IR 05000243/2006201
| ML062350280 | |
| Person / Time | |
|---|---|
| Site: | Oregon State University |
| Issue date: | 08/24/2006 |
| From: | Johnny Eads NRC/NRR/ADRA/DPR/PRTB |
| To: | Reese S Oregon State University |
| Bassett C, NRR/DRIP/REXB, 404-562-4899 | |
| References | |
| IR-06-201 | |
| Download: ML062350280 (22) | |
Text
ust 24, 2006
SUBJECT:
NRC INSPECTION REPORT NO. 50-243/2006-201
Dear Dr. Reese:
On August 7-10, 2006, the U.S. Nuclear Regulatory Commission (NRC) conducted an inspection at your Radiation Center TRIGA Mark-II Reactor Facility. The enclosed report documents the inspection results, which were discussed on August 10, 2006, with you and members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the NRCs rules and regulations and with the conditions of your license. The inspector reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, no findings of significance were identified.
In accordance with Section 2.390, Public inspections, exemptions, requests for withholding, of Title 10 of the Code of Federal Regulations, a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRCs Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Should you have any questions concerning this inspection, please contact Craig Bassett at 404-358-6515.
Sincerely,
/RA/
Johnny H. Eads, Branch Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No.: 50-243 License No.: R-106 Enclosures: NRC Inspection Report cc w/encl: See next page
Oregon State University Docket No. 50-243 cc:
Mayor of the City of Corvallis Corvallis, OR 97331 David Stewart-Smith, Administrator Energy Resources Oregon Office of Energy, Suite 1 625 Marion Street, N.E.
Salem, OR 97301-3742 Dr. John Cassady, Vice President for Research Oregon State University Administrative Services Bldg, Room A-312 Corvallis, OR 97331-5904 Dr. Michael Hartman Reactor Administrator Oregon State University Radiation Center, A-100 Corvallis, OR 97331-5904 gust 24, 2006
SUBJECT:
NRC INSPECTION REPORT NO. 50-243/2006-201
Dear Dr. Reese:
On August 7-10, 2006, the U.S. Nuclear Regulatory Commission (NRC) conducted an inspection at your Radiation Center TRIGA Mark-II Reactor Facility. The enclosed report documents the inspection results, which were discussed on August 10, 2006, with you and members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the NRCs rules and regulations and with the conditions of your license. The inspector reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, no findings of significance were identified.
In accordance with Section 2.390, Public inspections, exemptions, requests for withholding, of Title 10 of the Code of Federal Regulations, a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRCs Agencywide Documents Access and Management System (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Should you have any questions concerning this inspection, please contact Craig Bassett at 404-358-6515.
Sincerely,
/RA/
Johnny H. Eads, Branch Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No.: 50-243 License No.: R-106 Enclosures: NRC Inspection Report cc w/encl: See next page DISTRIBUTION:
PUBLIC PRTA r/f AAdams CBassett PDoyle JEads DHughes EHylton PIsaac CLyon MMendonca JQuichocho WSchuster MVoth KWitt PYoung DBarss (MS O6-H2) BDavis (Ltr only O5-A4)
NRR enforcement coordinator (Only for IRs with NOVs, O10-H14)
ACCESSION NO.: ML062350280 TEMPLATE #: NRR-OFFICE PRT:RI PRT:LA PRT:BC NAME CBassett:tls EHylton JEads DATE / /2006 08/23 /2006 08/ 24 /2006 OFFICIAL RECORD COPY
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No: 50-243 License No: R-106 Report No: 50-243/2006-201 Licensee: Oregon State University Facility: TRIGA Mark-II Reactor Facility Location: Radiation Center, Oregon State University Corvallis, Oregon Dates: August 7-10, 2006 Inspector: Craig Bassett Approved by: Johnny H. Eads, Branch Chief Research and Test Reactors Branch B Division of Policy and Rulemaking Office of Nuclear Reactor Regulation
EXECUTIVE SUMMARY Oregon State University TRIGA Mark-II Reactor Facility Report No: 50-243/2006-201 The primary focus of this routine, announced inspection was the onsite review of selected aspects of the licensees Class II research reactor safety program including: organization and staffing, review and audit and design change functions, operator requalification, procedures, fuel movement, maintenance and surveillance, reactor operations, experiments, and emergency preparedness since the last NRC inspection of these areas. The licensee's programs were determined to be directed toward the protection of public and facility worker health and safety and were in compliance with NRC requirements.
