IR 05000294/1989001
| ML20245H582 | |
| Person / Time | |
|---|---|
| Site: | 05000294 |
| Issue date: | 08/10/1989 |
| From: | Paul R, Schumacher M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20245H563 | List: |
| References | |
| 50-294-89-01, 50-294-89-1, NUDOCS 8908170186 | |
| Download: ML20245H582 (5) | |
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C U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-294/89001(DRSS)
Docket No. 50-294 License No. R-114 Licensee: Michigan State University East Lansing, MI 48824 Facility Name:. Michigan State University TRIGA Reactor Inspection At: Michigan State University TRIGA Reactor East Lansing, Michigan Inspection Conducted: July 19-21,1989 Inspector:
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Q f f t & u sro f $ y -
Approved By:
_M. Schumacher, Chief k
Radiological Controls and Date Chemistry Section Inspection Summary Inspection on July 19-21, 1989 (Report No. 50-294/89001(DRSS))
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; open inspection items; and aspects of the reactor decommissioning project.
Results: No violations or significant safety issues were identified in the areas inspected.
8908170186 890811 PDR ADOCK 05000294 Q
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DETAILS
'1.
. Persons Contacted L
- B. Wilkinson, Reactor Supervisor - Chairman, Reactor Safety Committee M. Mitchell, Health Physicist (ORCBS)
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W. Malchman, Radiation Safety Officer (ORCBS)
- Indicates those present at the exit interviews.
2..
General This inspection was conducted to examine the research reactor program
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L at Michigan State University. The facility is in the process of
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decommissioning, the fuel has been removed and transferred, and the reactor was being dismantled during the inspection.
3.
Licensee Action on Previous Inspection Findings (92701-92702)
(Closed) Unresolved Item (50-294/86001-02): Written report including corrective actions taken as a result of discrepancies found concerning
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instrument calibrations. The inspector verified the-discrepancies were corrected in revised ARM calibration procedures.
(Closed) Open Item (50-294/86001-01): Ensure detection efficiencies for reactor faci.lity portable radiation survey meters calibrated by ORCBS are correct. The reactor licensee implemented a program which required review of calibration data for each instrument calibrated by ORCBS and used by the reactor facility.
(Closed) Open Item (50-294/86001-03): Practice of calibrating the reactor effluent monitor without verifying the radioactivity levels of each calibration source. By using a calibrated NBS traceable standard, the' licensee verified that the calculated' argon-41 radioactivity used for the effluent monitoring system was valid.
4.
Organization Logs and Records (40750)
e The facility organization was reviewed and verified to be consistent with the requirements. The reactor has not operated since October 10, 1987.
The reactor maintenance logs and records were reviewed to verify they were maintained for the period June 1986, (date of the last inspection)
until October 10, 1987.
No violations or deviations were identified.
l 5.
Reviews and Audits (40750)
I The licensee's review and audit program records were examined by the j
inspector to verify that:
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a.
Reviews of facility changes, operating and maintenance procedures,
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-design changes, and unreviewed experiments had been conducted by a
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safety review committee as required by technical specifications or SAR.
b.
That the review committee and/or subcommittee were composed of qualified members and that quorum requirements and frequency of meetings had been met. A review of selected RSC meetings indicated the committee was meeting all requirements.
No violations or deviations were identified.
6.
Requalification Training (40750)
The inspector reviewed procedures, logs, training records, and test results,. and interviewed personnel to verify that the requalification training program was being carried out in conformance with the facility's NRC requirements.
Requalification examinations had been conducted in December 1987 for both licensed operators.
No violations or deviations were identified.
7.
Procedures (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.
The inspector determined that the required procedures were available and the contents of the procedures were adequate.
No violations or deviations were identified.
8.
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 tasts, tests were completed within the required time schedule, and test records were available. The licensee's surveillance program appeared to be satisfactory.
No violations or deviations were identified.
9.
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, and no new experiments have been initiated since the last operational inspection (June 1986, Inspection Report No. 50-294/86001).
No violations or deviations were identified.
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10. Transportation Activities (86740)
Three fuel shipments consisting of all the licensee's fuel (96 elements)
were shipped to authorized recipients between May 22, 1987 through
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l June 10, 1989. The elements were shipped in an authorized TRIGA fuel
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cask (BMI-1-USA /5957/B0F).
The fuel was shipped in accordance with the-licensee's Quality Assurance Approved Program and 10 CFR requirements.
11.
Radiation Control (40750)
The inspector reviewed the radiation protection activities since the last
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inspection.
Records were reviewed, personnel were interviewed, and the l '
inspection verified that radiation controls were carried out in accordance with licensee and NRC regulations.
The results of this review indicated licensed members of the reactor staff had received adequate radiation protection training; there are sufficient operable and calibrated portable survey meters; personal whole body exposures did not exceed 140 mrem in 1986, 1987, 1988 and 1989 to date, airborne activity samples were considerably less than 10 CFR 20 MPC limits; no bioassay samples were required; posting, labelling, and radiological controls were adequate.
12.
Radwaste Management (40750)
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a.
Gaseous Radwaste According to the licensee's calculations, the facility released 15 mC1 of argon-41 in calendar year 1986, 70 mci in 1987, and none in calendar year 1988.
The average concentration was 1.3E-9 and 7E-9 microcuries per milliliter in 1986 and 1987 respectively, and corresponds to less than 20 percent of the technical specification limit.
b.
Liquid Wastes There were no liquid radioactive discharges in 1986 or 1987.
Pool water samples were collected and analysed for alpha, beta, gamma,
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and tritium as required; no problems were identified, c.
Solid Wastes There were no solid waste shipments, the waste was handled by the ORCBS under the University Broad License.
No violations or deviations were identified.
13.
Review of Periodic and Special Reports (90713)
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The inspector reviewed the Annual Report for 1986, 1987, and 1989 for i
timeliness of submittal and adequacy of information submitted-
No violations or deviations were identified.
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14. ' Status of Reactor Dismantling Program The inspector reviewed the licensee's reactor dismantling program history and the organization and management controls established for monitoring
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l the program. The inspector reviewed procedures, interviewed licensee and i.
contractor personnel, including the cognizant contractor supervisor, and the health physicist responsible for implementing the radiological
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controls for the program.
In addition, the inspector observed various dismantling activities-in progress, including the removal of the reactor rotary specimen (Lazy Susan).
Radiation work permits, air samples, smear and direct survey results were also reviewed, and independent surveys and inspections were performed to ensure good health physics practices were followed.
Based on the inspector's review, it appears the dismantling was performed by trained personnel in accordance with procedures and was overseen by an experienced radiation protection staff.
Solid radwaste appeared to be l
removed from the facility and managed in accordance with NRC l
requirements.
Liquid wastes will be disposed to the sanitary sewer in accordance with 10 CFR 20.303 limits.
Protective clothing and personal dosimetry was issued, shielding was used when practicable, sufficient surveys and air samples were performed and radiological controls in
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general were adequate.
15. Exit Interview (30703)
The inspector met with the licensee representatives (listed in Paragraph 1) at the. conclusion of the inspection on July 21, 1989, and summarized the scope and findings of the inspection.
The inspector discussed the likely informational content of the inspection report with regard to documents or processes reviewed by the inspector during the inspection.
The licensee did not identify any documents or processes as proprietary.
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