IR 05000116/1999201
| ML20211J436 | |
| Person / Time | |
|---|---|
| Site: | University of Iowa |
| Issue date: | 09/01/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20211J415 | List: |
| References | |
| 50-116-99-201, NUDOCS 9909030141 | |
| Download: ML20211J436 (15) | |
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Il U. S. NUCLEAR REGULATORY COMMISSION L
r Docket No:
50-116
l License No:
R-59 Report No:
50-116/99-201 d
Licensee:
lowa State University
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Facility:
UTR-10 Research Reactor
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Location:
Ames, Iowa Dates:
August 10-12,1999 i
inspector:
Thomas M. Burdick l
Approved by:
- Ledyard B. Marsh, Director Events Assessment, Generic Communications and Non-Power Reactors Branch Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation i
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9909030141 990901 I
PDR ADOCK 05000116
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EXECUTIVE SUMMARY This routine, announced inspection included onsite review of selected aspects of the operations program, organizational structure and functions program, design control program, review and audit program, radiation protection program, environmental protection program, operator requalification program, maintenance program, surveillance program, fuel handling program, experimental program, procedural control program, emergency preparedness program, material accountability program, security program, and transportation program since the last NRC inspection of this program.
l The licensee's programs were acceptably directed toward the protection of public health and safety, and in compliance with NRC requirements.
ORGANIZATIONAL STRUCTURE AND FUNCTIONS The licensee is seeking replacements for two of the Reactor Use Committee members who recently resigned.
OPERATIONS Reactor operations ceased in May 1998 as the licensee proceeded with their plans to ship fuel and begin decommissioning.
DESIGN CONTROL The licensee replaced some channels of the radiation monitoring system and removed others from service since the last inspection.
REVIEW AND AUDIT The licensee conducted all the required audits within the specified intervals.
RADIATION PROTECTION Facility activities did not result in contamination or exposure.
ENVIRONMENTAL PROTECTION The licensee took the necessary precautions to ensure that they met the requirements when they disposed of the reactor coolant.
OPERATOR REQUALIFICATION
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Operator requalification under the most recently approved program was completed as required.
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MAINTENANCE No significant maintenance was conducted since the last inspection.
SURVEILLANCE The licensee corrected their problem with timely reactor protection surveillance completion identified in the last inspection while the overall burden has been reduced due to their
" possession only" status.
FUEL HANDLING Much of the licensee's activity had involved fuel handling since the last inspection and no problems occurred.
EXPERIMENTS The licensee performed one last new experiment before they ceased operations last year.
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PROCEDURES Procedures were properly developed and reviewed for the licensee's fuel handling operations.
The licensee assured emergency drills, training, and equipment readiness verification were done as required.
i FUEL INVENTORY The licensee met their requirements for maintaining proper accountability of Special Nuclear Material (SNM) of Low Strategic Significance.
j SECURITY The licensee maintained security requirements for both fixed and transit conditions.
TRANSPORTATION Shipments of fuel and other SNM were conducted by the licensee according to regulations.
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Report Details Summary of Plant Status The reactor operated until May of 1998 to support education and experiments. The licensee then unloaded the reactor core, shipped SNM except the used low enriched fuel, four fission chambers, and several Uranium foils which they hope to ship this year.
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DRGANIZATIONAL STRUCTURE AND FUNCTIONS a.
Scope (69001)
The inspector reviewed selected aspects of:
organization and staffing e
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qualifications e
management responsibilities i
e administrative controls
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b.
Observations and Findinas The organizational structure and sts.ifing had changed since the last inspection.
Additional personnel were employed and some were licensed to assist in conducting operations, fuel shipping, and testing. The organizational structure and staffing at the facility and as reported in the Annual Report was as required by technical specification
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(TS). Qualifications of the staff met TS requirements. Review of records verified that management responsibilities were administered as required by TS and applicable procedures.
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Conclusions The organizational structure and functions were consistent with TS requirements.
2.
OPERATIONS a.
Scope (69001)
The inspector reviewed selected aspects of:
operationallogs and records e
e staffing for operations b.
Observations and Findinas Reactor operations ceased in May 199 ]
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Conclusions
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Reactor operations ceased in May 1998 as the licensee proceeded with their plans to
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ship fuel and begin decommissioning.
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DESIGN CONTROL a.