Organization and Staffing
! The licensee's organization and staffing were in compliance with the requirements specified in the Technical Specifications.
Review and Audit Functions and Design Control
! Review, audit, and oversight functions required by Technical Specification Section 6.2 were acceptably completed by the Reactor Operations Committee.
! The change review process at the facility was in place and was being followed when changes were initiated.
Reactor Operations
! Reactor operations were conducted in accordance with Technical Specification requirements and applicable procedures.
Operator Licenses, Requalification, and Medical Activities
! Operator requalification was conducted as required by the Operator Requalification Program.
Procedures
! Facility procedures were acceptable and satisfied Technical Specification requirements for being revised by the licensee and reviewed and approved by the Reactor Operations Committee.
! Procedural compliance was observed and found to be acceptable.
Fuel Movement
! Fuel handling activities were as required by Technical Specification and fuel inspections were documented as required by facility procedures.
Maintenance and Surveillance
! Maintenance was being completed in accordance with Technical Specification and procedural requirements.
! The program for surveillance verifications and calibrations was being implemented in accordance with Technical Specification requirements.
Experiments
! The program for the control of experiments satisfied regulatory and Technical Specification Sections 3.8 and 4.3 requirements.
! Emergency response facilities and equipment were being maintained as required and responders were knowledgeable of proper actions to take in case of an emergency.
! The licensee maintained current Emergency Support Agreements with offsite agencies which indicated that support would be available in case of an emergency.
! Annual drills were being held and documentation was maintained concerning the follow-up critiques and subsequent corrective actions.
! Emergency preparedness training for staff and off-site personnel was being conducted as required.
REPORT DETAILS Summary of Plant Status The licensees 1.1 megawatt TRIGA Mark-II research and test reactor continued normal, routine operations. Observation of reactor operation and a review of the applicable records indicated that the reactor was typically operated approximately six hours per day, five days per week, in support of laboratory testing, reactor system testing, reactor surveillances, and sample irradiations. During this inspection, the reactor was started up and operated several hours per day at varying power levels for training and sample irradiation.
1. Organizational Structure and Staffing a. Inspection Scope (Inspection Procedure [IP] 69001)
The inspector reviewed the following regarding the licensees organization and staffing to ensure that the requirements of Section 6 of the Technical Specifications (TS), Amendment No. 20, dated September 26, 2005, were being met:
- Oregon State University (OSU) Radiation Center facility organizational structure and staffing
- selected portions of the Reactor Console Logbooks for the past two years which indicated staffing levels during routine reactor operations
- OSU TRIGA Reactor Annual Reports for the period from July 1, 2003 through June 30, 2004, and the period from July 1, 2004 through June 30, 2005
6, Administrative and Personnel Procedures, Revision (Rev.) 14, dated July 2006, which outlined various administrative controls
- American National Standard ANSI/ANS 15.4-1977 (N380), Selection and Training of Personnel for Research Reactors, dated 1977 b. Observations and Findings The inspector noted that the title of the person that the Director of the Radiation Center (RC) reports to had changed since the last inspection. The RC Director now reports to the President of the University through the Vice President for Research. Formerly the RC Director had reported through the Vice Provost for Research. The RC organizational structure and the responsibilities of the reactor staff had not changed since the last inspection. Staffing levels remained consistent with those noted during the last inspection of this facility.
