IR 05000156/1980004
| ML19338E660 | |
| Person / Time | |
|---|---|
| Site: | University of Wisconsin, 07000134 |
| Issue date: | 08/26/1980 |
| From: | Bovendale P, Fisher W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19338E657 | List: |
| References | |
| 50-156-80-04, 50-156-80-4, 70-0134-80-02, 70-134-80-2, NUDOCS 8010030519 | |
| Download: ML19338E660 (5) | |
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NUCLEAR REGULATORY COMMISSION
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OFFICE OF INSPECTION AND ENFORCEMENT J
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REGION III
Report Nos. 50-156/80-04; 70-134/80-02
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Docket Nos. 50-156;70-134 License Nos. R-74; SNM-116
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Licensee: University of Wisconsin Madison, Wisconsin 53705
Facility Name: University of Wisconsin Nuclear Reactor
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l Inspection At: Madison, Wisconsin s
Inspection Conducted: August 11-12, 1980 4.fG.x Inspector:h.C.Lovendale 8[46/fC
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Date Sig'ned Approved By:
W. L. Fisher, Chief Ar/2L6j/JFO
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Fuel Facility Projects and Date Sighed Radiation Support Section i
i Inspection Summary s
j Inspection on August 11-12, 1980 (Report Nos. 50-156/80-04; 70-134/80-02)
Areas Inspected: Routine, unannounced inspection of radiation protection and radwaste management program, including: qualifications; audits; training; radiation protection procedures; instruments and equipment; exposure control; posting, labeling, and control; surveys; notifications g
and reports;-effluent controls; solid radioactive waste; and transporta-
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i tion activities. The inspection involved ten inspector-hours on site by
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Results: No items of noncompliance or deviations were identified.
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i DETAILS 1.
Persons Contacted
- R. J. Cashwell, Supervisor, Nuclear Reactor
- S. M. Matusewic, Senior Reactor Operator
- M. Baumann, University Health Physicist
- Denotes those present at the exit interview.
2.
General This inspection, which began at 10:00 a.m. on August 11, 1980, with visual observation of facilities and equipment, posting and labeling, and access controls, was conducted to examine the radiation protection and radwaste aspects of routine facility operations. No problems were noted during the facility tour.
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Radiation Protection Organization Health physics functions at the reactor facility are performed by the reactor operators.
Routine surveys, sample collection and analysis, and calibrations are performed on an assigned basis in accordance with UWNR-100. There are five reactor operators, three of whom are senior reactor operators. A University health physicist audits the results of the operator's surveys and conducts a facility tour monthly.
No problems were noted.
4.
Logs and Records The following logs and records were reviewed:
a.
Annual Operating Report for Fiscal Year 1979-1980.
b.
Minutes of Reactor Safety Committee Meetings from May 1979 to date.
c.
Monthly Surveillance Checksheets from June 1979 to July 1980, d.
Transfer of Radioisotopes from R-74 to the broad license from June 1979 to date.
e.
Monthly Personal Exposure Reports from vendor for May 1979
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through June 1980, f.
Operating Logs from June 1979 to date.
5.
Audits A designated University health physicist audits the reactor radiation safety program monthly and incorporates the results into the minutes of the Reactor Safety Committee meetings.
No items requiring corree-tive action were identified during these audits.
No items of noncompliance were identified.
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6.
Training Radiation protection and radwc.;te hand 1fng are incorporated into training reactor operators.
Experimenters and laboratory instructors are trained in accordance with 10 CFR 19 and records of this training are maintained. Students do not receive a comprehensive health physics orientation, but do receive instruction on evacuation procedures and radioactive material handling. Students are under the direct super-vision of staff personnel while in the reactor facility.
No items of noncompliance were identified.
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7.
Instrumentation and Equipment The inspector reviewed records which indicated compliance with the following technical specification requirements; no problems were noted.
a.
Control room readout instrumentation required by Technical Specification 5.4.a and 5.4.b.
b.
Ventilation system operability checks required by Technical Specification 4.2.4.
c.
. ?bration and operability checks required by Technical Spet(fication 4.2.3.
d.
