IR 05000282/1980002
| ML19305B854 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 01/30/1980 |
| From: | Dubry N, Fisher W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19305B850 | List: |
| References | |
| 50-282-80-02, 50-282-80-2, 50-306-80-02, 50-306-80-2, NUDOCS 8003200488 | |
| Download: ML19305B854 (10) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-282/80-02; 50-306/80-02 Docket No. 50-282; 50-306 License No. DPR-42; DPR-60 Licensee: Northern States Power Company 414 Nicollet Mall Minneapolis, MN 55401 Facility Name: Prairie Island Nuclear Generating Station Units 1 and 2 Inspection At: Prairie Island Site, Red Wing, MN Inspection Conducted: January 8-10, 1980 Inspector: N
[h W fc4 Approved By:
W. L. 'Fis er, Chief
/ j/ PQ/2F 49 Fuel Facility Projects and Radiation Support Section Inspection Summary:
Inspection on January 8-10, 1980 (Report No 50-282/80-02; 50-306/80-02 Areas Inspected: Routine, unannounced inspection of the radiation pro-tection program for operation and refueling, including:
qualifications; licensee audits; training; radiation protection procedures; advance plan-ning and preparation for refueling; instruments and equipment; exposure control; posting, labeling, and control; notifications and reports; IE Bulletin 79-19; and surveys. The inspection involved 25 inspector-hours on site by one NRC inspector.
Results: Of the eleven areas inspected, no items of noncompliance or deviations were identified.
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DETAILS
1.
Persons Contacted
- E. L. Watzl, Superintendent
- D. A. Schuelke, Superintendent of Radiation Protection R. A. Stenroos, Assistant Radiation Protection Supervisor
- A. A. Hunstad, Staff Engineer
- A.
C. Johnson, Radiation Protection Coordinator
- T. E. Finholm, Training Supervisor J. T. Linville, Plant Chemist
- C. D. Feierabend, NRC Resident Inspector i
The inspector also talked with other licensee employees, including members of the technical staff and contract personnel.
- Denotes those present at exit interview.
2.
General l
This inspection began at 10:45 a.m. on January 8,1980. On arrival, Unit I was operating at power and Unit 2 was shut down for the re-fueling outage. A tour and observation of the facility at the beginning of the inspection included access control and the radwaste, auxiliary service building, and Unit 2 containment.
Special emphasis was given to areas of work for the refueling outage. During the tour, the inspector made independent survey measurements using a licensee's meter (PIC-6, No. 449, calibrated December 1979). Measure-ments made during the tour were in agreement with posted survey data.
Subsequent tours inc1rded the control room and turbine building, where radiation monitors and remote counting stations were located.
The plant appeared more cluttered than during previous inspections due to the heavy workload during this outage. However, no significant problems or fire hazards were observed and housekeeping in general appeared adequate.
3.
Licensee Actions on Previous Inspection Findings Most portable survey instruments-had been repaired and returned to service.
(Paragraph 8).
4.
Radiation Protection Organization and Qualifications Theradiationprotectiongroup'sorganigptionalstructureisasdea-cribed in a previous inspection report.-
A new Radiation and CF
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istry Specialist has recently been hired and is progressing through
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the training program. The individual has had previous nuclear power i
plant experience.
1/- IE Inspection Report No. 50-282/79-24; 50-306/79-30.
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The licensee contracted with Nuclear Support Services for the assist-
ance of nine senior and five junior health physics technicians during the current outage. The criteria for hir physicistsisasdescribedinapreviousreport.jpgcontracthealth No problems were found in this area.
5.
Audits The Safety Audit Committee's (SAC) Audit Report No. P-79-1, dated December 12, 1979, and minutes for committee meetings of February 6, 1979, June 13-14, 1979, and September 26-27, 1979, were reviewed.
Significant radiation protection items covered by the audit included the ALARA concepts of tracking sources of exposure during refueling outages to identify areas where exposure reduction efforts would be most effective, and what effect hydrogen peroxide injection into primary systems had in reducing exposures during outages.
A subsection of audit report P-79-1 includes the results of the September 12, 1979, audit by the Nuclear Safety and Technical Services Engineer in response to IE Bulletin 79-19.
