IR 05000113/1998201
| ML20236F464 | |
| Person / Time | |
|---|---|
| Site: | 05000113 |
| Issue date: | 06/26/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20236F460 | List: |
| References | |
| 50-113-98-201, NUDOCS 9807020176 | |
| Download: ML20236F464 (19) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No: 50-113 License No: R-52 t Report No: 50-113/98-201 l
Licensea: University of Arizona l
Facility: Nuclear Reactor Laboratory Location: Engineering Building (202)
Tucson, Arizona l Dates: May 26-29,1998 L
i Inspector: Stephen W. Holmes, Reactor Inspector Approved by: Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation 9907020176 990626 i PDR ADOCK 05000113 *
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EXECUTIVE SUMMARY This routine, announced inspection consisted of the review of selected conditions and records, evaluation of actions regarding a licensee information report on thermal power calibration, and related discussions with licensee personnel. Additionally the inspector observed a reactor critical operation from start-up to shutdown and observed health physics staff performing routine surveys. The inspection was conducted following the guidance of NRC Inspection Manua The reactor was being maintained and operated as required by the license and applicable l regulations. Licensees' operations, surveillance and operator requalification records and checklists were notable in their clear and concise documentation and control of Technical 1 Specification requirements. Licensee actions regarding reactor thermal power calibration items and mode selector switch failure were acceptable. The last two emergency drills had .
extensive involvement from off-site agencies with productive result )
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Reoort Details Summarv of Plant Status Reactor operations were continuing to support research, reactor operator training, educational cources, and to performing preventive maintenance and operational surveillance required by the Technical Specifications (TS). No safety concerns were note Ooerations 01 Conduct of Operations 01.1 Reactor Staffing insoection Scoce (Insoection Procedure 69001)
The inspector reviewed reactor staff qualifications, operations logs and records, selected events, and interviewed staf Observations and Findings Licensed staff consisted of the Reactor Director (RD), the Reactor Supervisor (RS) position, two other Senior Reactor Operators (SRO), and a Reactor Operator (RO). The reactor staff satisfied the training and experience required by the T Operation logs and records confirmed that shift staffing met the minimum requirements for duty and on-call personne During the inspection the RD and RS informed the inspector that the RS was going to retire within the next two years. The inspector discussed with the licensee concerns and difficulties the loss of staff could cause without adequate replacement training, overlap with departing personnel, or other methods of insuring adequate tumover. The licensee acknowledged the inspector comment Conclusions The research reactor operations staffing satisfied TS requirement .2 Control and Performance of Experiments Insoection Scoce (Insoection Procedure 69001)
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l The inspector reviewed approved reactor experiments, reactor logs, documentation of experiments performed, experimental data, Reactor Committee (RC) minutes, and interviewed staff.
