IR 05000156/1985003
| ML20198B218 | |
| Person / Time | |
|---|---|
| Site: | University of Wisconsin |
| Issue date: | 11/04/1985 |
| From: | Ridgway K, Schweibinz E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20198B217 | List: |
| References | |
| 50-156-85-03, 50-156-85-3, NUDOCS 8511060331 | |
| Download: ML20198B218 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-156/85003(DRP)
Docket No. 50-156 License No. R-74 Licensee: University of Wisconsin
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Facility Name: Nuclear Reactor Laboratory Inspection Conducted: October 23-25, 1985 k'.W (Etl Inspector: K.R.RidhR ay n/4 /s 5 Dat'e '
(S/hdjMugh Approved By: E. R. Schweibinz, Chief n /4 /ri Technical Support Staff Date'
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Inspection Summary Inspection on October 23-25, 1985 (Report No. 50-156/85003 (DRP))
Areas Inspected: Routine, unannounced inspection of records, logs, and organization; review and audit functions; requalification training; procedures; surveillance and maintenance; fuel handling activities; radiation protection;
.radwaste management control; transportation activities; and emergency plannin This inspection involved a total of 23 inspector-hours by one NRC inspecto Results: No violations or significant safety issues were identified in the areas inspected.
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DETAILS Persons Contacted
- R. J. Cashwell, Reactor Director
- S. M. Matusewic, Supervisor Nuclear Reactor J. Lorenz, University Health Physicist D. L. LeGare, Senior Reactor Operator R. M. Jones II, Reactor Operator
- Indicates those present at the exit intervie . General
- This inspection,'which began at 1:00 PM on October 23, 1985, was conducted to examine the research reactor program at the University of Wisconsi The facility was toured shortly after arrival. The inspector observed a reactor startup and an evacuation drill during the inspection. The general housekeeping of the facility-remains excellent, as was noted in the previous inspection (Inspection Report No. 50-156/84001(DRP)).
Operational activity at the reactor facility remains at the same level as during the previous inspectio The licensee had received the NRC show cause order to reduce the amount of high enriched fuel-(HEU) onsite to that amount necessary to maintain a normal schedule of operations. The licensee had responded in a letter
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dated October 19, 1985 with several questions concerning the definition of unirradiated vs irradiated fuel, what constituted a " fuel element" (the Wisconsin Reactor utilizes four modified TRIGA fuel elements in a fixed bundle), and if Type B shipping containers are to be used, can the license 2 be exempted from an approved quality assurance (QA) plan as requi'ed by-10 CFR 71.12(b). The licensee also stated they would not be able to comply with the 120 day limit of the order because shipping containers are not available, they do not have an approved QA plan, and the 180 day leeway required for receiver notification of the shipment could not be made prior to the resolution of the above question . Organization, Logs and Records (40750)
The facility organization was reviewed and verified to be consistent with the Technical Specifications and/or Safety Analysis Report (SAR). The minimcm staffing requirements were verified to be present during reactor and fuel handling operation The reactor logs'and records were reviewed to verify that: Records were available for inspectio Required entries were mad Significant problems or incidents were documente , _ _ .. _ ,
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, The-facility was being maintained properl Records were found to be complete and provided adequate information in all area ~
Two Reactor Operators had received license ~s since.the last inspectio The licensed organization now consists of four Senior and three Reactor Operator No violations or deviations were identifie . Reviews and Audits (40750)
The licensee's review and audit program records were examined by the inspector to verify that: Reviews of facility changes, operating and maintenance procedures, design changes, and unreviewed experiments had been conducted by a safety review committee as required by Technical Specifications or SA b .- That the review committee and/or subcommittees were composed of qualified, members and that quorum requirements and frequency of meetings had been me Required safety audits had been conducted in accordance with
. Technical Specification requirements and that any identified problems were resolve A. review of the. semiannual Reactor Safety Committee meeting minutes indicated the committee had been meeting all requirement . Monthly audits of facility records and conditions had been conducted by a member of the University Radiation Safety Offic No violations or deviations were identifie ' Requalification Training (40750)
The inspector reviewed procedures, logs, and training records; and interviewed personnel to verify that the requalification training program was being carried out in conformance with the facility's approved plan and NRC Regulations. Requalification examinations have been conducted annually as required and were of adequate dept Experience records and performance evaluations'were also documented.
.No violations or deviations were identified.