The results of this audit formed part of the licensee's response letter of September 21, 1979, to the Commission concerning IE Bulletin 79-19.
No problems were found in this area.
The audit report also indicated areas of concern in the source inventory and survey accuracy and timeliness, and suggested a need to review and possibly revise the Chemistry Counting Manual. These areas will be looked at during a future inspection.
No items of noncompliance or deviations were identified by the inspector.
6.
Training l
The inspector attended the General Training, Radiation Protection Training, and Respiratory Protection Training sessions and completed the exams at the end of the classes on January 9,1980.
Parts I and II have new slide preparations and the general training manuals were revised in January 1980. The narrative portion of the classes cover those items not handled in the slide presentation, including a brief handling of topics from IE Bulletin 79-19.
Part III, Respiratory Protection, is the same as described in a previous inspection report.3/
The film used in this portion is no longer curren+ nd an extensive explanation of plant equipment is needed after i presentation.
Discussions with licensee representatives indic r they are planning to revise this portion of the training when tir s available. This
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matter was discussed during the exit interview 2/ Ibid.
3/ IE Inspection Report 50-282/78-18; 50-306//8-18.
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Routine training at Prairie Island is held weekly for new personnel.
-During outages, training sessions are held daily. Refresher training is conducted annually. Records of initial training and/or annual retraining were reviewed for several people selected at random from among contractor and company employees.
Records were available and indicated non-Prairie Island personnel retraining was being accom-plished annually.
But a few Prairie Island personnel had not attended annual retraining even though special memos had been issued by the Training Supervisor regarding this matter.
This subject was discussed at the exit interview.
Records indicated approximately 200 Prairie Island personnel and about 2000 other personnel had gone through the training program in 1979. Approximately 300 persons had received training from December 26, 1979, to the present for the current refueling and maintenance outage.
No items of noncompliance or deviations were found.
7.
Radiation Protection Procedures The RadiatiogjSafety Manual (RSM) was reviewed for completeness and new changes.-
Temporary Memo No. TM-80-2 has been issued to reflect the licensee's use of a hood in the respiratory protection program.
During the exit meeting, revision to the respiratory protection por-tion of the RSM which would describe the current program and equipment was discussed.
The following revisions to Section Work Instructions in Radiation Protection (SWI-RP) were reviewed for compatibility with Technical Specifications.
SWI-RP-2 Rev. 17, October 16, 1979
" Routine Sampling Schedule" SWI-RP-8 Rev. 8, October 16, 1979
" Effluent Surveillance Form Preparation" SWI-RP-4 Rev. 18 September 12, 1979
" Work Assignments" SWI-RP-17 Rev. 6 October 16, 1979
" Calculating Radio-Activity Released from Containment Purge" SWI-RP-28 Rev. 2, October 25, 1979
" Quality Assurance for Instrumentation" No problems were found in this area.
4/ IE Inspection Report 50-282/79-24; 50-306/79-20.
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8.
Instruments and Equipment A review of calibration dates and records from October 1979 to the present was conducted for portable and fixed devices.
It was noted that most of the portable devices out of service or in need of repair have been fixed, recalibrated, and returned to service.5/
A review of the monthly functional tests, Test 1028, for October and November 1979, and Test 1027, " Refueling Calibration and Checkpoint Test," of radiation monitoring instrumentation was done by the inspector.
Follow up of identified items with licensee representa-tives found that 1R19, Unit 1 S/G Blowdown Liquid Monitor, was alarming due to the recent tube rupture contamination; therefore, the licensee has adjusted the alarm point to a setting just over the radiation levels being experienced. This was done to ensure that in the event of another S/G tube rupture an identifying alarm would be received. The licensee also identified a procedural problem for R-41 " Waste Gas High Activity Loop Inventory Monitor." Personnel stated the procedure was being prepared but had to be delayed for final review because of the preparation of the TMI Emergency Response Plan upgrade. No problems were found in this area.
The status of monitors R43-R47 is still as previously reported.6/
The in-containment high radiation monitor status reviewed in the above report has changed. The licensee representatives indicated that the detectors have been reordered because the previous vendor's detectors could not meet the desired design criteria.
The licensee stated this should not affect the installation date.
The licensee recently completed modifications to the Auxiliary Building ventilation system monitoring.
