adiation Specialist, FRPS, FRSSB, DRSS date Approved by:
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V-G -f1 W. PascialCChief, FRPS, FRSSB, DRSS date Areas Inspected: Announced inspection of the radiation protection program including:
management organization, radiation protection during normal operations, contamination control, transportation of radwaste, respiratory protection, instrumentation, dosimetry, training, and implementation of the above programs.
Results: Performance in the areas of external dosimetry, internal dosimetry, respiratory protection and instrumentation was determined to be good. Improved performance in the area of health physics technician training was also observed. Some weakness in health physics technician knowledge and plant personnel industrial safety practices was noted.
9305110058 930504 PDR ADOCK 05000333 G
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DETAII3 1. Eersonnel Contacted 1.1 Licensee Personnel
- R. Barrett, General Manager - Operations
- T. Bergene, ALARA Supervisor D. Crisafulli, Training Instructor
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- M. Colomb, General Manager - Support Services i
- C. Gannon, Radiological and Environmental Services Manager R. Graben, Instrument & Respiratory Supervisor
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- J. Heddy, Licensing
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- D. Lindsey, General Manager - Maintenance
- J. McCarty, Senior Quality Engineer
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- M. McMahon, Health Physics General Supervisor j
- E. Mulcahey, Senior Technical Advisor
C. Peper, Radiological Engineer l
R. Ruben, Program Administrator - Training
- H. Salmon, Resident Manager
- J. Solini, Radiological Engineering General Supervisor
- K. Szeluga, Dosimetry Supervisor i
G. Tasick, Quality Assurance Manager A. Young, Decontamination and Shipping Supervisor 1.2 NRC Personnel
- W. Cook, Senior Resident Inspector
- W. Pasciak, Chief, Facilities Radiation Protection Section J. Tappert, Resident Inspector
- Denotes those present at the exit interview on April 16, 1993.
2. Previously Identified Items (Closed) Inspector Follow-Up (50-333/92-16-01) Radiological Incident Report (RIR)
follow-up problems. The licensee has added the items created by the RIR program to the plant Deviation Event Report tracking system, in order to better track open items from the RIR system. This item is closed.
3. Radiation Protection Program No management changes have been made by the licensee in the radiation protection area of the Radiological and Environmental Services (RES) Department since the last inspection. In February 1993 the licensee undertook a small maintenance outage,
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which is further described below. The licensee anticipated undertaking a more
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extensive maintenance outage in September 1993 lasting for several weeks. In addition, the licensee plans to implement the "new " Title 10, Code of Federal Regulations (CFR), Part 20 on September 1,1993.
3.1 Radiation Control During this inspection, the licensee operated the plant at or near 100% power.
As part of this inspection, tours of various parts of the Restricted Area were conducted. In general, all areas were determined to be well maintained and properly posted. Several minor discrepancies were noted by the inspectors, but these were promptly addressed and corrected by the licensee staff. One item of industrial safety non-compliance was also noted on the 252' elevation of the turbine building, where a worker was observed climbing on electrical conduit and switch boxes in order to reach a valve over 10' in the overhead.
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Also of some concern was the level of knowledge and attitude presented by two health physics technicians when questioned about some work in progress.
Specifically, the technicians did not appear familiar with the limitations on portable High Efficiency Particulate Air (HEPA) systems, and the need to place hoses connected to these systems as close to the work area as possible.
A second concern involved an amber alarm light in the turbine building that was continuously flashing. The entrance to most High Radiation Areas had been equipped with these alarm lights as part of the licensee's improvement plan for High Radiation Areas. When a space on the 252' elevation of the Turbine Building (door 252-11) was downgraded to a radiation area, the licensee chose to keep the door propped open, causing the alarm light to be continually on. When asked about this, the two health physics technicians indicated that the lights were of little use anyway, as most plant staff would not notice them. Plant management indicated that this was an issue that they would look into, and will be further examined by the inspector during a future inspection.
The inspectors also observed a shipment of radwaste made by the licensee on April 13. This shipment consisted of 177.5 cubic feet of high activity dry active wastes (DAW) shipped in a wide mouth liner and transported in an NRC-approved 14-195 shipping cask. Shipment activities involved members of the Decon and Shipping and Health Physics Sections of the RES Department, together with surveillances provided by the Quality Assurance Department. These activities were conducted in accordance with plant procedures and the appropriate regulatory requirements found in 49 CFR Parts 100-177 and 10 CFR Parts 20, 61 and 71.
Since the last inspection of this area, the licensee has made significant inroads into reducing the total contaminated areas in the plant. In February 1993, the
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total contaminated area represented approximately 15% of the plant, while as i
of April 14,1993 the total contaminated area was at 7.6%. A significant portion of these results arose from the licensee's decontamination efforts on the refuel floor and in the torus room. While significant areas of the refuel floor remain posted as contaminated areas, much of this was attributable to the large amount of outage related equipment in storage at this location.