Since the last inspection, the former Reactor Administrator had been appointed as the RC Director and a new person had been hired to fill the Reactor Administrator position. With the addition of the new person, the current reactor operations organization consisted of the Director of the Radiation Center, a Reactor Administrator, a Reactor Supervisor, a Senior Reactor Operator (SRO),
and a Scientific Instrument Technician. It was noted that the RC Director, Reactor Supervisor, and Scientific Instrument Technician were also qualified
SROs. The new Reactor Administrator was in training to become an SRO and should take the NRC examination by the end of this year. This organization was consistent with that specified in the TS.
The inspector reviewed the qualifications of the reactor staff including the resume of the new Reactor Administrator. All personnel satisfied the training and experience requirements stated in ANSI/ANS 15.4, Standard for the Selection and Training of Personnel for Research Reactors, as stipulated in the TS. A review of the Reactor Console Logbooks and associated records confirmed that shift staffing met the minimum requirements for duty and on-call personnel.
c. Conclusions Organizational structure and staffing were in compliance with the requirements specified in TS Section 6.
2. Review and Audit, and Design Change Functions a. Inspection Scope (IP 69001)
In order to verify that the licensee had established and conducted reviews and audits as required by TS Section 6.2 and to determine whether modifications to the facility were consistent with 10 CFR 50.59, the inspector reviewed:
- 50.59 Screen Logbook
- 50.59 Evaluation Logbook
- responses to the safety audits and reviews
- design change functions outlined in OSTROP 6
- safety audit and review records for the past two years
- Reactor Operations Committee meeting minutes from May 2005 to the present
- OSU TRIGA Reactor Annual Reports for the period from July 1, 2003 through June 30, 2004, and from July 1, 2004 through June 30, 2005
- design/facility change evaluations conducted under and documented in accordance with OSTROP 6, Figure 6.2 entitled, OSU TRIGA Reactor (OSTR) Changes, Tests, and Experiments Evaluated Under the Provisions of 10 CFR 50.59, Numbers (Nos.) 05-01 through 05-06
- design/facility change screens conducted under and documented in accordance with OSTROP 6, Figure 6.1 entitled, Oregon State TRIGA Reactor (OSTR) 10 CFR 50.59 Screen Form , Nos. 05-01 through 05-08 and 06-01 through 06-06
- Forms which documented approval of procedure revisions by the ROC between scheduled meetings entitled Reactor Operations Committee Approval Sheet (ROCAS), Nos. 05-01 through 05-03
- OSTROP 6, Administrative and Personnel Procedures, Rev. 14, dated July 2006, which also contained the Charter of the Reactor Operations Committee (ROC) and its responsibilities
b. Observations and Findings (1) Review and Audit Functions The inspector reviewed the Reactor Operations Committee meeting minutes from May 2005 to the present. These meeting minutes showed that the committee met as required by the TS with a quorum being present. The inspector also noted that the ROC had considered the types of topics outlined by the TS Section 6.2. Review of the committee meeting minutes also indicated that the ROC provided appropriate guidance and direction for reactor operations, and ensured suitable use and oversight of the reactor.
It was noted that ROC members completed audits of reactor operations and related records, as well as, the radiation protection, emergency preparedness, and other programs. The inspector noted that the audits and the resulting findings were acceptable and the audits were generally completed within the time frame stipulated by the TS. If the findings contained recommendations for possible changes, the licensee responded and took corrective actions as necessary.
(2) Design Control The inspector reviewed recent 10 CFR 50.59 screen and evaluation forms and interviewed licensee personnel concerning facility changes.
As a result, the inspector determined that all changes that had been initiated at the facility since the last NRC operations inspection had undergone a review by the licensee staff who then wrote a proposal outlining the changes. These were presented to the ROC for review and approval in accordance with OSTROP 6. It was noted that none of the changes constituted a safety question or required an amendment to the license or a change to the facility TS.
c. Conclusions Review, audit, and oversight functions required by TS Section 6.2 were acceptably completed by the ROC. Changes to the facility were being reviewed using the 10 CFR 50.59 criteria and were then reviewed and approved by the ROC as required. No changes were determined to constitute a safety question.