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, P_rocedures (40750)
The inspector reviewed the licensee's procedures to determine if-procedures were issued, reviewed, changed or updated, and approved in accordance with Technical Specifications and SAR requirements. This review also verified: That procedure content was adequate to safely operate, refuel and-maintain the facilit That responsibilities were clearly define That' required checklists and forms were use 'The' inspector determined that the required procedures available at the control console had been reviewed annually and the procedure contents were adequat No violations or deviations were identifie . Surveillance (40750)
-The inspector reviewed procedures, surveillance test schedules and test'
records, and discussed the surveillance program with responsible personnel to verify: That, when necessary, procedures were available and adequate to perform test That tests were completed within the required time schedul Test records were availabl "
Surveillance records since the last-inspection indicated that all checks
.had been completed at the. required frequencie No violations or deviations were identifie . Experiments (40750)
The inspector verified by reviewing experiment records and other reactor logs that: Experiments were conducted using approved procedures and under approved reactor condition New experiments or changes in experiments were properly reviewed and approve The experiments did not involve an unreviewed safety question, i.e.,
10 CfR 50.59 requirements regarding experiments were met.
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, Experiments. involving potential hazards or reactivity changes were~ .
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. identified in procedures; Reactivity limits were not or could not have been exceeded during an experimen The inspector reviewed the one experiment approved since
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.the last. inspectio No.newfexperiments'had been conducted;.however, two beam ports have been
- equipped with external' shielding to provide an irradiation facility to study the effects'of fast neutrons on animal tissues. A Modification
' Checklist had.been completed and reviewed by the RS As yet no irradiations have been mad No violations'or deviations were identifie .' -Fuel Handling'(40750)
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.The: facility fuel handling program was reviewed by the inspector. The review included the' verification of approved procedures for fuel handling
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.and their technical adequacy in the steas of radiation protection, criticality-safety, . Technical Specincation and security plan require- ments. The inspector determined.by records review and discussions with
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personnel that annual fuel-examinations were carried out.in conformance with the licensee's procedure '
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No violations or deviations were identifie . ' Transportation Activities (86740)
There-have'been no shipments of radioactive material since the last-
-inspection. . Solid wastes are held at the facility awaiting a waste shipment to be made under the University broad-licens . Radiation Control (40750)
-The inspector reviewed'the radiation protection activities since_the las ~ inspection.~ Records were reviewed, personnel were interviewed, an observations were made to verify that radiation controls were being carried out in accordance with license and NRC regulations. The areas
. covered were: Posting and labeling of restricted areas and radioactive material Control of irradiated sample Calibration of radiation detection instrument d .- Required periodic dose rate and contamination survey _ Exposure records of personne f .' . Posted a eas of the facilit _
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,, Personnel trainin A review of personal dosimetry records for 1984 and 1985 indicated no problem The maximum annual whole body exposure was 160 mrem Dose and contamination surveys had been conducted as required with no problems noted.-
Personal training had been carried out in accordance with the requirements of 10 CFR 19 for students completing class room work at the reactor; however, the records of this training and required tests for students had not been submitted to the University Radiation Safety Office and included-in their records. This is considered an open item which will be reviewed during the next inspection (156/85003-01).
No violatiors or deviations were identifie .1 Radwaste Management (40750) Gaseous Radwaste According to the licensee's calculations, the average concentration of argon-41 released in calendar year 1984-85 was 0.105E-6 microcuries per milliliter, which corresponds to approximately percent of the MPC calculated in the SA Liquid Wastes Potentially contaminated water is collected and stored in a 2000 gallon holdup tank where it is sampled prior to release to the sanitary sewer. In 1984-85, 125 microcuries were released in two batches at an average concentration of 1.35E-5 microcuries per milliliter, well below the limits of 10 CFR 20.303 without considering dilution from the sanitary sewe Solid Wastes There have been no solid waste shipment Spent resins and other irradiated materials are stored in 55 gallon drum No violations or deviations were identifie . Emergency Planning (40750)
The inspector reviewed records and interviewed personnel to determine that the approved emergency plan was being carried out by verifying: That procedures were in place and required records were being kep That required drills were conducted and evaluate That required training had been conducte ,
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The inspector observed the building evacuation drill initiated by a manual trip of the evacuation alarm on October >23,1985. The building was evacuated in a timely manner and the drill was evaluated following the all clea Drills are conducted semiannually and at least one of these includes a' practice evacuation. A review of the emergency procedure for the filling of the pool without normal water supplies was conducted following the dril No violations'or deviations were identifie . Review of Periodic and Special Reports (90713)
The inspector reviewed the following reports for timeliness of submittal and adequacy of information submitted:
Annual Operating Report for License R-74 to the NRC for Fiscal Year 1984-1985 (Submitted August 19, 1985).
No violations or deviations were identifie . Exit Interview (30703)
The inspector met with the licensee representatives (listed in Paragraph 1) at the conclusion of the inspection on October 25, 1985 and summarized the scope and findings of the inspectio The inspector also discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspectors during the inspection. The licensee did not identify any documents or processes as proprietar The licensee acknowledged the inspector's remarks at the exit meeting and by telecon following the meeting concerning the need to standardize training requirements and records for all students 'using the reactor facility (Paragraph 11).
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