IR 05000266/1993008
| ML20035F509 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/16/1993 |
| From: | Kozak T, Snell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20035F506 | List: |
| References | |
| 50-266-93-08, 50-266-93-8, 50-301-93-08, 50-301-93-8, NUDOCS 9304210360 | |
| Download: ML20035F509 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
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Reports Nos. 50-266/93008(DRSS); 50-301/93008(DRSS)
Dockets No. 50-266; 50-301 Licenses No. DPR-24; DPR-27
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Licensee: Wisconsin Electric Power Company
231 West Michigan Milwaukee, WI 53201 Facility Name:
Point Beach Nuclear Plant Inspection At: Two Rivers, Wisconsin
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Inspection Conducted: March 29 - April 2, 1993 f
Inspector:
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l T.'J. (p2ak Date I Senior Radiation Specialist
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Approved By:
t J 00 1 K,#4 s/ic /n I
William Snell, Chief Date '
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Radiological Controls Section 2
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Inspection Summary Inspection on March 29 - April 2. 1993 (Recorts No. 50-266/93008(DRSS):
50-301/93008(ORSS))
Areas Inspected: Routine, announced inspection of the radiation protection program during a Unit I refueling outage including:
licensee action on previous inspection findings; organization, management controls and training;
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internal' exposure control; control of radioactive material and contamination; radioactive waste processing; and maintaining occupational exposures as low as reasonably achievable (ALARA) (Inspection Procedures (IP) 83750, 84750 and
86750).
- 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
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an excellent contamination control program. The radiological condition of the auxiliary building was good with safety related equipment being readily
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accessible. Training on 10 CFR Part 20, Revision I was excellent.
Development of the source term reduction program will continue to be
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monitored.
9304210360 930416 ADOCKOWOg6 PDR G
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DETAllS 1.
Persons Contacted Wisconsin Electric Company
- J. Becka, Manager - Regulatory and Support Services
- J. Bevelacqua, Manager - Health Physics W. Doolittle, Health Physics Specialist
- F. Flentjie, Administrative Specialist - Regulatory Services
- T. Guay, Health Physics Supervisor
- G. Maxfield, Manager - Point Beach Nuclear Plant M. Moseman, Health Physics Specialist P. Scheffel, Supervisor, Health Physics Technician S. Thomas, Health Physics Specialist Nuclear Reaulatory Commission
- K. Jury, Senior Resident Inspector J. Gadzala, Resident Inspector The inspector also interviewed other licensee and contractor personnel during the course of the inspection.
- Denotes those present at the exit meeting on April 2, 1993.
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General This inspection was conducted to review aspects of the licensee's radiation protection program during a Unit I refueling outage.
The inspection included tours of radiologically controlled areas, Unit I centainment, the auxiliary building, and radwaste facilities; observations of licensee activities; reviews of representative records; and discussions with licensee personnel.
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Licensee Action on Previous Insoection Findinas (IP 83750)
(Closed) Open Item (266/92019-01: 301/92019-01): The quality control requirements of 10 CFR 20.311 were implemented through the use of peer review of specified work activities. - While this meets the intent of the regulation, it was not documented that the licensee was using th:s form of quality control nor was there a written requirement for _it to.take
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place. Thus, it was possible for radwaste activities to occur without any quality control review. Appropriate radioactive material shipping -
procedures have been modified to require peer review and approval signatures on the shipping papers for radioactive material / waste shipments. This should ensure that the required reviews occur. This item is closed.
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Oraanization. Manaaement Controls and Trainina (IP 83750)
l The inspector reviewed the licensee's organization and management controls for the radiation protection program including:
organizational
structure, staffing, delineation of authority and management techniques
used to implement the program, and experience concerning self-i identification and correction of program implementation wea',nesses.
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The radiation protection technician staff was augmented by approximately 45 contract technicians for the Unit I refueling outage. Although the staff appeared to be qualified to accomplish their responsibilities,
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only a small percentage of the technicians previously worked at the
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station. The technicians were required to take and pass theory and site
specific examinations prior to performing work. The exams were t
challenging and appeared to be a good tool to assess the knowledge level I
of the technicians. No other organizational changes occurred since the
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last inspection.
l The inspector reviewed the contents of the 10 CFR Part 20, Revision 1 i
training class which has been presented to all licensee and contractor
personnel working at the site during the outage. The content and
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presentation of the class was excellent. The inspector found the
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radiation protection staff to be knowledgeable.about the changes in the
rule and that there was an understanding about the philosophy of maintaining the total effective dose ALARA.
i No violations or deviations were identified.
5.
Internal Exposure Control (IP 83750)
The inspector reviewed the licensee's internal exposure control and
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assessment programs, including: changes to facilities, equipment, and y
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procedures affecting internal exposure control and personal exposure assessment; determination whether respiratory equipment and assessment of individual intakes met regulatory requirements; and required records,
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reports, and notifications.