3. Operations a. Inspection Scope (IP 69001)
The inspector reviewed selected portions and/or aspects of:
- Supervisors Log #12 and #14
- staffing during routine reactor operations
- Licensed Operator Time Log Sheets for the past two years
- selected OSU TRIGA Reactor Daily Power Log Sheets for the past two years
- operations records documented in the Reactor Console Logbook, Nos.
141 - 144
- observation of startup, operations, and shutdown activities on August 3 and 4, 2004
- start-up activities documented on OSTROP 2 forms entitled OSU TRIGA Reactor Startup Checklists, from December 2005 through June 2006
- shut down activities documented on OSTROP 3 forms entitled Reactor Shutdown Checklists, from December 2005 through June 2006
- selected records of console instrumentation readings documented on Control Room Log Sheets for the past two years
- OSU TRIGA Reactor Annual Reports for the period from July 1, 2003 through June 30, 2004, and from July 1, 2004 through June 30, 2005
- OSTROP 2, Reactor Startup Checklist Procedures, Rev. 10, dated March 2006
- OSTROP 3, Reactor Shutdown Checklist Procedures, Rev. 8, dated December 2005
- OSTROP 4, Reactor Operation Procedures, Rev. 5, dated May 2002
- OSTROP 5, Procedure for Maintaining Reactor Operational Records, Rev. 7, dated March 2006
- OSTROP 25, Reporting Requirements, Rev. 3, dated December 2000
- OSTROP 27, Procedures to Follow in the Event of a Commercial Electrical Power Failure, Rev. 3, dated December 2005 b. Observations and Findings The inspector conducted observations of the reactor staff on August 8 and 9, 2006, and reviewed Reactor Console Logbooks and associated records. The inspector noted that the licensed reactor operators were knowledgeable and competent. Observation of operational activities also confirmed that reactor operations, including start-ups, routine operations, and shutdowns, were carried out in accordance with written procedures and TS requirements. Adherence to procedures was acceptable.
These observations and reviews also confirmed that shift staffing during reactor operation met the TS requirements for duty and on-call personnel. The inspector noted that the logs were being maintained as required by procedure, they were clear and concise, and the records and associated forms provided an acceptable indication of operational activities. The records showed that operational conditions and parameters were consistent with license and TS requirements.
The Reactor Console Logbooks, as well as other supplemental records, also documented abnormal events that occurred and measures that had been taken to resolve or track the events.
c. Conclusions Reactor operations were being completed in accordance with TS and procedural requirements.
4. Operator Licenses, Requalification, and Medical Activities a. Inspection Scope (IP 69001)
The inspector reviewed the following in order to determine that operator training and requalification activities were conducted as required and that medical requirements were met:
- OSU Operator Time Log
- medical examination records
- biennial written examination records
- effective dates of current operator licenses
- OSU TRIGA Reactor (Operator) Initial Licensing Program
- operator training records documented in the Operator Requalification Manual
- Requalification Program for Licensed Operators of the Oregon State TRIGA Reactor, Rev. 1, dated September 30, 2004
- logs and records of reactivity manipulations maintained in the Operator Time Log and associated manual
- active duty status and Annual Reactor Operating Test results noted and maintained in the Operator Time Log and associated manual
- operations records documented in the Reactor Console Logbook, Nos.
141-144
- OSTROP 16, Annual Surveillance and Maintenance Procedures, Rev.
12, dated December 2005 and related log sheets b. Observations and Findings At the time of the inspection, there were four qualified SROs working at the facility. The inspector verified that all the operators licenses were current.
A review of the logs and records showed that training had been conducted in the areas outlined in the licensees requalification and training program such that all the material was covered within a two-year period. It was noted that lectures had been given as stipulated, that training reviews had been documented, and that written examinations had been completed. An annual operating test had been conducted for each SRO by the Reactor Supervisor as required by the program as well. It was also verified that each operator had completed the required number of hours of reactor operations each calendar quarter as required.