Each stack is equipped with a low range and high range monitor, with overlap, including a charcoal and particulate filter. At present, the monitoring is done by portable detection devices with capability to 1E05jtCi/cc.
Licensee representatives indicated that by approximately March 1980 there are plans to have a permanent detector assembly with capability to 1E07,pq Ci/cc installed.
The licensee has recently constructed a mobile counting trailer complete with a multichannel analyzer (MCA) and a GeLi detection system. This trailer provides the licensee with a backup to the normal counting room.
It gives the licensee a counting capability offsite in case of an accident (the trailer plugs into 220 VAC service and there are tentative plans to put a generator on the i
trailer). Via a horizontal GeLi detector assembly, the licensee can analyze radwaste containers, which are ready for shipping, for qualitative identification of nuclides; and by use of the horizontal detector configuration, he gained a high level sample counting capability.
No items of noncompliance or deviations were identified in this area.
S/ Ibid.
6/ Ibid.
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o 9.
Exposure Control a.
External Exposure External exposure control dose records for September 1979 through November 1979 were reviewed. Special emphasis was given to those involved in the recent SG tube rupture outage and recovery operation. The highest individual whole body dose received through November 1979 was about 1960 mrem. The highest skin and extremity dose for an individual _through November 1979 has been about 2100 mrem. The norm for the few individuals exposed to neutrons is still approximately 30 mrem / month.
b.
Internal Exposure Internal exposure from tritium is evaluated by quarterly urin-alysis for individuals who have potential for exposure to the tritium. A review of the fourth quarter records of 1979 found the maximum body burden of tritium to be about 1%. The sampling period continues to be staggered such that about one third of the samples are collected and analyzed each month.
Internal exposure from gamma emitters was determined by whole body counting using a llelgeson "do-it-yourself" whole body counter.
The inspector's review of whole body count data from August 30, 1979, to December 31, 1979, identified no problems. The highest individual was approximately 5 flPC-hours.
Some elevated initial counts were due to external contamination.
Lower counts were obtained after decontamination.
The inspector verified that the respiratory protection program remains 7ssentiallyasdescribedinapreviousinspectionThe new respirator added report.7 was noted to be in use during the tour. The instructions, i
uses, and training for utilization of this hood were discussed with the licensee (Paragraphs 6 and 7).
No items of noncompliance or deviations were identified.
I 10.
ALARA ALARA (As Low As Reasonably Achievable) efforts were apparent in the following areas:
a.
ALARA continues to be considered in writing Radiation Work i
Permits (RWP's).
7/ IE Inspection Report 50-282/78-18; 50-306/78-18.
8/ IE Inspection Report 50-282/79-24; 50-306/79-20.
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b.
Concrete block shielding and movable lead plate room dividers
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are placed around radiation areas in containment to reduce ex-posure levels.
c.
A TV camera is used to remotely monitor eddy current testing.
d.
New eddy current test equipment allows operators to work remotely-from outside of containment.
A computerized progrom is being utilized to track sources of e.
exposure during refueling outage to identify areas where exposure reduction efforts would be most effective.
f.
The Radiation Protection Coordinator attended a " Radiation Exposure Management Seminar" in October 1979.
g.
The licensee will be trying a method of back-flushing the incore thimble tubes in an attempt to prevent future work in this area, which would result in higher personnel exposures.
h.
Pre-outage meetings in preparation for this refueling began in September; preliminary planning is in the initial phase for the next scheduled refueling outage.
i.
The licensee has constructed a mobile laboratory capable of counting and analyzing at remote locations and as a backup lab as needed.
j.
The licenset is redoing survey maps in a three dimensional format to help clarify radiation and contamination areas relative to equipment and location in the plant.
11.
Posting, Labeling, and Control The licensee's method to control radiation exposure at the reactor facility is to review the plant high radiation areas weekly and enter the results in the RWP's or EP's at access control. General and outstanding RWP's are updated weekly for contamination and exposure control. General area surveys are done daily and specific area surveys are done before RWP issuance and during the job.
High radiation areas were conspicuously posted with the proper information and access to these areas was controlled.
Containers observed had appropriate labeling.