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There were no changes to facilities or procedures affecting internal
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exposure control since the last inspection. The inspector reviewed
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plans for use of respiratory protection equipment for radiological work during the Unit I refueling outage. The licensee performed a review of
all tasks where airborne contamination could be present.
Meetings-were
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conducted between Radiation Protection and members of each plant group
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that performed evolutions during which respiratory protection-has been
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used in the past. The meetings tried to identify potential airborne
hazards and determine whether additional engineering controls could be
applied to the jobs to reduce the need for respiratory protection while maintaining total worker exposure ALARA. This was a good, systematic
approach to the determination of whether or not respiratory equipment i
should be used. No problems were noted.
i No violations or deviations were identified.
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Control of Radioactive Material and Contamination (IP 83750)
The inspector reviewed the licensee's program for control of radioactive materials and contamination, including:
adequacy of supply,
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maintenance, and calibration of contamination survey and monitoring
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equipment; effectiveness of survey methods, practices, equipment, and procedures; adequacy of review and dissemination of survey data; and
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effectiveness of radioactive and contaminated material controls.
The inspector verified by a review of records, discussions, with licensee personnel, and tours of operational areas that the supply, maintenance, and performance checks of survey instruments were accurate.
f The inspector toured the auxiliary building to determine the impact that-the radiological condition had on day-to-day work activities.
Essentially, all safety related equipment was readily accessible to operators performing shiftly rounds. A contaminated square footage
report was generated monthly and was used to track these and other areas to ensure that areas that become contaminated areas were decontaminated in a timely manner.
No problems were noted.
No violations or deviations were identified.
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Radioactive Waste Processina (IP 84750. 86750)
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The inspector reviewed radioactive waste processing activities and
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effluent reports for 1992.
The licensee disposed of approximately 4,500 cubic feet of solid radioactive waste during the year.
Only a
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l partial shipment of waste was onsite at the time of the inspection. The
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licensee has estimated total waste disposal volume to be 4,000 cubic
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feet for the next 18 months. As described in previous reports, the i
licensee has been utilizing vendors to reach maximum reduction in waste
volumes.
Radwaste generation was reduced during 1992 through decreased use of protective clothing in the auxiliary building and increased
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sorting of waste at its generation.
l No violations or deviations were identified.
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8.
Maintainina Occupational Exposures ALARA (IP 83750)
The inspector reviewed the licensee's program for maintaining occupational exposures ALARA, including: ALARA group staffing and qualification; changes in ALARA policy and procedures, and their s
implementation; ALARA considerations for planned maintenance and refueling outages; worker awareness and involvement in the ALARA i
program; and establishment of goals and' objectives, and effectiveness in
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meeting them.
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Since the last inspection, the licensee has made progress in an ongoing
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reactor coolant letdown system filtration enhancement project.
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Unit, the letdown system has two reactor coolant pump seal water
injection (SWI) filters (F-39A and B), one gas stripper filter (F-60),
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and one letdown filter (F-1). Point Beach has been using 20 micron
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nominal filters in these housings. Modifications have been initiated to standardize these filter housings such that they accommodate one filter element. The modifications have been completed for F-39A and B and F-1
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on both Units.
Plans were to modify Unit 1 F-60 during the Unit 1 refueling outage and Unit 2 F-60 shortly thereafter. Upon completion of the F-60 modifications, a 2 micron absolute filter will be used in the housings. A 2 micron absolute filter was already in use in Unit 2
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F-398.
Plans were to install 2 micron absolute filters in the other SWI filter housings once the 20 micron nominal filters were expended. There were no plans to decrease either Unit's F-1 filter element from the 20 micron nominal rating. The licensee was not sure if there would be a dose rate reduction in the systems downstream of the filters as a result
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of the downsizing.
Plans were to track the downstream dose rates to l
determine the effectiveness of the filter size reduction.
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The ALARA group recommended actions to reduce dose based on a review of the last refueling outage activities. To improve efficiency for reactor coolant pump seal work, mock-up training was performed for this outage.
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The seal housing will be removed from the containment for disassembly,
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decontamination, and reassembly which should result in a dose. savings.
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The still video system has been expanded and pictures organized for easy assistance in planning for jobs such as insulation removal and piping support inspections. The ALARA group also developed a list of potential valve replacements which would be targeted during maintenance activities
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once a detailed source term reduction program is put in place.
Developments in this area will be followed during future inspections.
No violations or deviations were identified.
9.
Exit Interview
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The inspector met with licensee representatives (denoted in Section 1)
at the conclusion of the inspection on April 2,1993, to discuss the scope and findings of the inspection.
1 During the exit interview, the inspector discussed the likely
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r informational content of the inspection report with regard to documents
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or processes reviewed by the inspector during the inspection.
Licensee
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representatives did not identify any such documents or processes as
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proprietary. The inspector specifically addressed the following:
The source term reduction program and its continued development
The excellent 10 CFR Part 20, Revision 1 training class.
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