IR 05000243/1999201
| ML20207F614 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 06/07/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20207F611 | List: |
| References | |
| 50-243-99-201, NUDOCS 9906090120 | |
| Download: ML20207F614 (12) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No: 50-243 License No: R-106 Report No: 50-243/99-201 Licensee: Oregon State University Facility: TRIGA Mark-Il Reactor Facilit Location: Radiation Center, Oregon State University Corvallis, Oregon Dates: May 10-13,1999 Inspector: Craig Bassett, Senior Non-Power Rea:: tor inspector j I
Approved by: Ledyard B. Marsh, Chief Events Assessment, Generic Communications and Non-Power Reactors Branch Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation j i
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9906090120 990607 "
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EXECUTIVE SUMMARY
~ This routine, announced inspection included onsite review of selected aspects of the following:- organizational structure, review and audit program, radiation protection program, safeguards program, security program, and transportation program since the last NRC inspection of these area The licensee's programs were acceptably directed toward the protection of public health and safety, and in compliance with NRC requirement ORGANIZATIONAL STRUCTURE AND FUNCTIONS The organizational structure and functions were consistent with Technical Specification requirement REVIEW AND AUDIT The review and audit program satisfied Technical Specification requirement RADIATION PROTECTION The radiation protection program satisfied NRC requirement ENVIRONMENTAL PROTECTION The environmental protection program satisfied NRC requirement PROCEDURES The procedural control and implementation program satisfied Technical Specification requirement SAFEGUARDS Special Nuclear Materials were acceptably controlled and inventorie SECURITY Security activities and systems satisfied Physical Security Plan requirement ,
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TRANSPORTATION The program for transportation of radioactive materials satisfied NRC requirements.
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YEAR 2000 CONCERNS No problems had been identified concerning reactor operations but Y2K concerns in the area of spectroscopy were being addresse ;
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Report Details
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Summary of Mant Status
. During the inspection the reactor was operated several days a week to support experiments, education, operator training, and surveillance activitie . ORGANIZATIONAL STRUCTURE AND FUNCTIONS (69001) Scope The inspector reviewed selected aspects of:
e organization and staffing e qualifications e management responsibilities e- administrative controls Observations and Findinas The organizational structure and staffing with respect to the health physics organization had changed since the last inspection. A new Assistant Health Physicist had been hired because the previous person filling that position had retire The organizational structure and staffing as a whole at the facility, and as reported in the Annual Report, was as required by Technical Specification. Qualifications of the staff met Technical Specification requirements. Review of records verified that management responsibilities were administered as required by Technical Specifications and applicable procedure Conclusions The organizational structure and functions were consistent with Technical Specification requirement . REVIEW AND AUDIT (69001) Scope
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The inspector reviewed selected aspects of: I e Reactor Operations Committee (ROC) meeting minutes / records e ROC safety review and audit records e responses to safety reviews and audits 1
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I 2- Observations and Findinas Records showed that the safety reviews were conducted at the Technical Specification required frequency. Topics of these reviews were also consistent with Technical Specification requirements to provide guidance, direction, and oversight, and to ensure acceptable use of the reacto The audit records showed that audits had been completed in those areas outlined in the Technical Specifications and at the required frequency.-
The inspector noted that the safety reviews and audits and the associated findings were acceptably detailed and that the licensee responded and took corrective actions as neede Conclusiong The review and audit program satisfied Technical Specification requirement . RADIATION PROTECTION (69001) Scope The inspector reviewed selected aspects of:
i e the Radiation Protection Program o radiological signs and postirig a routine surveys and monitoring e dosimetry records .
e maintenance and calibration of radiation monitoring equipment l
e As Low As Reasonably Achievable (ALARA) reviews
' Observations and Findinas The radiation protection program had not changed since the last inspection. The licensee reviewed the radiation protection program at least annually in accordance
! I with-10 CFR 20.1101(c). The review included all areas and no weaknesses were reported. The licensee showed that the air emissions of radioactive material to the
- environment met the 10 millirem constraint specified in 10 CFR 20.1101(d).