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! 2 Observations and Findinos The inspector verified that each routine, or not significantly different, experiment had been reviewed and approved by the RD or his designee and that new or significantly different ones were referred to the RC as required. Review of the experiment procedures and reactor log books, interviews with staff, and i observation by the inspector verified that experiments were constrained as required by the TS and experiment authorization. The experiments were also
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installed, performed, and removed as outlined in the experiment authorization I and licensee's procedures. The checklist for Reactor Committee review of experiments ensured experiments conformed to TS and license requirements, had safety constraints for the hazards identified, and experimenter oversigh Conclusions )
License control and performance of experiments met TS and licensee requirement .3 Reactor Ooerations and Fuel Handlina insoection Scoce (Insoection Procedure 69001)
The inspector interviewed staff, reviewed reactor operations and fuel logs, and periodic checkout, start-up and shutdown checklists. The inspector also observed a start-up, steady state power operation, and shutdow Observations and Findinag Reactor operations were carried out following written procedures and T Information on operational status was recorded in log books and checklists as required by procedures and TS. Use of maintenance and repair logs satisfied regulatory and licensee requirements. Significant problems and events noted in the operations log were reported to the RD, RC, and the NRC quickly resolved as required by TS and licensee administrative procedure Fuel movement and handling was infrequent. Data recorded for fuel movement was clear. Fuel movement, inspection, log keeping, and recording followed the facility's procedure Conclusions Reactor operations conformed to TS and licensee procedural requirements. Fuel handling, record maintenance, and documentation were accomplished as required by TS and licensee procedures. No safety concerns were identified, i
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02 Operational Status of Facilities and Equipment insoection Scoce (Insoection Procedure 69001)
i The inspector reviewed reactor equipment, evaluated the physical plant, and '
observed the facility and equipment during a tou I Observations and Findinas Equipment was accessible with no extraneous clutter. All required equipment l and facilities observed by the inspector were operational, Conclusions Reactor and support. facilities were operational as require Operations Procedures and Documentation Insoection Scoce (Insoection Procedure 69001)
i The inspector reviewed operating procedures and updates, reactor operating records and logs, RC minutes, interviewed staff and observed reactor operation Observations and Findinas Written procedures required by the TS were available and used by the staff. Use of and adherence to the procedures was acceptable. Procedures were routinely updated as needed. The inspector verified that the reactor facility procedures had been reviewed and approved by the RC as required by TS. Minor changes ;
were approved by the RS as authorized. The inspector identified a few places
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where obsolete terms, references to deleted programs, and changed directives had been missed during these updates. The licensee stated that they would review the procedures, checklists, logs, etc. and correct these inconsistencie This will be reviewed during a future inspection as an inspection Follow-up Item j (IFI) 50-113/201-01-0 Records of power level, operating periods, unusual events, calibration and maintenance procedures, installed experiments, and start-up and shutdown checks were being kept. The licensee's logs and records were clear, concise, and legible. The inspector determined that the annual reactor operating reports, logs, and records acceptably documented reactor operations activities. Reactor l ' operations and testing were documented as required by the TS.
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The inspector traced scrams identified in the logs and records and verified that they were reported and resolved as required before the resumption of operations lunder the' authorization of a SR _- ____ _ _ - _ _ _ _ _ - _
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l 4 Conclusions Facility operational procedures satisfied TS requirements. Reactor operating !
records and logs were being maintained as required by TS. Significant problems and events identified in the logs and records were reported and resolved as require Operator Training and Qualification Program Insoection Scooe (Insoection Procedure 69001)
The inspector reviewed requalification program records, NRC licenses, training records, SRO operational hours and interviewed staf . Observations and Findinas Currently licensed operators were participating in the ongoing training as required by the NRC-approved requalification plan. Lectures were conducted as require The lecture outline for the reactor operator requalification program included appropriate subject material and a comprehensive written examination, which j had been given and successfully passed by the reactor operator Requalification training records contained the documentation required by the approved operator requalification program. Biennial medical exams had been completed as require SRO operational hours were tracked to ensure that the performance requirements of 10 CFR 55 was met. Checklists used for tracking requalification requirements were commendable and ensured that the plan elements were accomplishe Conclusions The reactor operator requalification training program was being conducted and documented following the NRC approved program. Reactor operator requalification training records were being acceptably maintained. TS and NRC-approved requalification plan requirements were me Organization and Administration I insoection Scoce (Insoection Procedure 69001)
The inspector reviewed organization, staffing and administrative controls and interviewed management and staf l 1 Observations and Findinas Since the last inspection no functional changes in the management organization
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5 Conclusions Organizational and administrative controls remain consistent with TS and license requirements and commitment Quality Assurance in Operations Insoection Scone (Insoection Procedure 690011 The inspector reviewed RC minutes, annual reviews, audits, the audit and review program checklist,50.59 and new/ modified experiment approvals, and interviewed staff, Observations and Findinas RC membership satisfied TS requirements and the Committee's procedural rule The RC had quarterly meetings as required. Appointment letters were curren Review of the minutes showed that the RC provided guidance, direction, safety oversight, and ensured suitable use of the reactor. Review of the committee's comprehensive actions on 50.59 approvals of the console mode switch modification and the 12 volt console lights / exhaust fan relay power supply replacement, and the modified RASR experiment approval confirmed that the RC was actively performing its dutie Since the last inspection all required audits of reactor facility activities and reviews of procedures, equipment changes, proposed tests or experiments, had been performed and documented. Additionally the reviews of the emergency
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and security plans had been conducted and acceptably documented. Audits i
were performed throughout the year meeting the annual frequency requirement The use of audit and program checklists was noteworthy.
