IR 05000027/1998201
| ML20154A454 | |
| Person / Time | |
|---|---|
| Site: | Washington State University |
| Issue date: | 09/25/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20154A440 | List: |
| References | |
| 50-027-98-201, 50-27-98-201, NUDOCS 9810020311 | |
| Download: ML20154A454 (14) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No: 50-027
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License No: R-76 Report No: 50-027/98-201- ,
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Licensee: Washington State University l
Facility: Washington State University j TRIGA Reactor Location: Nuclear Radiation Center Roundtop D Pullman, Washington 99164 ustes: September 8-10,1998 Inspector: Stephen W. Holmes, Reactor Inspector Approved by: Seymour H. Weiss, Director Non-Power Reactors and Decommissioning Project Directorate 9910020311 900925 *
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J EXECUTIVE SUMMARY This routine, announced inspection consisted of the revisw of selected conditions and records since the last inspection, verification of corrective actions previously committed to l
by the licensee, review of licensee reported item, and related discussions with licensee i personnel. The inspection was conducted in accordance with the guidance of NRC Inspection Manua The reactor was being maintained and operated as required by the license and applicable regulations. Technical Specification required tests and surveillances were being done as required. As previously reported by the reactor director, minor poolleaks were being contained and sealing of the tank walls was being accomplished. Past deferred maintenance was being done and evaluation of reactor system maintenance needs was ongoing. The licensee plans to enhancing reactor pool and waste water analyses. One non-cited violation was noted for failure to provide the 1997 annual training to university police as required by the NRC approved security plan. One inspector follow-up item regarding the calibration of the liquid scintillation counter was close _
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Report Details Surrmary of Plant Status The reactor was being operated daily in support of research and training programs and for production of isotopes for outside contracts. Reactor tank wallleaks were being seale BNCT facility work activities were continuin l. Operations 01 Conduct of Operations 0 Reactor Staffina l l insoection Scone (Insoection Procedure 69001)
The inspector reviewed reactor staff qualifications, operations 'ogs and r3 cords, selected events, and interviewed staf l l Observations and Findinas l
l Since the last inspection, licensed staff consisted of the Director, Nuclear Radiation Center (DIR), the Reactor Supervisor (R'S), and two or three Reactor Operators and Senior Reactor Operators. The reactor staff satisfied the training and experience required by the Technical Specifications (TS). Operation logs and records confirmed that shift staffing met the minimum requirements for duty and on-call personnel for day and evening shifts, Conclusions The operations staffing of the research reactor satisfied TS requirement .2 Control and Performance of Exoeriments ,
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l Insoection Scoce (Insoection ProcedurejaQQ11 The inspector reviewed approved experiment records, reactor logs, experimonial data, Reactor Safeguards Committee (RSC) minutes and interviewed staf Observations and Findinas l
Experiments and changes to approved experiments had been reviewed and approved as required by T Review of the experiment data in the reactor log, interviews with staff,
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observation of experimental set-up and review of the RSC experiment approvals verified that experiments were constrained as required by the TS and experiment authorizat'on, and were installed, conducted, and removed es outlined in the experiment authorization and licensee's procedure I
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.2-The inspector observed selected aspects for an experiment on the production of
, Ir'". The irradiation process was well controlled with transfer shields and other handling apparatus being useo to keep exposures ALAR fanclusions Control and performance of experiments met TS and licensee requirements.
- - 01.3 Reactor Ooerations and Fuel Handlina
, Insoection Scone (Insoection Procedure 69001)
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The inspector interviewed staff, reviewed reactor operations and fuel logs, and periodic checkout, start-up and shutdown checklists. The inspector observed
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full power operations.
< Observations and Findinas Reactor operations were implemented in accordance with written procedures and TS. Information en operational status was recorded in log books and checklists as required by procedures and TS. Use of maintenance and repair logs complied with procedures and satisfied regulatory and licensee requirements. Shift turnover control and transfer of reactor status information was acceptabl Fuel movement and handling was infrequent. Data recorded for the one fuel movement since the last inspection was acceptable. Fuel movement, inspection, log keeping, and recording followed the facility's procedures and satisfied TS requirements.
4 Conclusions
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Reactor operations and shift turn-overs 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 identifie Operations Procedures and Documentation Insoection Scone (Insoection Procedure 69001)
The inspector reviewed operating procedures and updates, reactor operating reccrds and logs, and RSC minutes.
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3- Observations and Fbt.gs Written procedures required by the TS were available and used by the staf Implementation of and adherence to the procedures was acceptable. No procedure changes, other than those for new experiments, had been made since the last inspectio Records of power level, ope (ating periods, unusual events, calibration and !
maintenance procedures, installed experiments, and start-up and shutdown checks were being kep Conclusions Facility procedures satisfied TS requirements. Reactor operating records and j logs were, being maintained as required by T l a !