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As part of this inspection, the following procedures were reviewed:
RPP-10, Rev 3, " Operation of the RES Department Issue Room" l
RPP-23, Rev 0, " Hot Spot Tracking Procedure"
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RPP-24, Rev 0, " Radiological Survey Documentation" i
RPP-25, Rev 0, " Radiation Survey Techniques" RPP-26, Rev 0, " Contamination Survey Techniques" RPP-27, Rev 0, " Airborne Radioactivity Survey Techniques" These procedures were determined to accurately reflect the licensee's radiation
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protection program.
The inspectors also reviewed the licensee's most recent audit of the radiation protection program, conducted late in 1992, covering the Radiation Work Permit Procedure (Audit No. 794, dated December 17,1992). This comprehensive performance based audit identified several areas of significant concern involving the Radiation Work Permit (RWP) process, including the identification of five Adverse Quality Condition Reports (AQCRs) and 17 recommendations. The RES Department has committed to correct the issues involved in the five AQCRs by June 30,1993. These corrective actions will be reviewed during a future inspection.
3.2 Respiratory Protection In order to determine whether the licensee had established a respiratory protection program in accordance with federal regulations, the inspectors reviewed procedures, reviewed records, and toured the respirator repair / test facility. In addition, the inspectors observed a class provided on respiratory training. The inspectors were unable to observe fit testing or respirator repair / testing.
j The Instrument and Respiratory Supervisor was responsible for the respiratory
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protection program. The Radiological Engineering General Supervisor was l
t responsible for the station's internal dose estimation program and reported to
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the RES Manager.
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The inspectors reviewed the following documents pertaining to the licensee's t
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respiratory protection program.
RPP-6, Rev 16, " Respiratory Protection Procedure" j
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RPP-12, Rev 2, " Inspection and Quality Assurance of Respiratory Protection
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Equipment" l
RTP-44, Rev 2, " Respirator Test Device TDA-2ENB Operation and-i Calibration" l
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RTP-45, Rev 9, "Q127 DOP Penetrometer Operation"
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RTP-59, Rev 0, " Portable Ventilation Systems" PDP-15, Rev 1, " Standup Whole Body Counter Operation and Calibration"
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ITP-14, Rev 7, " Respiratory Protection Training"
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Respiratory Protection Study Guide,9/24/92 Training Department Standing Order (TDSO) No. 2A, "TDA-52 Computerized, Dual Quantitative Fit Tester," Revision 1,12/2/92 i
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TDSO No. 2B, "TDA-52 Computerized, Dual Quantitative Fit Tester,"
Revision 0, 7/2/92 These documents were determined to accurately reflect the licensee's respiratory protection program.
The licensee required that an individual pass a physical, receive training, demonstrate sufficient knowledge through testing, determine an individual specific respirator fitting factor, and be clean shaven prior to wearing respiratory protection equipment. The licensee maintained medical exam results in each individual's exposure file. Inspector review of the training class found that appropriate training materials were provided, sufficient l
demonstration was given (inspecting and donning equipment), and that sufficient depth was provided by the lecture. Inspector review of the post-training test found it thorough and challenging (licensee criteria for passing was 80%).
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Procedure RTP-44 directed an annual calibration of the TDA-2EN Particulate Detector Apparatus and quarterly calibration of the TDA-2ENB test bench.
Procedure RTP-45 directed an annual calibration of the percent penetration meter, annual calibration of the mechanical analyzer, and biennial calibration of the system magnehelic (a device used for measuring filter resistance). The licensee contracted these calibrations to a vendor (Air Techniques) and inspector review verified that these instruments had been calibrated in accordance with RTP-44 and RTP-45.
3.3 Instrumentation The licensee's program for instrumentation 21ibration was under the direction of the Instrument and Respiratory Supervisor, who reported through the Radiological Engineering General Supervisor to the Radiological and Environmental Services Manager. Repair of defective survey, frisker and other portable radiation instrumentation was the responsibility of the Instrumentation and Controls Department.
The licensee maintained an adequate inventory of survey instrumentation including ion chambers, G-M survey instruments, portable friskers, frisking booths, neutron instrumentation, radiation area monitors and air samplers. For the calibration of most of the survey instruments, the licensee utilized two JL Shepherd cesium-137 irradiators. Survey instruments were calibrated on a quarterly basis, to within +/- 10% of the known value. The known value was determined by decay-correcting the dose rate data provided with the irradiator at the time of purchase.
Neutron instrumentation was calibrated on a quarterly basis by submission to the Eberline Instrument Company. Frisker booth equipment, specifically Nuclear Enterprises detectors, were calibrated on a quarterly basis, and the licensee had recently purchased a set of technicium-99 standards for this purpose.