Operability of area radiation and gaseous effluent monitors required by Technical Specification 3.4.
Theinspectornotedthatonlyoneportablesurveyinstrumentgdbeen calibrated on the high range scale since the last inspection.-
This instrument was located near the reactor bridge, where it could not be utilized during an emergency.
Thelackofcalibratedhighrangesurveyinstrgentshasbeenaconcern expressed in IE Inspection Reports since 1977.-
The licensee stated that delays in completion of a calibration facility have hampered their ability to calibrate high range instruments. This matter was discussed with licensee representatives during the exit interview and during subsequent phone conversations on August 18, 1980. This matter will be reviewed during a future inspection.
No items of noncompliance were identified.
8.
Exposure Control The inspector reviewed the licensee's monthly personal dosimetry records for the period May 1979 through June 1980. No problems were noted. The maximum whole body dose for CY 1979 was 140 mrems and the maximum skin dose was 170 mrems. The maximum extremity dose
IE Inspection keport 50-156/79-02
- IE Inspection Reports 50-156/77-02, 50-156/78-02, 50-156/79-02-3-l
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was 60 mrems. Records and conversations with the reactor supervisor i
indicate there have been no neutron exposures to date.
The licensee is presently using Landauer Track-Etch dosimeters for neutron dosimetry in lieu of NTA film, which was previously used.
No items of noncompliance were identified.
9.
Surveys The inspector reviewed the results of contamination and. radiation surveys for the period June 1977 through July 1980.
It was noted that smears are taken at predetermined locations only. The inspector pointed out that areas of contamination may go undetected if occasional smears are not taken in low suspect areas. This item was discussed during the exit interview.
The inspector reviewed records of air and water sampling for the period June 1979 through July 1980. No problems were noted.
No items of noncompliant.e were identified.
10.
Notifications and Reports l
A review of records and discussions with licensee representatives indicated that the licensee has complied with 10 CFR 19 and 10 CFR 20 reporting requirements.
No items of noncompliance were identified.
11.
Radioactive Waste Management a.
Solid Radioactive Waste Solid radwaste generated at the reactor facility is transferred to the University Health Physics Office, which is responsible for packaging the waste for shipment to a burial site.
It was noted that no transfers of solid radwaste occurred during FY 1979.
The inspector reviewed the licensee's response to IE Bulletin 79-19 and is satisfied that proper action has been taken. No problems were noted.
b.
Liquid Radioactive Waste There have been four liquid radwaste releases to the sanitary sewer since the last inspection. The total activity discharged was 582 microcuries. No problems were noted.
c.
Gaseous Radioactive Waste Gaseous radioactivity in the stack effluent is measured by the stack monitor. The total activity discharge during FY 1979 was-4-
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2.68 curies, all argon-41. No particulate discharges exceeded background during this period. No problems were noted.
No items of noncompliance were identified.
12.
Radiation Protection Procedures All procedures are reviewed annually by the Reactor Supervisor and revised as needed. Revised procedures are presented to the Reactor Safety Committee for approval. The inspector selectively reviewed
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procedures that have been revised since the last inspection. No problems were noted.
13.
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All sources held under this license are stored and used in the i
reactor building. Review of leak test and accountability records indicate that the licensee is satisfying license requirements.
No items of noncompliance were identified.
14.
Transportation Activities The licensee stated that radioactive material has not been shipped from the reactor facility for a number of years. No spent reactor fuel has been shipped since the early sixties. The licensee maintains current copies of DOT and NRC regulations concerning the transportation of radioactive materials in the unlikely event that they are needed.
The licensee also stated that they actively discourage shipping radio-active material from the facility.
No items of noncompliance were identified.
15.
Exit Interview The inspector met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection on August 12, 1980. The following items were discussed:
a.
The purpose and scope of the inspection.
b.
The problems associated with the contamination surveys (Paragraph 9).
The Reactor Supervisor stated that he would consider the inspector's comment.
c.
The continuing lack of portable survey instruments that are calibrated at high range for emergency use (Paragraph 7).
The licensee stated that construction of the calibration facility would be completed by November 14, 1980, and that they would start calibrating portable survey instruments at higher ranges by December 31, 1980.
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