Scope (69001)
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The inspector reviewed selected aspects of:
e facility design changes and records j
e facility configuration
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b.
Observations and Findinas
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. Records and observations showed that changes at the facility were acceptably reviewed in accordance with 10 CFR 50.59 and applicable licensee administrative controls.
i Upgraded replacement area radiation monitoring channels were installed in three locations while the remaining channels were deactivated under the amended
" possession only" TS.
Year 2K issues at lowa State's UTR-10 were not considered a problem since the reactor cannot be operated and was permanently defueled in 1998, Systems required to
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operate are limited to physical security and area radiation monitoring. Neither of these l
systems will be adversely affected.
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Conclusions The design change program satisfied NRC requirements.
4.
REVIEW AND AUDIT a.
Scope (69001)
The inspector reviewed selected aspects of:
e safety review records e
audit records e
responses to safety reviews and audits e.
review and audit personnel qualifications
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Observations and Findinas Records showed that the safety reviews were conducted at the TS required frequency.
Topics of these reviews were also consistent with TS requirements to provide guidance, direction, and oversight, and to ensure acceptable use of the reacto l
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The audit records showed that audits had been completed in those areas outlined in the TS and at the required frequency.
The inspector noted that the safety reviews and audits and the associated findings were l
acceptably detailed and that the licensee responded and took corrective actions as I
needed.
(Closed) Follow-Vo item 50-116/97201-03: failure of the licensee to include fuel shipping quality assurance in the annual audit of licensee programs. The licensee had identified the problem before the last inspection and included it in their last two audits.
The safety review and audit personnel qualifications satisfied TS requirements and licensee administrative controls in most cases. The inspector noted that the Reactor Use Committee (RUC) Chair had audited the RUC function which was not consistent with TS 6.2.4 requirements. The licensee acknowledged the concern. Further, the number of personnelinvolved in the safety reviews and audits also satisfied TS and licensee procedural requirements.
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Conclusions The review and audit program satisfied TS requirements.
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RADIATION PROTECTION a.
Scoce (69001)
The inspector reviewed selected aspects of:
the Radiation Protection Program e
radiological signs and posting o
routine surveys and monitoring
dosimetry records e
maintenance and calibration of radiation monitoring equipment e
As Low As Reasonably Achievable (ALARA) reviews e
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Observations and Findinas
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I The radiation protection program had not changed since the last inspection. The I
licensee reviewed the radiation protection program at least annually in accordance with 10 CFR 20.1101(c). The review included all areas and no weaknesses were reported.
The licensee showed that the air emissions or radioactive material to the environment met the 10 millirem constraint specified in 10 CFR 20.1101(d).
NRC Form 3, " Notice to Employees," was posted in accordance with 10 CFR 19.11.
i Caution signs, postings and controls to radiation areas were as required in 10 CFR 20, q
Subpart J. Licensee personnel observed the indicated precautions for access to the J
radiation areas.
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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 dosimetry. Radiological exposure records showed that occupational doses and doses to the public were within j
10 CFR Part 20 limitations. Training records showed that personnel were acceptably l
trained in radiation protection practices.
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Radiation monitoring and curvey activities were as required. Equipment used for these activities were maintained, calibrated and used acceptably.
ALARA reviews were acceptably performed at required.
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The licensee did not require a respiratory protection program or planned special exposure program.
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Conclusions
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The radiation protection program satisfied NRC requirements.
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ENVIRONMENTAL PROTECTION l
a.
ScoDe (69001)
The inspector reviewed selected aspects of.
the environmental monitoring program
o annual reports e
release records e
counting and analysis program
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Observations and Findinas Observation of the facility found no new potential release paths. Reactor operations did i
not exceed TS limits designed to keep airbome emissions below limits.
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The program for the monitoring and storage of radioactive liquid, gases, and solids was consistent with applicable regulatory requirements. The licensee monitored and released all of its reactor coolant to the sanitary sewer when activity was below acceptable limits. Other radioactive low level waste 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 maintained.
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Conclusions The environmental protection program satisfied NRC requirements.
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OPERATOR REQUALIFICATION '
a.