Records of these reactor manipulations, other operational activities, and/or Reactor Supervisor activities were being maintained, as were records of the Annual Operations Tests. The program was up-to-date and training was current.
Three operators had had a medical examination within two years as required.
The fourth operator was due to have an examination the week of the inspection as required by the program.
c. Conclusions The requalification and training program was up-to-date and acceptably maintained.
5. Procedures a. Inspection Scope (IP 69001)
To determine whether facility procedures were being audited annually and met the requirements outlined in TS Section 6.5, the inspector reviewed:
- selected operating procedures
- procedural reviews and updates documented in ROC meeting minutes.
- OSTROP 5, Procedure for Maintaining Reactor Operational Records, Rev. 7, dated March 2006
- OSTROP 6, Administrative and Personnel Procedures, Rev. 14, dated July 2006 b. Observations and Findings The licensees procedures were found to be acceptable for the facilitys current operating status and staffing level. It was noted that the procedures specified the responsibilities of the various members of the staff. The inspector determined that the procedures were being audited and reviewed annually as required and revised as needed. Substantive changes to procedures, checklists, and forms were presented to the ROC for review and approval as required by TS. The operations observed by the inspector during this inspection were completed in accordance with the applicable procedures.
c. Conclusions Facility procedures were being reviewed and audited annually as required by TS Section 6 and procedure revisions were reviewed and approved by the ROC.
Procedural compliance was acceptable.
6. Fuel Movement a. Inspection Scope (IP 69001)
The inspector reviewed the following to verify adherence to fuel handling, positioning, and inspection requirements specified in TS Sections 4.4 and 5.2:
- fuel handling equipment and instrumentation
- operations records documented in the Reactor Console Logbook, Nos.
141 - 144
- fuel handling and examination records for the past two years documented on Oregon State University TRIGA Mark II Research Reactor Fuel
Element History File cards maintained in the FLIP Fuel Element History Logbook and on Fuel Element Transfer Sheet forms
- OSTROP 11, Fuel Element Handling Procedures, Rev. 5, dated December 2005
- OSTROP 16, Annual Surveillance and Maintenance Procedures, Rev.
12, dated December 2005 and related log sheets
- OSTROP 20, Special Nuclear Material Control and Accounting Procedures, Rev. 6, dated July 2004 b. Observations and Findings The inspector noted that the licensee was operating with FLIP Core No.10. It was also noted that the reactor could be operated in different configurations depending upon what equipment was installed in the B-1 position of the core.
The actual configuration was tracked in the Reactor Console Logbook via colored markers used to mark the edge of each applicable logbook page.
The inspector determined that the licensee was maintaining the required records of the various fuel movements that were completed and verified that the movements were conducted in compliance with procedure. The reactor fuel was being inspected upon initial receipt and on an as needed basis as required by TS Section 4.4. It was also noted that the specific elements located in the B-ring and those adjacent to the transient rod were inspected annually as a quality control measure because occasional swelling of those elements had been noted in the past due to reactor operation.
The procedures used for fuel movement and inspection were acceptable, as were the precautions that were required to be established during fuel movements and inspections. Fuel element locations were being tracked by log book and on a Fuel Status Board maintained in the Reactor Control Room.
c. Conclusions Reactor fuel movements were made and documented in accordance with procedure. The fuel was being inspected on an as-needed basis as allowed by TS Section 4.4.
7. Maintenance and Surveillance a. Inspection Scope (IP 69001)
To determine that surveillance requirements and Limiting Conditions for Operation (LCO) verifications were being completed as required by TS Sections 3 and 4 and that maintenance activities were conducted when required, the inspector reviewed:
- selected portions of the Reactor Supervisor Log Nos. #12 & 14
- operations records documented in the Reactor Console Logbook, Nos.
