IR 05000266/1993005
| ML20012G519 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/25/1993 |
| From: | Kozak T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20012G517 | List: |
| References | |
| 50-266-93-05, 50-266-93-5, 50-301-93-05, 50-301-93-5, NUDOCS 9303050039 | |
| Download: ML20012G519 (5) | |
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I U.S. NUCLEAR REGULATORY COMMISSION j
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REGION III
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Reports No. 50-266/93005(DRSS); 50-301/93005(DRSS)
Dockets No. 50-266; 50-301 License Nos. DPR-24; DPR-27
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i Licensee: Wisconsin Electric Power Company
231 West Michigan i
Milwaukee, WI 53201 i
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Facility Name:
Point Beach Nuclear Plant l
Inspection At: Two Rivers, Wisconsin Inspection Conducted:
February 1-5, 1993 i
Inspector:
ld$0l.SJ Ia 2A r/n T. J. Kozak
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Approved By:
(IIh[i$JB z/w/>3 William Snell, Chief Date i
Radiological Controls Section 2
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i Inspection Summary Inspection on February 1-5. 1993 (Reports No. 50-266/93005(DRSS):
l 50-301/93005(DRSS))
Areas Inspected:
Routine announced inspection of the radiation protection
program including: external exposure control, internal exposure control, control of radioactive materials and contamination, and maintaining occupational exposures as low as reasonably achievable (ALARA) (Inspection
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Procedure (IP) 83750).
Results: The licensee's radiation protection program appears to be very effective in controlling radiological work and in protecting the public health
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and safety.
Strengths included a continued downward trend in overall dose and i
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the contamination control program.
General housekeeping in the auxiliary building was good.
Extensive effort was expended during the past year to implement the requirements of 10 CFR Part 20, Revision 1, one year early on January 1, 1993. No major weaknesses were identified.
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9303050039 930225-PDR ADOCK 05000266 O
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DETAILS
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Persons Contacted
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- M. Baumann, Project Engineer, Radiological Engineering '
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- J. Becka, Manager - Regulatory and Support Services
J. Bevelacqua, Manager - Health Physics
W. Doolittle, Health Physics Specialist
- F. Flentjie, Administrative Specialist - Regulatory Services
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- T. Guay, Health Physics Supervisor G. Maxfield, Manager - Point Beach Nuclear Plant M. Moseman, Health Physics Specialist
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P. Scheffel, Supervisor, Health Physics Technician
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S. Thomas, Health Physics Specialist J. Gadzala, Resident Inspector
i The inspector also interviewed other licensee and contractor personnel during the course of the inspection.
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- Denotes those present at the exit meeting on February 5, 1993.
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2.
General i
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This inspection was conducted to review aspects of the licensee's
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radiation protection program. The inspection included tours of
radiologically controlled areas, the auxiliary building, and radwaste j
facilities, observations of licensee activities, reviews of
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representative records, and discussions with licensee personnel.
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3.
External Exoosure Control (83750)
The inspector reviewed the licensee's external exposure control and
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personal dosimetry program, including: changes in the program, use of dosimetry to determine whether requirements were met, planning and preparation for maintenance and refueling outage tasks including ALARA considerations, and required records, reports and notifications.
There were no significant changes to the external exposure control l
program. The licensee was in the process of testing electronic l
dosimeters in anticipation of plantwide use later this year.
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Observations of work in progress indicated that dosimetry was worn properly to adequately assess the dose received by workers.
Outage preparations with respect to ALARA improved during 1992.
Implementation of new work techniques and other dose saving ideas resulted in a third successive year in which there was a decline in
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overall dose expended which is commendable considering that the 1992 work scope was significantly greater than the previous few years. Total dose expended for the year was low at 256.42 person-rem. The licensee's goal for 1993 was established at 257.8 person-rem.
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Personnel exposure records for current and past licensee and contractor i
employees were selectively reviewed for completeness, accuracy and l
consistency.
In addition, reporting of exposure information was
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reviewed for timeliness. No exposures above 10 CFR 20.101 limits and no i
problems with the records for 1992 were noted. There were no
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significant hot particle events requiring dose calculations since the
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last inspection.
i No violations or deviations were identified.
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Internal EXDosure Control (IP 83750)
i The inspector reviewed the licensee's internal exposure control and i
assessment programs, including: changes to facilities, equipment, and i
procedures affecting internal exposure control and personal exposure
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assessment; determination of whether respiratory equipment and
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assessment of individeal intakes met regulatory requirements; and required records, reports, and notifications.
Respiratory protection procedures have been modified somewhat since the.
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last inspection due to the licenset's early implementation of 10 CFR i
Part 20, Revision 1 requirements.