05 Operator Training and Qualification Program Insoection Scone (Insoection Procedure 69001) i l
The inspector reviewed requalification program records, NRC licenses, training records and interviewed staf . Observations and Findinas Currently licensed operators were successfully completing reactivity manipulations, and participating in the ongoing training as required by the NRC-approved requalification plan. Review of records showed that performance and competence' evaluations of the operators had been given as required. Past test rfJestions covered the material prescribed by the program and demonstrated technical depth. Required quarterly operation hours were being tracked. Biennial medical exams had been performed as require Conclusions The requalification program was being acceptably implemented. TS and NRC-approved requalification plan requirements were me Organization and Administration Insoection Scone (Insoection Procedure 69001)
The inspe. * - reviewed organization, staffing and administrative controls and interview inagement and staff.
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4 Observations and Findings A new Vice Provost for Research had been appointed since the last inspectio However this did not entail any functional change in the management organization or adrninistrative controls required by T Conclusions -
Organizational and administrative controls remain consistent with TS .mnd license requirements and commitment Quality Assurance in Operations
- Insoection Scone (Insoectionftocedure 69001)
The inspector reviewed RSC minutes annual reviews, audits, and interviewed l staf I
' Ooservations and Findinos The meeting schedule and membership satisfied TS requirements and the j
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committee's procedural rules. Review of the minutes confirmed that the RSC ;
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provided guidance, direction and oversight, and ensured suitable use of the reauor. The minutes provided a record of the safety oversight of reactor operation Tho . inspector reviewed the new experiment approval for the Irn : production and I the approvals for the removal of the thermal column lead shleiding and graphite blocks. The RSC approvals of these activities were detailed, met TS constraints, and implemented ALARA principle Conclusions The RSC performed its duties as required by license, TS, and administrative
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M1 Cor. duct of Maintenance M1.1 Surveillances and Limitino Conditions for Ooeration sDection Scoos (Insoaction Procedure 69001)
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d The inspector reviewed selected surveillance records, data sheets and records of tests, licensee procedures, reactor log-s, checklists, periodic reports, and
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interviewed staff.
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5 Observations and Findinas Daily and other periodic checks, tests, and verifications for TS required limiting conditions for operations (LCO) were completed as required. All surveillance and I.CO verifications were completed on schedule as required by TS and licensee procedures. All were within prescribed TS and procedure parameter The TS surveillance for periodic pool water analyses is to detect leaking of the sealed cobalt-60 sources stored in the reactor pool. Although the licensee is only required to measure cobalt-60, they review all energy peaks identified to evaluate contamination levels in the pool water. To enhance their program the licensee had ordered a new mixed gamma calibration source for liquid analyses and stated they were periodically going to perform an alpha / beta boil-down !
count on future pool water sample Concil sions l
The liceuee'c program for surveillance and LCO confirmations satisfied TS requirement M2 Maintenance and Material Condition of Facilities and Equipment M1.1 General Facility Maintenance and Reoair Insoection Scooe (Insoection Procedure 6900U
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The inspector reviewed maintenance and reactor loos, RSC minutes, repair records, and observed facility and equipment during an accompanied tou l
I Observations and Findinas Reactor maintenance was noted in a maintenance log and the reactor logbook as required by procedures. Routine / preventative maintenance was adequately i controlled and documented. Unscheduled maintenance was routinely evaluated
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by use of a checklist to verify that it did not constitute a change or if it did that it posed no unreviewed safety question and was approved under 50.59 criteri ;
c. Conclusiqas Maintenance logs, records, performance, and 50.59 reviews satisfied TS and procedure requirement M2.2 Reactor Pool
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6- Insoection Scone (Insoection Procedure 69001)
The inspector reviewed maintenance and reactor logs, RSC minutes, repair records, observed facility and equipment during an accompanied tours and met
- with university engineering, radiological, and reactor staff Observations and Findinas As reported to the NRC by the DIR, after an overnight cool-down of the pool water from 55'C to 35'C pool leaks increased in number and rato of loss. The leaks were controlled such that the water was channeled into the facility waste holding tanks. Additionally, the volume was well within the capacity of the make-up demineralizer resins resulting in no change in pool water level. The contracted repairs for the leaks were ongoing during the inspectio .
The university had their Facilities Development (FD) section evaluate the pool integrity and recommend corrective actions. Personnel involved included 3 professional Civil and Structural engineers, a Building Construction Specialist, project managers including the Boron / Neutron Capture Therapy experiment manager, the FD Acting Assistant Director, and pertinent reactor and radiation rc'ety staffs, in .. ceting with the inspector the licensee representatives outlined their evaluation of the pool and their strategy for repairing the present leaks and preventing future leaks. The reactor pool, consisting of high and regular
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densities reenforced concrete, was structurally sound. The leaks were normally at penetrations in the tank wall, such as water lines, electrical conduits, experimental beam tubes, concrete pour interfaces, etc. The waterproof pool lining, which was past its useful life expectancy, was bubbling and degrade Although they would continue to seal the leaks on the outside of the tank, to correct the problem the tank liner would be replaced. FD representatives were
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evaluating a number of options for lining the tank, from metal or rubber inner liners to various coatings to permanently seat and water proof the inner wal The FD representative stated that the NRC staff would be informed of the progress on this project.
