IR 05000282/1993005
| ML20035A821 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 03/18/1993 |
| From: | Kozak T, Snell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20035A820 | List: |
| References | |
| 50-282-93-05, 50-282-93-5, 50-306-93-05, 50-306-93-5, NUDOCS 9303300014 | |
| Download: ML20035A821 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION.
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REGION III
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Reports No. 50-282/93005(DRSS); 50-306/93005(DRSS)
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e Dockets No. 50-282; 50-306 Licenses No. DPR-42; DPR-60 l
Licensee: Northern States Power Company
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414 Nicollet Hall
Minneapolis, MN 55401 Facility Name:
Prairie Island Nuclear Generating Plant Inspection At:
Prairie Island Site, Redwing, Minnesota
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Inspection Conducted: March 8 - 12, 1993 i
Inspector:
bM_. -
3/n b3
T. J(Jozak Date j
f Approved By:
LAM b A JA s/sh3 I
William Snell, Chief Date i
Radiological Controls Section 2
Insoection Summary Inspection on March 8-12. 1993 (Recorts No. 50-282/93005(DRSSh
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50-306/93005(DRSSJ1 Areas Inspected: Routine, announced inspection of the radiation protection program (Inspection Procedures (IPs) 83750, 84750, and 86750), including a j
review of:
licensee event report followup; organization; external exposure
control; internal exposure control; control of radioactive materials,
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contamination, and surveys; maintaining occupational exposures ALARA; and i
liquid solid and gaseous radioactive waste.
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Results: The licensee's radiation protection program was very effective in
controlling radiological work and in protecting-the public health and safety.
Dose expended in 1992 was very low, especially considering that there were 166 i
outage days. Contamination control was also very good. Development of a s
source term reduction program continued and appeared to be heading in a
positive direction.
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9303300014 930324 PDR ADOCK 05000282
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e DETAILS l
1.
Persons Contacted i
Northern States Power Company
- K. Albrecht, General Superintendent, Engineering l
- G. Malinowski, Radiation Protection Supervisor
- P. Wildenborg, Plant Health Physicist
D. Schuelke, General Superintendent, Radiation Protection j
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l M. Dapas, Senior Resident Inspector l
- R. Bywater, Reactor Engineer j
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 March 12, 1993,
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2.
General
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This inspection was conducted to review aspects of the licensee's radiation protection program. The inspection included tours of
radiologically controlled areas in the auxiliary building and radwaste
i facilities, observations of work in progress, reviews of representative records, and discussions with licensee personnel. During performance of
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the tours, no significant access control, posting, or procedural adherence problems were noted.
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3.
Licensee Event Report (LER) Followup (IP 83750)
j (Closed) LER 282/91006: The radioactive waste building ventilation i
discharge continued following the placement of its associated noble gas monitor in the RESET position.
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While performing a daily radiation monitor surveillance, an operator
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discovered that the selector switch for radiation monitor R-35, Radwaste i
Building Ventilation Monitor, was in RESET.
The high radiation alarm
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function for R-35, which results in an isolation of the Radwaste
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Building Ventilation System, is inoperable with the selector switch in
this position. There are no other automatic actions associated with this monitor.
Immediate corrective actions included returning-the
switch to the OPERATE position.
It was determined that the switch was placed in RESET the previous day while an adjacent monitor was being
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serviced. A licensee review of surveys and an analysis of activities in
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the builiding during this timeframe indicated that no radioactive material release occurred while the monitor was in RESET. Therefore,
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sampling was not required. Corrective actions to prevent recurrence of-this event included adding a redundant high radiation alarm which is
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independent of the monitor's switch position to the Emergency Response l
Computer System for each monitor required by technical specifications
and tightening administrative controls regarding the removal of I
radiation monitors from service. This LER is closed.
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4.
External Exposure Control ilP 83750)
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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; and required-records, reports, and notifications.
i The inspector verified that there were no changes in the licensee's
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exposure evaluation, badge spiking, QA/QC, extremity, neutron, or multiple badge monitoring programs. The licensee plans to change TLD
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vendors later this year and will have dose reported for each of the categories listed in 10 CFR Part 20, Revision 1 (deep dose, shallow
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dose, and eye dose).
Vendor qualifications will be reviewed during a
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future inspection.
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The inspector reviewed calibration procedures for the electronic
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dosimeters in use to determine if software problems affecting the
calibration factor existed. No problems were noted. The electronic i
dosimeters were generally overestimating the dose measured with TLDs by
approximately ten percent. The licensee's vendor supplied exposure
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reports for 1992 were reviewed. No exposures greater than the
licensee's administrative limits or 10 CFR 20.101 requirements were
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noted and no reports or notifications were required due to external
radiation exposure to personnel.
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No violations or deviations were identified.