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The RC meeting frequency satisfied TS requirements. Audits were conducted as i
required. The RC carried out its safety duties as obligated by license, TS, and administrative criteri , ll. Maintenance M1 Conduct of Maintenance M1.1 Surveillance and Limitina Conditions for Ooeratiori Insoection Scoce (Insoection Procedure 69001)
The inspector reviewed selected surveillance records, data sheets and records of tests, licensee procedures, reactor logs, checklists, periodic reports, and interviewed staf ,
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b. . Observations and Findings Daily and other periodic checks, tests, and verifications for TS required limiting conditions for operations (LCO) were completed as required. Surveillance and LCO verifications were completed on schedule as required by TS and following licensee piocedures. All were within prescribed TS and procedure parameters and in close agreement with the previous surveillance result Extensive checklists were used to track daily, monthly, and annual" (including semiannual through biennial to five year /500 pulse items) surveillance, checks, audits, drills, training, and inspections. ; The checklists included date last performed, date presently completed, and information on where documented, and by whom. These checklists provided clear and concise documentation and
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control of reactor operational tests and surveillance. Use by the licensee was comprehensive and timel l fenclusions The facility's program for surveillance, LCO confirmations, and inspections satisfied TS requirements. The licensee's extensive use of !n-depth checklists was notabl M2 Maintenance and Material Condition of Facilities and Equipment Insoection Scone (Insoection Procedure 69001) f
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The inspector reviewed maintenance and reactor logs, RC minutes, repair records, and observed facility and equipment during accompanied tours, surveys, and operations.
l Observations and Findinos Routine / preventative maintenance was controlled and documented in the i maintenance or operations log. Unscheduled maintenance or repairs were reviewed to decide if they required a 50.59 evaluation. Verifications and operational systems checks were performed to ensure system operability before return to service. This included a statement signed by the RS indicating that the system had been tested for operation and that the reactor was approved for operatio c. - Conclusions !
Maintenance logs, records, performance, and maintenance reviews satisfied TS and procedure requirements.
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MB Miscellaneous Maintenance issues M8.1 Malfunction of Mode Selector Switch Insoection Scone (Insoection Procedure 69001)
The inspector reviewed the safety evaluation of the mode selector switch modification, the minutes of the RC meetings, reactor and maintenance logs, and interviewed staf Observations and Findinas On November 4,1997, the licensee experienced a failure of the reactor mode switch when performing a pulse. The switch failed to shift between the normal and high range signals when rotated from its manual to pulse settin This was reported to the NRC on November 5,1998, by telephone, fax and subsequent by a letter dated November 13,199 The licensee halted operations, evaluated the consequences, investigated the failure, identified the cause, and took corrective action The consequences of the failure had no effect on the physical performance of the pulse which was normal nor the recorded fuel temperature rise and timer scram expected for a standard pulse. However, no valid indication for peak or integrated power was rccorded at the console and the right safety channel showed a trip on reactor power. This along with an 11-ms period recorded by the digital data acquisition system connected to the right safety channel confirmed that the channel was still connected to the ion chamber used in steady state mode rather than the high range chamber for pulsing. The inspector corroborated the licensees conclusion that the system failed safe with a scram at 110-kw, that it did not operate outside its normal envelope and there was no safety concern for the publi The cause of the failure was the rear wafer becoming mechanically misaligned due to loosening, overtime, of the rear case bolt nuts. These bolts also held the internal wafer assembly in alignmen The licensee processed a modification to the mode switch to add a nut and lock washer on each bolt to hold the wafer assemblies in place internally, independent of the rear case nuts. The modification was reviewed and approved by the RC following their 50.59 procedures. Updated SAR drawings were made and post installation testing was performed to ensure proper operatio _ _ _ _ _ _ _ _ _ _ _ .