Scooe (69001)
The inspector reviewed selected aspects of:
the Requalification Program e
e operators' licenses e
operator training records e
operator physical examination records e
operator examination records e
operator active duty status
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Observations and Findinas The Requalification Program was maintained up to date. Operators' licenses were also current. Records showed that operator training was consistent with the Requalification Program requirements. Physical examinations of the operators were conducted as required.: Records showed that written and operating examinations of the operators were acceptably implemented. Logs showed thzt operators maintained active duty status as required.
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Conclusions Operator requalification was conducted as required by the Requalification Program.
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MAINTENANCE
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a Scooe (69001)
The inspector reviewed selected aspects of:
maintenance procedures o
e equipment maintenance records
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Observations and Findinas i
Logs indicated that corrective maintenance activities and problems were addressed as required by procedure. Records showed that routine maintenance activities were i
conducted at the required frequency and in accordance with the TS, applicable procedure, or equipment manual. Maintenance activities ensured that equipment remained consistent with the Safety Analysis Report and TS requirements. Further, maintenance activities were consistent with the requirements of 10CFR 50.59.
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' Conclusions -
The maintenance program satisfied NRC requirements.
9.
SURVElLLANCE
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Scooe (69001)
The inspector reviewed selected aspects of:
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. surveillance and calibration procedures, e-surveillance, calibration and test data sheets and records b.
Observations and Findinas Since the last inspection the licensee requested and obtained a " possession only"
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license amendment that reduced their survaillance requirements.
Surveillance, test and LCO verifications and calibrations 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 complete and were being maintained as required. Checks, tests, and calibrations were completed as required by TS.
(Closed) Violation 50-116/97201-01: failure of the licensee to conduct surveillance required by TS prior to operating the reactor. The licensee provided sufficient qualified stafling to prevent a recurrence of the problem identified during the last inspection. The reactor is defueled and no longer operated.
(Closed) Follow-Uo item 50-116/97201-02 : licensee identified the failure to conduct emergency power supply battery surveillance at the prescribed intervals. The licensee had identified the problem and corrected it. The batteries were tested as required following the last inspection, c.
Conciusions The surveillance program satisfied TS requirements.
10.
FUEL HANDLING
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Scope (69001)
The inspector reviewed selected aspects of:
e fuel-handling procedures-e fuel handling equipment and instrumentation e
fuel handling and examination records
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Observations and Findinas
l-The licensee made two fuel shipments since the last inspection.
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l Fuel-handling procedures provided a prescribed method to move and handle fuel l
consistent with the provision'of ti's TS and the licensee safety analyses. Fuel
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movement and fuel examination records showed that the fuel was moved and examined l
as required. Records also show that fuel-handling and monitoring equipment and
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instrumentation were verified operable prior to use. Personnel were knowledgeable of (
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the procedural and equipment requirements for criticality control and assurance of fuel integrity. Radiological and security precautions were also met in accordance with i
applicable procedures.
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Conclusions l
The fuel handling program satisfied licensee TS and procedural requirements.
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EXPERIMENTS
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Scooe (69001)
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The inspector reviewed selected aspects of:
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experimental program requirements
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e logs and records experimental administrative controls and precautions e
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Observations and Findinos
l One new type of experiment had been initiated, reviewed, and approved since the last
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inspection. The experiments were completed with the cognizance of the Reactor Supervisor and a Senior Reactor Operator and in accordance with TS requirements (e.g., reactivity limitations). The results of the experiments were documented in appropriate experimental logs, data sheets, or records. Engineering and radiation protection controls were implemented as required to limit exposure to radiation.
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Conclusions
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l The program for experiments satisfied TS and procedural requirements.
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PROCEDURES a.
Scope (69001)
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The inspector reviewed selected aspects of:
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e administrative controls records for changes and temporary changes e
e proceduralimplementation logs and records e
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Observations and Findinos Administrative controls of changes and temporary changes to procedures, and associated review and approval processes were as required. Training of personnel on l
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procedures and changes was acceptable. Personnel conducted activities in accordance
'with applicable procedures. Records showed that procedures for potential malfunctions
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(e.g., radioactive releases and contaminations, and reactor equipment problems) were implemented as required.
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The procedural control and implementation program satisfied TS requirements.
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Scope (69001)
The inspector reviewed selected aspects of:
the Emergency Plan e
e implementing procedures emergency response facilities, supplies, equipment and instrumentation e
e training records e
offsite support e
emergency drills and exercises b.