I rocedure HP 4.2, Respiratory l
Protection Program For Radiological Hazards, provided general
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instruct %ns for the use of respirators. HP 4.4, Restriction Of
Internal Sose, provided instructions to ensure internal doses to workers
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remained within regulatory limits and that the total dose remained as
low as reasonably achievable. Basically, an evaluation of the controls
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to be used for minimizing internal dose was required to be performed for
each job specific radiation work permit which was completed. A flow chart was provided for use in this evaluation. No threshold was
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established below which an evaluation did not need to be performed.
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licensee established that internal doses exceeding 10 millirem per year j
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would be recorded.
Plans were to monitor all personnel entering t
cortaminated : areas for internal exposure to radiation.
No problems were l
noted.
Developments in this area will be monitored during future
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inspections.
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No violations or deviations were identified.
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5.
Control of Radioactive Material and Contamination (IP 83750)
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The inspector reviewed the licensee's program for control of radioactive -
materials and contamination, including:
adequacy of supply, maintenance and calibration of contamination survey and monitoring equipment;
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effectiveness of survey methods, practices, equipment and procedures; t
adequacy of review and dissemination of survey data; effectiveness of
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radioactive and contaminated material controls.
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The inspector verified by a review of records, discussions, with
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licensee personnel, and tours of operational areas that the supply,
maintenance, and performance checks of survey monitoring instruments.
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were accurate.
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The licensee's contamination control program remained effective as there
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were only 121 personnel contamination events (PCE's) greater than 100 counts per minute recorded in 1992. This is especially noteworthy i
considering that the requirement for wearing protective clothing in the l
auxiliary building was eliminated during the year without an appreciable
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increase in the number of PCE's. The modification in clothing l
requirements has reduced radioactive waste generation and time spent i
laundering protective clothing. Housekeeping in the auxiliary building remained good.
The licensee has developed a contaminated floor space report for use in tracking contaminated areas and assigning decontamination
responsibility. Significant progress has been made during the past year in improving personnel accessibility to safety related equipment through
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decontamination efforts. Cooperation in this effort was noted
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specifically from the Operations and Chemistry Departments in the most i
recent report.
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The inspector reviewed a 10 CFR 50.59 evaluation for storage of
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radioactive material in Warehouse 2.
No problems were noted. A tour of
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the area revealed that the warehouse contains clean equipment which will
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remain when the radioactive material is relocated to the area.
Plans
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were to erect a fence within the warehouse to contain the radioactive
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materici The licensee was aware of the strict controls required in
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areas containing both clean and contaminated equipment and of industry
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events in which radioactive material from similar types of areas was inadvertently shipped offsite as clean material.
It appeared that
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adequate controls would be in place to prevent similar events from
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occurring at Point Beach.
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No violations or deviations were identified.
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Maintainina Occupational Exposures At ARA (IP 83750)
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The inspector reviewed the licensee's program for maintaining I
occupational exposures ALARA, including: ALARA group staffing and
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qualification; changes in ALARA policy and procedures, and their
implementation; ALARA considerations for planned maintenance and l
refueling outages; worker awareness and involvement in the ALARA
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program; establishment of goals and objectives, and effectiveness in meeting them.
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I The ALARA group staffing was increased to include two permanent ALARA i
technicians.
The technicians were responsible for items such as pre-job i
ALARA reviews, dose tracking, and video recording of jobs.
This
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development should enhance preoutage preparations and contribute to
further reductions in the licensee's total dose.
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t Since the last inspection, the licensee has made progress in an ongoing
i reactor coolant system filtration enhancement project. At the time of
the inspection, a 2 micron absolute filter was in use for the Unit 2 i
reactor coolant pump seal water injection filter F-398. Approval has
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been obtained and plans are to install the same size filter in the Unit 2 gas stripper line.
Plans for similar modifications to Unit I are in the approval stage. The licensee plans to track the effectiveness of the enhanced filtration project with respect to dose savings and coolant activity reduction.
The licensee recently completed a study in which it was determined that approximately 90 percent of the total site dose can be attributed to the radiation from cobalt isotopes. This study was conducted to determine whether an engineering study to identify cost-effective cobalt reduction opportunities was warranted. The results indicated that the evaluation was warranted and plans were to initiate one soon. The results of the evaluation will be evaluated during a future inspection.
No violations or deviations were identified.
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Exit Interview i
The inspector met with licensee representatives (denoted in Section 1)
at the conclusion of the inspection on February 5,1993, to discuss the scope and findings of the inspection.
During the exit interview, the inspector discussed the likely
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informational content of the inspection report with regard to documents
or processes reviewed by the inspector during the inspection.
Licensee
representatives did not identify any such documents or processes as i
proprietary.
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