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8 Conclusions The licensee evaluation, investigation, identification, and corrective actions of the mode switch failure were as reported to the NRC and satisfied regulatory requirements M8.1 Reactor Power Calibration Concern Insoection Scoce (Insoettion Procedure 69001)
The inspector reviewed the reactor thermal power calibration records, reactor procedures, the minutes of the RC meetings, reactor and maintenance logs, and interviewed staf Observations and Findinas
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During a power calibration performed September 30,1997, at 90-kW indicated l
on the liner channel, the licensee noted that the readings on the left and right I safety channels were 84-kW and 86-kW respectively. The calculate actual
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power level for the run was 92 +/- 1.5kW. Therefore, although the actual !
settings of each safety channel were less than 110-kW as required, the two channels red low by 8-kW and 6-kW which was a larger discrepancy than l expected based on historical operating experience for this reactor. The licensee was concerned that the discrepancy was in such a direction that non-conservative settings may have been possible in that the safety channel could read lower than the linear channel by a margin greater than the difference between the scram set point and 110-kW, the maximum licensed powe '
This was reported to the NRC on October 1,1997, by telephone, fax and subsequently by letter dated October 22,199 The licensee halted operations, evaluated the consequences, investigated the cause, and took remedial action The inspector confirmed the licensee's evaluation that at no time since the last power calibration, July 31,1997, was the reactof operated in excess of its licensed power or in an unanalyzed condition, and that there was no safety significance to the reported condition The licensee's investigation identified two items that may have effected the July 31,1997, power calibration. First, the July 31,1997, calibration was a day after a three hour run at 100-kW, thus the' core still contained xenon fission product poisons. Second, after the fuelinspection performed June 3-4,1997, a number of the fuel elements may not have been fully seated. Reactor flux profile during short high power runs would therefore tilt towards the west side of the core making the safety channels read low relative to the linear channe . _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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The inspector verified that the reseating of the suspeccted elements on L August 5,1997 and the calibrations performed September 30, October 2, and I October 7 resulted in the three power indication channels agreeing with the rneasured power and between the three channels themselves. Additionally changes were made to the operating procedures directing the operators to monitor and record the magnitude of the differences between the channels and j l
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when operating above 50-kW, to shut down, if the magnitude is greater than that between the scram set point and 110-kw. The RD is also required to review the data following a power calibration and to post the selected set point margins on the status board. These actions were confirmed by the inspector.
l- Conclusions The licensee's cessation of operations, and evaluation, investigation, and remedial actions of the power calibration concern were as reported to the NRC and satisfied regulatory requirement I til. Enaineerina
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E1 Conduct of Engineering, Design Changes I a. lasoection Scooe Unsoestion Prorgdure 69001)
The inspector reviewed procedures, logs, records, RC files, and interviewed staff. The inspector also reviewed the change packages for the consola mode switch modification and the 12 volt console lights and exhaust fan relay power ;
supply replacement. The inspector also reviewed the FSAR and TS basis, b. Observations and Findinas The packages for design changes were kept with the RC minutes. Changes were rigorously controlled requiring a staff review, a committee review, and were recorded in the facility logbook or the Reactor Upgrade and Instrument Lo Questions from the committee and replies from the reactor and HP staffs were l
documented and incorporated into the modification package The inspector reviewed the packages for the console mode switch modification
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L The evaluations were far-reaching with supporting documentation and information. RC involvement was also comprehensive. Post installation verification testing of the systems was thorough. Procedure and drawing changes were included and were consistent with the observations of the inspector.