Annual retraining of all plant personnel on general and radiation protection areas is required. Attendance at these sessions is documented. The 1979 records were reviewed by the inspector, who found that some personnel had not been to the retraining, even though an interoffice memo had been issued identifying said indivi-duals (Paragraph 6).
This matter was discussed at the exit interview.
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RWP's were reviewed for the period of October 12, 1979, to January 9,
1980, with emphasis on those RWP's generated associated with the steam generator tube rupture and the present refueling outage.
It was noted that significant maintenance, repair, and modification work had also been done in the radwaste building during this period.
It appeared that RWP's were being initiated and reviewed timely and that proper approval and radiation protection measures were being taken.
Theprocedureforcontrolandreuseop'toolswithfixedcontamination is as described in a previous report.-
No items of noncompliance or deviations were identified.
12.
Surveys Daily and special general area survey records for contamination and direct radiation were reviewed from October 12, 1979 to January 10, 1980. When elevated levels of radiation or contamination were identified, follow-up action appeared proper and timely.
Daily records of airborne surveys from the Continuous Air Monitors (CAM) were reviewed from October 12, 1979, to January 10, 1980.
Portable air sample survey records were also reviewed.
No items of noncompliance or deviations were identified.
13.
Notifications and Reports According to licensee representatives and verified to the extent of records reviewed by the inspector, the licensee has had no theft, loss, concentrations cf radioactive material, or overexposure of personnel requiring reporting pursuant to 10 CFR 20.402, 20.403, 20.405, or other reporting requirements. A review of licensee's records indicate reports to the Commission were made timely and in accord with 10 CFR 20.403.
A sampling of employee records showed that reports of personal ex-posure are being submitted to the Commission as required by 10 CFR 20.408 for terminated employees and to individuals upon request, as required by 10 CFR 19.13.
No items of noncompliance or deviations were identified.
14.
Bulletins
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werereviewedbytheinspector.gsradiationprotectioninspection Items outstanding from the prev
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The annual retraining for the health physics group concerning shipping of Radioactive material was held November 8, 15, and 29, 1979, and December 6, 1979. The material 9/ IE Inspection Report 50-282/78-18; 50-306/78-18 (Control of Material).
10/ IE Inspection Report No. 50-282/79-24; 50-306/79-20.
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presented appeared adequate and review of attendance records verified o
that individuals who missed the formal training sessions studied the material presented.
The training neeled by employees regarding radioactive waste material has been incorpsrated into the slide presentation and lecture narrative of the General Employee Training Program.
The retraining program for operations personnel for the waste solidifica-tion system has not been developed at this time. This matter was discussed with the training coordinator and at the exit interview and will be looked at during a future inspection.
The licensee is presently hiring personnel who will set up and implement a quality assurance and control program at the Prairie Island facility. One of the areas they will review will be radio-active material handling and shipping activities at the site. This area will be followed during future inspections.
The inspector reviewed the results of the September 12, 1979, audit conducted by the Nuclear Safety and Technical Services Engineer.
No significant problems were noted in this area.
15.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection. The inspector summarized the scope and findings of the inspection.
The inspector stated that no items of noncompliance or deviations a.
were identified, b.
The inspector noted that some of the Prairie Island staff had failed to attend the annual general employee training. The licensee acknowledged these comments. This matter will be reviewed during a future inspection (Paragraph 6).
c.
The inspector reviewed the licensee's actions regarding lE Bulletin 79-19.
The revision to the General Employee Training Program
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manual had not been made. However, the subject was being very briefly handled in Part II of the training narrative lecture.
(Paragraph 6).
The co amitment to develop a retraining program for operations
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personnel for the waste solidification system was brought to the attention of the licensee representatives (Paragraph 14).
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The implementation'of a Quality Assurance and Control
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Program on site was discussed (Paragraph 14).
The licensee acknowledged these comments. These matters will L
be followed during a future inspection.
d.
The licensee representatives stated the narrative and attachment C in the Radiation Safety Manual will be revised to reflect the current respiratory protection program at this facility by June 1980.
(Paragraph 7).
e.
The inspector noted that the repair and calibration of portable survey instruments had been addressed.
(Paragraph 8).
f.
Changes to part III of the General Employee Training were dis-cussed.
(Paragraph 6).
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