141 - 144
- selected surveillance and calibration test data sheets and records maintained in the Surveillance and Maintenance Logbook
- OSU TRIGA Reactor Annual Reports for the period from July 1, 2003 through June 30, 2004, and from July 1, 2004 through June 30, 2005
- OSTROP 8, Reactor Power Calibration Procedures, Rev. 5, dated September 2005
- OSTROP 9, Control Rod Calibration Procedures, Rev. 10, dated December 2005
- OSTROP 12, Control Rod Maintenance, Removal, and Replacement Procedures, Rev. 4, dated March 2006
- OSTROP 13, Monthly Surveillance and Maintenance Procedures, Rev.
11, dated September 2005 and related log sheets
- OSTROP 14, Quarterly Surveillance and Maintenance Procedures, Rev.
9, dated September 2005 and related log sheets
- OSTROP 15, Semi-Annual Surveillance and Maintenance Procedures, Rev. 14, dated December 2005 and related log sheets
- OSTROP 16, Annual Surveillance and Maintenance Procedures, Rev.
12, dated December 2005 and related log sheets
- OSTROP 19, Equipment Maintenance and Calibration Procedures, Rev.
1, dated July 2004 b. Observations and Findings The inspector noted that selected monthly, quarterly, semiannual, and annual checks, tests, verifications, and/or calibrations for TS-required surveillances and LCO verifications were being completed as stipulated. All the surveillances and LCO verifications reviewed were completed on schedule and in accordance with licensee procedures. All the recorded results were within the TS and procedurally prescribed parameters. The records and logs reviewed were accurate, complete, and being maintained as required.
The maintenance logs and records indicated that problems were addressed and preventive maintenance operations completed as required by procedure.
Records showed that routine maintenance activities were conducted at the required frequency and in accordance with the TS and/or the applicable procedure. Maintenance activities ensured that equipment remained consistent with the Safety Analysis Report and TS requirements.
The Reactor Supervisor maintained a schedule for reactor operations and tracked the completion of maintenance and surveillance activities. This practice ensured that the staff was aware of upcoming activities and helped ensure good administrative control over operational aspects of the facility.
c. Conclusions The program for surveillance and LCO confirmations was being carried out in accordance with TS and procedural requirements. Maintenance was also being completed as required.
8. Experiments a. Inspection Scope (IP 69001)
The inspector reviewed the following to verify that experiments were being conducted within approved guidelines specified in TS Sections 3.8 and 4.3:
- OSU Radiation Center TRIGA Users Certification Form
- potential hazards identification and control of irradiated items
- documentation of experiment review and approval by the ROC
- selected Standard Form Irradiation Request forms for the past two years
- selected Pneumatic Transfer Irradiation Request forms for the past two years
- General Limitations of Experiments Performed Using the OSU TRIGA Reactor
- selected OSU TRIGA Reactor Irradiation Request forms for the past two years
- operations records documented in the Reactor Console Logbook, Nos.
135-141
- OSU Approved Experiments including the following:
- No. A-1, Normal TRIGA Operations, Rev. 1, dated July 1992
- No. B-3, Irradiation of Materials in the Standard OSTR Irradiation Facilities, Rev. 4, dated December 1999
- No. B-31, TRIGA Flux Mapping, Rev. 1, dated December 1988
- No. B-32, Argon Production Facility, Rev. 0, dated January 1999
- No. B-33, Irradiation of Combustible Liquids in the Rotating Rack, Rev. 0, dated May 2003
- OSU TRIGA Reactor Annual Reports for the period from July 1, 2003 through June 30, 2004, and from July 1, 2004 through June 30, 2005
- OSTROP 10, Operating Procedures for Reactor Experimental Facilities, Rev. 13, dated July 2006
- OSTROP 18, Procedures for the Approval and Use of Reactor Experiments, Rev. 8, dated March 2005 b. Observations and Findings The licensee had three types of experiments at the facility based generally on the reactivity, amount of shielding required, and the amounts of radioisotopes produced. Class A experiments were those that involved small changes in reactivity, required no external shielding, and/or produced limited amounts of radioisotopes. Class B experiments involved larger changes in reactivity, required external shielding, and/or produced larger amounts of radioisotopes.