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. Conclusions The licensee's design changes were reviewed, approved, carried out, tested, and controlled as required by TS, licensee procedures, and pertinent regulation IV. Plant Sunoort R1 Radiological Protection and Chemistry Controls R1,1 Raciation Protection Postinas Scoce (Insoection Procedure 69001)
The inspector reviewed radiological signs and postings, routine radiation surveys and observed the facility and equipment during accompanied tour Observations and Findinas Postings were acceptable for the hazards involved. NRC Forms-3 were posted in the facility as were current notices to workers required by 10 CFR Part 1 Conclusions ,
Radiological postings satisfied regulatory requirement R1.2 {iaseous Effluent Monitorina and Release Scooe (Insoection Procedure 69001)
The inspector reviewed annual reports, release records, counting and analysis results. The inspector interviewed reactor and HP staff Observations and Findinar Gaseous releases were calculated from integrated power using the COMPLY
. Code. Releases were acceptably documented and well within the annual dose constraint of 20.1101(d) and the Appendix B concentration limits, i Conclusions Gaseous effluent monitoring and releases satisfied regulatory requirements.
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. R1.3 Radiation Protection Survevs - Scone (Insoection Procedure 69001)
The inspector reviewed procedures and survey records, and interviewed staf Observations and Findinos Monthly and other periodic contamination and radiation surveys including pool water analyses were done by reactor and HP staffs as required by TS and licensee procedures. Results were evaluated and corrective actions taken and documented when readings /results exceeded set action level Survey results verified that contamination in the facility was infrequent and both identified contamination and radiation levels were well below regulatory and licensee limit Conclusions Surveys were performed and documented as required by 10 CFR Part 20. TS and licensee requirements were me R1.4 Personnel Dosimetrv Scoce (Insoection Procedure 69001) *
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The inspector reviewed dosimetry records, licensee procedures, and interviewed staf Observations and Findinos The licensee used a National Voluntary Laboratory Accreditation Program-Accredited vendor to process personnel thermoluminescent dosimetry. An examination of records for the past year showed that all exposures were within NRC limits, with most having no exposure above background. Records were reviewed by the RSO. ALARA and declared pregnancy programs were in effec Conclusions Doses were in conformance with licensee and 10 CFR Part 20 limits. The dosimetry program was conducted in accordance with 10 CFR 20.1501, 10 CFR 20.1502, and licensee procedures.
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R2 Status of Radiation Pro ution and Control (RP&C) Facilities and Equipment Scoce (Insoection Procedure 69001) 1 The inspector reviewed the licensee's inventory, calibration, and periodic checks I of portable radiation survey and laboratory instruments, and interviewed HP staf Observations and Findings l
Calibrated instruments were available at the time of inspection. Instruments used to perform radiation surveys were calibrated with radioactive sources traceable to nationsi standards. Calibration frequencies satisfied TS i requirements, l l
The calibration of the GeLi multi-channel analyzer followed the manufacturers'
recommendations and used calibration sources in the same geometry as the actual samples analyzed. All instruments checked were in calibratio Calibration records were in orde Conclusions l
l RP&C equipment was being maintained according to industry and equipment I manufacturer standards. Calibrations satisfied TS requirement P1 Conduct of Emergency Preparedness Activities and Staff Training
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The inspector reviewed the emergency plan (EP) procedures, training and drill records for the reactor and interviewed licensee employees to determine 1 compliance with regulatory, TS, and licensee requirements, Observations and Findinas The drill documentation consisted of a scenario, a description of the emergency j responders' actions as noted by the designated observers, and a summary of the l critique of the exercise by the participants and observers. This acceptably I documented the drill. The exercise was conducted according to, and fulfilled, i the requirements stipulated in the Emergency Plan. Key licensee emergency l response personnel demonstrated that they could respond to emergencies as I required. Offsite response by security, law enforcement, and other responders were acceptable for the scenario involved. Involvement of offsite personnel was ( comprehensive and well coordinated. Items identified by individual critiques were addressed, evaluated, and then incorporated when appropriat Training records verified that acceptable training had been provided to in-house staff and outside responders.