i l Copies of NRC Form 3, " Notice to Employees," were posted in accordance with
! 10 CFR 19.11. Caution signs, postings, and controls for radiation areas were as required in 10 CFR 20, Subpart J. Licensee personnel observed the indicated precautions for access to radiation area i l
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-3-The use of dosimeters and exit frisking practices were in accordance with radiation protection requirements. The licensee used a National Voluntary Laboratory Accreditation Program (NVLAP)-accredited vendor to process dnsimetr Radiological exposure records showed that occupational doses and doscs to the public were within 10 CFR Part 20 limitations. Training records showed that personnel were a:ceptably trained in radiation protection practice Radiation monitoring and survey activities were as required. Equipment used for l these activities were maintained, calibrated, and used acceptabl I ALARA reviews were acceptably performed as require The licensee did not require a respiratory protection program or planned special '
exposure program, c. Conclusions The radiation protection program satisfied NRC requirement . ENV!RONMENTAL PROTECTION (69001)
a. Scope The inspector reviewed selected aspects of:
o the environmental monitoring program e annual reports e release records e counting and analysis program b. Observations and Findinas Environmental samples were collected, prepared, and analyzed consistently with the Technical Specification requirements. Laboratory equipment was maintained and calibrated acceptably. Data indicated that there were no measurable dose above background. This was acceptably documented in the Annual Reports. Observation of the facility found no new potential release path The program for the monitoring and storage of radioactive liquid, gases, and solids was consistent with applicable regulatory requirements. Radioactive material was monitored and released when below acceptable limits or was acceptably transferred to the broad-scope license for disposition. The principles of ALARA were acceptably implemented to minimize radioactive releases. Monitoring equipment was acceptably maintained and calibrated. Records were current and acceptably maintaine ,
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' Conclusions The environmentan protection program satisfied NRC requirement .- PROCEDURES (69001) Egegg The inspector reviewed selected aspects of:
e administrative controls . e records for changes and temporary changes e procedural implementation ( e logs and records Observations and Findinos
- Administrative controls of changes and associated review and approval processes were as required. . Training of personnel on procedures and changes was acceptabl Personnel conducted activities in accordance with applicable procedures. Records -
showed t'hat procedures for potential malfunctions (e.g., radioactive releases and contaminations) were implemented as require Conclusions The procedural control and implementation program satisfied Technical Specification . requirement . . SAFEGUARDS (85102)
- Scope .The inspector reviewed selected aspects of: ' e- - nuclear material inventory and locations <
e accountability records
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The inve' ntory of material was verified. The material control and accountability
. program tracked locations and content of fuel and fission detectors under th research reactor license._ The possession and use of special nuclear material (SNM)
was limited to the locations and purposes authorized under the license. The -{' material control and accountability forms (DOE /NRC Forms 741 and 742) were c generally prepared and transmitted as required,; it was noted that, on two l i
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. . -5-occasions, the licensee had not submitted the DOE /NRC Forms 741 and 742 within thirty days following the end of the periods covered by the reports as required by 10 CFR 74.13(a)(1). However, the licensee had identified these problems and had notified the NRC of the violations accordingly. The licensee was informed that these licensee-identified and corrected violations were being treated as a Non-Cited Violation (NCV), consistent with Section Vll.B.1 of the NRC Enforcement Policy (NCV 50-243/99-201-01).