Class C experiments were special experiments involving unusual experimental setups, the irradiation of special materials such as explosives, unusual fuel element arrangements, large in-core experimental facilities, etc. There were currently one Class A and eight Class B experiments that were considered active.
Most of the experiments conducted at the facility were well-established procedures that have been in place for many years. However, it was noted that one new experiment had been initiated in 2003. It dealt with irradiation of combustible liquids in the rotating specimen rack (Lazy Susan). The inspector verified that all the active experiments had been reviewed and approved by the ROC as required.
A review of the records maintained by the licensee indicated that experiments were completed under the cognizance of the Reactor Supervisor as required.
The results of the experiments were documented in the reactor operations log book. Irradiation Request forms, required for reactor use, were also reviewed.
The forms were being completed as required. The forms documented the individual users, the required approvals and licenses, the length of the irradiations, the expected resulting radionuclides that would be produced, and the ultimate disposition of the material following the irradiations.
The inspector observed the removal of samples from and the insertion of samples into the reactor Thermal Column Irradiation Facility and the Cadmium-lined In-core Irradiation Tube (CLICIT). It was noted that licensee personnel followed procedure and established protocol. Health physics personnel were present to monitor the samples being removed and established controls were used to maintain exposures ALARA. Contamination controls were used effectively as well.
c. Conclusions The license's program for the control of experiments satisfied regulatory and TS requirements.
9. Emergency Preparedness a. Inspection Scope (IP 69001)
To verify proper implementation of the licensees Emergency Preparedness Program, the inspector reviewed selected aspects of:
- emergency response facilities, supplies, equipment, and instrumentation
- training and emergency drill records for the past two years
- offsite support as documented in Emergency Support Agreements.
- Oregon State University TRIGA Reactor (OSAR) Emergency Response Plan and Emergency Response Implementing Procedures (ERIP), dated May 17, 1984, and last revised December 2005 including:
- ERIP 0, Emergency Procedures for Emergency Response Personnel - Class 0 Emergency - Personnel and Operational Events, dated September 2004
- ERIP 1, Emergency Procedures for Emergency Response Personnel - Class 1 Emergency - Notification of Unusual Events, dated September 2004
- ERIP 2, Emergency Procedures for Emergency Response Personnel - Class 2 Emergency - Alert, dated September 2004
- ERIP 3, OSTROP Emergency Operation Procedures (OSTROP 1.0), dated September 2004
- ERIP 4, RCHPP - 34 - Orientation and Training Programs for the OSU Radiation Center, dated September 2004
- ERIP 5, Radiation Center Complex Evacuation Procedures, dated September 2004
- ERIP 6, Emergency Procedures to Follow on Receipt of a Bomb Threat, dated September 2004
- ERIP 7, Emergency Activation and Notification Procedures, dated September 2004
- ERIP 8, News Release Policy and Guidelines, dated September 2004
- OSTROP 1, Emergency Operating Procedures, Rev. 7, October 2004 b. Observations and Findings The Emergency Plan (E-Plan) in use at the facility was the same as the version approved by the NRC and was last revised December 2005 but another revision was to be submitted. The E-Plan was audited and reviewed annually by the ROC as required. Implementing procedures were also reviewed annually and revised by the licensee as needed to implement the E-Plan effectively. It was also noted that emergency response equipment at the Radiation Center was being maintained and inventoried as required.
Through records review and through interviews with licensee personnel, emergency responders were determined to be knowledgeable of the proper actions to take in case of an emergency. Emergency response facilities and equipment were being maintained as required. An Emergency Support Agreement with the Good Samaritan Hospital in Corvallis, to treat potential victims of a radiological event, had been updated and maintained as necessary.