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13 Conclusions The licensee's emergency plan was effectively carried out as required. EP drills and training were acceptably being conducte P2 Status of EP Facilities, Equipment, and Resources Insoection Scone (Insoection Procedure 69001)
The inspector reviewed inventory records, checked EP facilities, equipment and supplies, and interviewed staf . Observations and Findinos
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Equipment and supplies were as required by the EP and inventory record Support facilities and communications were also as specified by EP requirement.
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The inspector reviewed the EP documents and implementing procedules and interviewed staff.
! , Observations and Findinas l The procedures were current, approved and were readily available for use by L response personnel. They acceptably addressed classification, notification, and protective actions required during an emergency to protect the health and safety l l of the public. Implementing procedures were consistent with the EP
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requirements. Emergency phone list and on-call lists were also readily available and up-to-dat Conclusions i J
EP procedures and documentation were as required by the NRC approved EP and !
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S1 Conduct of Security en? Safeguards Activities I Insoection Scoce (Insoection Procedure 69001) 4 The inspector reviewed the NRC-approved security plan, toured the facility,
reviewed security logs, reports, and security related drill documents, and i interviewed reactor and security staff Observations and Findinas The reactor control room and the adjoining reactor pool room were secured with only those persons authorized by the plan having keys to the facility. University police provided security as required by the plan. The inspector verified that security checks were performed, tracked, and corrective actions taken when required. Communication between the RD and the University Police was ongoing and kept each informed of current activities. Reactor test / verification of the security systems were performed as require Conclusions Conduct of security and safeguards activities satisfied the NRC approved pla i S2
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Status of Security Facilities, Equipment, and, Procedure insoection Scoce (Insoection Procedure 69001)
The inspector reviewed the NRC approved security plan, toured the facility, reviewed security logs, reports, and security related drill documents, and interviewed reactor and security staffs Observations and Findinns The inspector verified that the safeguards system was as described in the NRC l approved p!an. The system provided detection and assessment of unauthorized assess and detection of removal of special nuclear materia from the facilit The inspector verifieu that the alarms, devices, and procedures used were adequate to allow the university police to detect and respond to unauthorized activities. Response rosters were current and posted as require Conclusions Security facilities, equipment, and, procedures satisfied plan requirements, i
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i V. Manaaement Meetinas X1 Exit Meeting Summary (
The inspector presented the inspectson results to members of licensee management
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at the conclusion of the inspection on May 29,1998. The licensee acknowledged
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PARTIAL LIST OF PERSONS CONTACTED Licensee
- H. Doane Reactor Supervisor
'C. Garcia Assistant Director, Arizona Research Labs K. Haywood Commander, University of Arizona Police Department
- J. Williams Reactor Director
- D. Silvain Pediation Safety Officer A. Speaker Chairman, Reactor Committee C. Soundhaus Director, Radiation Control Office
' Attended Exit Meeting INSPECTION PROCEDURE (IP) USED IP 69001: CLASS 11 NON-POWER REACTORS ITEMS OPENED, CLOSED, AND DISCUSSED QD_9119_d IFl 50-113-98-201-01 UPDATE OF PROCEDURES, CHECKLISTS AND LOGS CLQD. NONE PARTIAL LIST OF ACRONYMS USED HP Health Physics EP Emergency Plan FSAR Final Safety Analysis Report LCO Limiting Conditions for Operations NRC Nuclear Regulatory Commission RD Reactor Director RO Reactor Operator RS Reactor Supervisor RSO Radiation Safety Officer RC Reactor Committee SRO Senior Reactor Operator TS Technical Specifications l
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