As part of this inspection, the following procedures were reviewed:
RTP-9, Rev 3, "RO-7 Operation and Calibration" RTP-28, Rev 4, "E-520 Operation and Calibration" RTP-43, Rev 3, "E-530N Operation and Calibration" RTP-56, Rev 3, "Eberline RO-2A Operation and Calibration" These procedures were determined to accurately reflect the licensee's
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instrumentation program.
3.4 Dosimetrv A review of the personnel dosimetry program used on-site was conducted during this inspection. The licensee used SRDs in addition to the dosimetry of record. The program was headed by the Dosimetry Supervisor who reported to the Radiological Engineering General Supervisor.
As part of this inspection, the following procedures were reviewed:
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l PDP-1, Rev 7, " Dosimetry Records Procedure" PDP-5, Rev 5, " Extremity Badge Issue and Control" PDP-7, Rev 7, " Dosimetry System Calibration and Quality Control Procedure" l
PDP-9, Rev 3, " Internal Dosimetry" PDP-14, Rev 1, " Multiple TLD Issue"
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PDP-16, Rev 0, "New Equipment Acceptance Inspection" These procedures were determined to accurately reflect the licensee's external and internal dosimetry program.
The licensee was accredited by the National Voluntary Laboratory Accreditation Program (NVLAP) in all test categories with the exception of Category VIII (the mixed neutron plus high energy gamma radiation category),
which was performed by a vendor laboratory. On-site assessment of the program by NVLAP was conducted September 29-30,1992. The Radiological Engineering General Supervisor was designated as laboratory official. One deficiency was identified concerning the lack of backup TLD processing capability; the licensee addressed this concern by upgrading / repairing an existing inoperable UD-710 reader.
The licensee used a vendor (Landauer, Inc.) to provide neutron dosimetry services. The licensee maintained and evaluated the extremity dosimetry (Panasonic UD-807) used at the station.
The licensee used a 1.2 Ci Cs-137, Amersham Type X.9 capsule source to calibrate their dosimetry (TLDs and SRDs). The licensee conducted source calibration on October 31,1984 to maintain NIST traceability (using a secondary traced detector).
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The Dosimetry Supervisor planned the following additional program improvements:
e The licensee was in the process of acquiring an additional UD-710A reader, The licensee planned to move dosimetry services to a new office which e
will provide additional dedicated office space.
A new computerized digital alarming dosimeter and dose tracking e
system was under evaluation.
The Dosimetry Supervisor has established a quarterly TLD Quality Control (QC) surveillance conducted by a vendor (Atlan-Tech) in a manner similar to that used by NVLAP (with the exception of test category VIII). The inspector reviewed the first quarter 1993 TLD QC surveillance results; no inadequacies were identified.
The inspector reviewed Radiological Technical Information Document (RTID)92-012, " Elemental Response of Panasonic UD-812 TLD to Radiation." This study was used to determine new element correction factors. No inadequacies were found.
The inspectors reviewed the 1992 Personnel Contamination incidents (PCI) log generated per RPP-2. There were no personnel contaminations which caused exposure of regulatory significance or which required more detailed evaluation per PDP-11, " Dose Assessment of Personnel Contamination Incidents." The licensee had established a PCI goal of 25 events for the first quarter of 1993.
At the time of the inspection, no PCIs had occurred in 1993.
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Procedure PDP-15 required daily source checking (with Eu-152 source),
annual full width half maximum calibration, and efficiency calibration for the standup whole body counter. Inspector review found no standup whole body counter calibration inadequacies. The inspector reviewed selected entries into j
the daily source check log to determine whether source checking had been conducted in accordance with PDP-15. No inadequacies were found.
3.5 Training The licensee's health physics technician training has undergone significant changes during the past year. New personnel have been hired as the Program Administrator and Lead Training Instructor, while the controlling program documents had been revised or were in the revision process at the time of this inspectio,
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Training of new health physics technicians was spread out over an approximately four year period, and consisted of: (1) 30 days of classroom lecture; (2) 72 days of classroom and laboratory; (3) six weeks of radiological protection skills training, both classroom and laboratory; (4) in-plant training sessions of a varying time frame, and (5) on-the-job training over the four-year training cycle. Continuing training for the health physics technicians consisted
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of several six-week training cycles during the year, including a cycle for General Employee Training, and a special one this year to discuss the new 10 CFR Part 20. For 1993, the licensee introduced systems based training, scheduling a total of 106 hours0.00123 days <br />0.0294 hours <br />1.752645e-4 weeks <br />4.0333e-5 months <br />, and covering Reactor Water Clean-Up (RWCU) and Liquid and Solid Radwaste systems so far this year.
4. Exit Interview The inspectors met with the licensee representatives denoted in Section 1 at the conclusion of the inspection on April 16, 1993. The inspector summarized the purpose, scope and findings of the inspection.
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