Observations and Findinos The umergency Plan (E-Plan) in use at the reactor and emergency facilities was the same as the version most recently approved by the NRC. The E-Plan was audited and reviewed as required. Implementing procedures were reviewed and revised as needed to employ the E-Plan effectively. Fa:ilities, supplies, instrumentation and equipment were being maintained, controlled and inventoried as required in the E-Plan. Through records review and interviews with licensee personnel, emergency responders were determined to be knowledgeable of the proper actions to take in case of an emergency.
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Agreements with outside response organizations had been updated and maintained as
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necessary. Communications capabilities were acceptable with these support groups
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and had been tested as stipulated in the E-Plan. Emergency drills had been conducted l
as required by the E-Plan. Off-site support organization participation was also as required by the E-Plan. Critiques were held following the drills to discuss the strengths and weaknesses identified during the exercise and to develop possible solutions to any problems identified. The results of these critiques were documented and filed.
Emergency preparedness and response training was being completed as required.
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Training for off-site and reactor staff personnel was conducted and documented as stipulated by the E-Plan.
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Conclusions The emergency preparedness program was conducted in accordance with the Emergency Plan.
14.
Material Control and Accountina a.
Scoce (85102)
The inspector reviewed selected aspects of:
e nuclear material inventory and locations accountability records e
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Observations and Findinas The inventory of material was verified. The material control and accountability program tracked locations and content of fuel and fission detectors under the research reactor license. The possession and use of special nuclear material (SNM) were limited to the locations and purposes authorized under the license. The material control and accountability forms (DOE /NRC Forms 741 and 742) were prepared and transmitted as required.
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Conclusions Special Nuclear Materials were acceptably controlled and inventoried.
15.
SECURITY
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a.
Scope (81401/81431)
The inspector reviewed selected aspects of:
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the Physical Protection Plan e
security systems, equipment and instrumentations
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e implementation of the Physical Protection Plan
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Observations and Findinas The Physical Protection Plan was the same as the latest revision approved by the NRC.
Physical protection systems (barriers and alarms), equipment and instrumentation were as required by the Physical Protection Plan. Access control was as required.
Implementing procedures were consistent with the Physical Protection Plan. Acceptable security response and training were demonstrated through alarm response and drill response in accordance with procedures.
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Conclusions Security activities and systems satisfied Physical Protection Plan requirements.
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TRANSPORTATION a.
Scooe (86740)
The inspector reviewed selected aspects of:
radioactive materials shipping procedures o
records of radioactive material transportation and transfer e
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b.
Observations and Findinas
' The licensee conducted two fuel shipments since the last inspection.. Radioactive material, other than SNM, was transferred for disposal to the broad scope license in accordance with licensee requirements. The program for radioactive material transpcrt is consistent with license requirements. Records also showed that transportation of the radioactive material and fuel were in accordance with DOT and NRC requirements.
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Conclusions The program for transportation of radioactive materials satisfied NRC requirements.
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l Partial List of Persons Contacted S. Wendt UTR-10 Reactor Director T. Zimmerman Iowa State University Environmental Health and Safety The inspector also contacted other supervisory, technical and administrative staff personnel as well.
Inspection Procedures Used IP 69001 Class ll Non-Power Reactors IP 81401 Plans, Procedures, and Reviews IP 81431 Fixed Site Physical Protection of LSNM IP 85102 Material Control and Accounting IP 86740 Transportation of Radioactive Materials items Opened and Closed Open None Closed 50-116/97201-01 VIO Licensee failure to conduct TS protection surveillance 50-116/97201-02 IFl Licensee failure to conduct emergency battery surveillance 50-116/97201-03 IFl Licensee failure to audit fuel shipping QA program List of Documents Reviewed Administrative Procedures Dosimetry Records Emergency Procedures Emergency Plan Maintenance and Surveillance Records Maintenance Procedures Operating Procedures and Records Reactor Operating License Safety Evaluation Report Safety Analysis Report Shipping program and procedures Surveillance Procedures Technical Specifications Training Records Training Program Various Reports
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List of Acronyms Used ALARA As Low As Reasonably Achievable DOE Department of Energy LCO Limiting Conditions for Operation NRC Nuclear Regulatory Commission RUC Reactor Use Committee SNM
. Special Nuclear Material TS Technical Specifications
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