Agreements were also being maintained with the City of Corvallis Fire and Police Departments as required. Communications capabilities were acceptable with the support groups and were tested periodically, generally daily. Personnel from these off-site support organizations visited the facility periodically and were familiar with the facility and what would be required during a response.
The inspector visited the Corvallis Fire Department (CFD) and observed the equipment maintained by the CFD for response to an emergency at the Radiation Center. From this observation and as a result of reviewing the licensees records documenting drills and training, the inspector verified that CFD personnel were well trained, properly equipped, and knowledgeable of the actions to take in case of an emergency at the reactor facility. The inspector determined that the licensee was maintaining a good working relationship with this support group.
Emergency preparedness and response training for staff and specific support group personnel was being completed annually as required. Evacuation drills
had been conducted each year as well. The licensee was also conducting drills annually as stipulated in the E-Plan in order to test communications procedures and check on the response of facility personnel to simulated radiological, industrial hazards, or security problems. The inspector verified that every two years the drills were structured to involve and require the participation of off-site support agencies and personnel. Critiques were conducted following the drills to discuss and identify any strengths or weaknesses noted.
c. Conclusions The emergency preparedness program was conducted in accordance with the Emergency Plan.
10. Follow-up on Previous Identified Items a. Inspection Scope (IP69001)
The inspector reviewed the licensee's actions taken in response to a previously identified item in NRC Inspection Report No. 50-243/2004-201, dated August 19, 2004:
! 50-243/2004-201-01 - VIO - Failure to have an operator with an active license complete a medical examination every two years as required by procedure.
b. Observation and Findings (Closed) VIO 50-243/2004-201-01 - During an inspection in August 2004, the inspector reviewed the medical examinations conducted for each operator. Each operator was typically scheduled to have a medical examination biennially in accordance with procedures. On August 3, 2004, the inspector noted that all operators but one had received the required medical examinations at the frequency specified in the requalification program. One operator had a medical examination in January of 2002 but had not had one since that time. When the licensee was made aware of this situation, the individual was administratively suspended from performing reactor operations until he passed the required examination. The licensee was able to schedule an examination immediately, which was completed on August 4, 2004. However, the paperwork documenting the results was not available during the inspection.
During this inspection, the inspector reviewed the 2004 paperwork and found it to be acceptable. It was also noted that an item had been added to the Annual Surveillance and Maintenance form to list when each operators annual written exam and operating tests were due, when the biennial medical exam was due, and when the 6-year license renewal was due. This item is considered closed.
c. Conclusions One violation identified during a previous inspection was reviewed and closed during this inspection.
11. Exit Interview The inspection scope and results were summarized on August 10, 2006, 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 inspection of these program areas.
PARTIAL LIST OF PERSONS CONTACTED Licensee Personnel M. Hartman Reactor Administrator T. Keller Senior Reactor Operator Director, OSU Radiation Center S. Smith Instrument Technician and Senior Reactor Operator G. Wachs Reactor Supervisor Other Personnel R. Maldonado Hazardous Material (HAZ MAT) Team Leader, Corvallis Fire Department T. Palmer Chairman, Reactor Operations Committee INSPECTION PROCEDURE USED IP 69001 Class II Non-Power Reactors ITEMS OPENED, CLOSED, AND DISCUSSED Opened None Closed VIO 50-243/2004-201-01 Failure to follow procedure and complete a medical examination for each operator biennially as required.
LIST OF ACRONYMS USED ALARA As Low As Reasonably Achievable CFD Corvallis Fire Department CFR Code of Federal Regulations ERIP Emergency Response Implementing Procedure IP Inspection Procedure LCO Limiting Conditions for Operation NRC Nuclear Regulatory Commission NCV Non-cited Violation OSU Oregon State University OSTR Oregon State University TRIGA Reactor OSTROP Oregon State University TRIGA Reactor Operating Procedure Rev. Revision ROC Reactor Operations Committee ROCAS Reactor Operations Committee Approval Sheets SRO Senior reactor operator TS Technical Specifications VIO Violation