c. Conclusions Special Nuclear Materials were acceptably controlled and inventorie . SECURITY (81401. 81402. and 81431) a. Scope The inspector reviewed selected aspects of: e the Physical Security Plan and submitted chan e security systems, equipment, and instrumentati. .is e implementation of the Physical Security Plan (r. 21 b. Observations and Findinas The PSP was the same as the latest revision approved by the NRC. It was noted i that the licensee had submitted two changes to the PSP in 1997, two in 1998, and j one change thus far in 1999. The licensee had determined that the changes did not i decrease the effectiveness of the PSP. The NRC had screened one of the 1997 changes and the 1998 changes to date. The inspector screened the remaining open 1997 change while on site. The NRC Headquarters staff is currently screening the 1999 change. The results of this inspection indicated that the 1997 and 1998 changes did not appear to decrease the effectiveness of the PS l Physical protection systems (barriers and alarms), equipment, and instrumentation were as required by the PSP. Access control was as required. Implementing procedures were consistent with the PSP. Acceptable security response and training was demonstrated through alarm response and drill response in accordance with procedure c. Conclusions Security activities and systems satisfied Physical Security Plan requirement l
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_8 TRANSPORTATION (86740)
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' The inspector reviewed selected aspects of: :e= l radioactive materials shipping procedures - >
_ e . radioactive materials transportation ~ and transfer records - b.- - Observations 'and Findinas - f Records showed that the radioactive material for disposal'was transferred to the broad scope license in accordance with licensee requirements. This program for -
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radioactive material transfer was consistent with license requirement The transport of radiological samples was also reviewed. Records showed that the radioisotope type and quantities were calculated and dose rates were measure These records also showed that transportation of the radioactive materials were in
:accordance w.ith applicable DOT and NRC requirements.- ' ' Conclusions - > The program for transportation of radioactive materials satisfied NRC requirement . YEAR 2000 CONCERN Scope To determine the status of the licensee's preparations to deal with the potential ' problems caused by the Year 2000.(Y2K), the inspector reviewed:
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'e ~ the licensee's operating system e- the licensee's security system e: . the spectroscopy. system used at the facility e the Oregon State University (OSU) approach to the problem-1 b,P .Qbservations and Findinos The licensee had reviewed their operations,' security, and spectroscopy systems and had concluded that the only problem concerning Y2K might exist in the : spectroscopy or counting system used at the facility. - In order to correct the m problem, the licensee _ had purchased'new counting software from a vendo Nothing had been identified that would pose a problem to reactor operations and no instances were identified that could pose a threat to public health and safety. .
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-7-The security system at the facility was maintained jointly by the licensee and the OSU Security Services group on campus. The way the system was configured, no problems were anticipated with the approaching Y2K. OSU had also analyzed the Y2K status campus-wide and was taxing actions as neede Conclusions No problems had been identified concerning reactor operations but Y2K concerns in the area of spectroscopy were being addresse . EXIT INTERVIEW The inspection scope and results were summarized on May 13,1999, with licensee representatives. The inspector discussed the findings for each area reviewed. The licensee acknowledged the findings and did not identify as proprietary any of the material provided to or reviewed by the inspector during the inspectio ,
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PARTIAL LIST OF PERSONS CONTACTED Licensee ! S. Binney, Director, Radiation Center K. Brock, Health Physicist B. Brown, OSU Security Services Supervisor
- R. Brown, OSU Security Services Manager -
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A. Hall, Reactor Supervisor l J. Higginbotham, Chairman of Reactor Operations Committee D. Pratt, Senior Health Physicist S. Reese, Reactor Administrator S. Smith, Scientific Instrument Technician
G. Wachs, Senior Reactor Operator l lNSPECTION PROCEDURES USED IP 69001: Class 11 Non-Power Reactors ! IP 81401: Plans, Procedures, and Reviews IP 81402: Reports of Safeguards Events IP 81431: Fixed Site Physical Protection of Special Nuclear Material of Low Strategic Significance IP 85102: Material Control and Accounting - Reactors IP 86740: Inspection of Transportation Activities ITEMS OPENED, CLOSED, AND DISCUSSED Ooened 50-243/99-201-01 NCV Failure to submit Material Balance Reports within 30 days following the end of the period covered by the reports on two occasion l Closed 50-243/99 201-01 NCV Failure to submit Material Balance Reports within 30 days following the end of the period covered by the reports on two occasions.
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l , l uST OF ACRONYMS USED . ! ! l CFR Code of Federal Regulations IP inspection Procedure LCO Limiting Condition for Operations - Mw- Megawatt NCV Non-Cited Violation NPR Non-Power Reactor l NRC Nuclear Regulatory Commission NVLAP National Voluntary Laboratory Accreditation Program OSU Oregon State University PSP Physical Se.curity Plan
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ROC . Reactor Operations Committee-SNM Special Nuclear Material l TS Technical Specifications TRTR Test, Research, and Training Reactor l l ! . l
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