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Internal Exposure Control (IP 83750)
i The inspector reviewed the licensee's internal exposure control and assessment programs, including: changes to _ facilities, equipment, and procedures affecting internal exposure control and personal exposure assessment; determination whether respiratory equipment and assessment
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of individual intakes met regulatory requirements; and required records, reports, and notifications.
There were no major changes in the licensee's internal exposure control and assessment programs. The licensee uses engineering controls, i
surface and airborne radioactivity survey data, and respiratory protection to implement their internal exposure control program.
The licensee uses the PORTACOUNT system to determine fit factors for l
respiratory devices. The licensee recently reduced the fit factor
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acceptance value from 1,000 to 500 for air purifying respirators.
This meets regulatory guidance in this area and is acceptable.
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A review of whole body count and air sample records and discussions with licensee personnel indicated that no individual has been exposed to airborne radioactivity greater than the 40 MPC-hour investigation level requirement since the last radiation protection inspection. No reports i
or notifications were required due to personnel exposure to airborne radioactivity.
No violations or deviations were identified.
6.
Control of Radioactive Material and Contamination. Surveys. and
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Monitorino (IP 83750)
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The inspector reviewed the licensee's program for control of radioactive
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l materials and contamination, including:
adequacy of supply, maintenance, and calibration of contamination survey and monitoring-
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.
I The licensee's contamination monitoring devices remained essentially the
same as last reported. The licensee tracks personnel contaminations to determine problem areas and repeat offenders. There were 177 personnel contamination events (PCEs) in 1992 which represents excellent performance, considering the amount of outage time during the year. The inspector reviewed the contamination event report compiled by the licensee which listed the cause of each PCE and corrective actions which will be put in place to further reduce the number. Corrective actions l
focused on reducing residual contamination in laundered protective
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clothing.
The inspector accompanied an operator on a shiftly round in the auxiliary building in an effort to determine the radiological impact on The licensee conservatively posts areas as contamincted at his job.
100 disintegrations per minute per 100 square centimeters (dpm/100 cm')
which is just barely detectable using a hand held frisker.
Because of
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this conservative policy, several areas were permanently posted as contaminated. These areas were either_ separate rooms or were isolated from clean areas through the use of metal barriers.
Posted areas included the charging pumps, containment spray rooms, residual heat removal (RHR) pump pits, spent fuel pool area, and the filter room. All
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of these posted areas, with the exception of the RHR pit, had contamination levels less than 1,000 dpm/100 cm' which is the industry norm for posting contaminated areas. Protective clothing requirements
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to enter these areas included booties and surgeon's gloves which were j
located in bins at the entrance to each area. This was only a minor i
inconvenience for the operator during his rounds. The benefit of
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i posting these areas so conservatively was that low level contamination was not spread from these areas to the rest of the auxiliary building which keeps the percentage of clean area contaminations low.
No violations or deviations were identified.
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7.
Maintainino Occupational Exoosures ALARA (IP 83750)
i 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.
implementation; ALARA considerations for planned, maintenance, and
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refueling outages; worker awareness and involvement in the ALARA program; and establishment of goals and objectives, and effectiveness in
meeting them.
Total dose for 1992 was 211.240 person-rem which was very low considering that there were two refueling outages and a forced outage which totaled 166 outage days. The inspector reviewed the licensee's
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progress in establishing a cobalt reduction program. Since the last
inspection, a generic modification was started which will basically
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identify acceptable replacement parts for high cobalt materials in the primary system. Once completed, this modification will allow the generic inclusion of low cobalt materials in system modifications and
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replacement of high cobalt materials in existing systems. Up to now,
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each replacement project or new modification required a separate safety
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analysis which made it less likely that low cobalt materials would be used. This area will continue to be reviewed during future inspections.
fio violations or deviations were identified.
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Solid. Liouid and Gaseous Radioactive Waste (IPs 84750. 86750)
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The inspector reviewed the licensee's radioactive waste management program including data presented in the most recent semiannual effluent release report.
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The radioactive waste management program remained the same as reported l
during previous inspections. The inspector conducted verification
i calculations on two reporting periods for liquid and gaseous effluents contained in recent semiannual effluent release reports. The inspector-performed these calculations using the tiRC PCDOSE program which employs equations detailed in Regulatory Guide 1.109. All effluent calculations were within the factor of 2 comparative acceptance criteria.
l 110 violations or deviations were identified.
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9.
Exit Interview The inspector met with licensee representatives (denoted in Section 1)-
at the conclusion of the inspection on 14 arch 12,1993, to discuss-the i
scope and findings of the inspection.
During the exit interview, the inspector discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspectors during the inspection.
Licensee representatives did not identify any such documents or processes as proprietary. The inspector specifically discussed the following:
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f The excellent performance-during the previous year with regard to
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dose expenditure and PCEs.
'The continued development of the cobalt. reduction program,
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