, Conclusigna Since the volume of water is within the capacity of the reactor's make-up system and the leakage is controlled, TS requirements for pool water levels and
- management of liquid effluents were being me Licensee actions regarding refining the tank and sealing exterior poolleaks were acceptable.
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-7-M2.3 Secondarv Coolina Svstem Insoection Scope (Insoection Procedure 69001)
The inspector reviewed maintenance and reactor logs, RSC minutes, repair records, observed facility and equipment during an accompanied tours and met with university engineering, radiological, and reactor staff Observations and Findinas As previously reported to the NRC by the DIR, they obt erved that during recent high outside temperatures and longer full power runs the secondary cooling system was unable to keep the pool water temperature stable. This had caused them to run the secondary cooling system after hours to bring the pool temperatures down. During this period the pool water reached a peak temperature of 55*C, The WSU TS do not have a pool temperature limit for operations. Facilities similar to WSU who do have such limits have them to prevent degradation of the pool water demineralizer resins. The reactor staff contacted their resin's manufacturer and confirmed that temperatures up to 60'C would not damage the resins. The DIR stated that a procedural temperature limit would be imposed to prevent damage to the resin )
l In a meeting with the inspector the licensee representatives outlined their evaluation of the cooling system and their strategy for repair / replacement of the system. The cooling tower and heat exchanger are original and, due to aging, no longer meet their original heat transfer capacities. The FD representative stated that replacement of the cooling tower had been funded and that they wce going to clean the heat exchanger and evaluate its effectiveness. Based on the performance of the heat exchanger after cleaning, they would decide if a replacement was needed. The FD representative stated that the NRC staff would be informed of the progress on this projec Conclusions Licensee actions re0arding repair or replacement of cooling water system
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components and controlling the pool temperature were acceptabl . Enaineerina E1 Conduct of Engineering, Design Changes Insoection Scooe (Insoection Procedure 69001)
The inspector reviewed selected design change packages, associated procedures and drawings, logs, records, and RSC files. The inspector also interviewed staf . _
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8- Observations and Findinas No design changes had been made since the last inspection. Previous licensee design changes were reviewed, approved, implemented, testad, and controlled as required by TS, licensee procedures, and pertinent regulations. Adequate change procedures were in place, Conclusiens Design Aanges satisfied TS and regulatory requirement IV. Plant Support R1 Radiological Protection and Chemistry Controls R1.1 Radiation Prttaction Survevs Scone (Insoection Procedure 69001)
The inspector reviewed procedures, survey records, and interviewed staff, Observations and Findings Periodic surface contamination surveys were evaluated using liquid scintillation counters (LSC). The inspector verified that alpha contamination determined by counts in the low energy channel "a" of the LSC were less than licensee limits and normally less than background. The university office, who performed periodic contamination surveys outside reactor areas, stated that their results wtsre simila ConclusiQat Surveys were performed and documented as required by 10 CFR 20. TS and licensee requirements for alpha contamination were me R1.2 Personnel Dosimetrv i l Scone (Insoection Procedure 69001)
The inspector reviewed dosimetry records, licensee procedures, and interviewed I staf l
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In reviewing the staff's dosimetry records the inspector confirmed that the l shallow doses received, indicative of low energy gamma and beta exposures, were very low and routinely less than the minimum reportable by their National Voluntary Laboratory Accreditation Program - accredited vendor. Extremity doses, monitored using finger rings, of those staff who usually retrieved activated experimental material and package such were also well within regulatory limit I Conclusions Shallow and extremity doses were in conformance with licensee and 10 CFR 20 limit R2 Status of Radiation Protection and Control (RP&C) Facilities and Equipment Scoce (Insoection Procedure 69001)
The !nspector reviewed calibration of the liquid scintillation counters and -
interviewed staff.
l- Observations and Findinos The LSCs used by the licensee were computer controlled models with no recommended calibration other than the computer controlled daily start-up check / verification. The inspector verified by interviews with reactor staff that, j as with other new computer controlled LSC these checks along with the
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manufactures annual servicing of the unit satisfied calibration requirement This was confirmed through discussions with two manufacturer representative Inspection Follow up Item IFl 50-027/97-201-01 is closed.
l Conclusions RP&C equipment was being maintained according to industry and equipment manufacturer standards. LSC calibrations satisfied TS requirements.
I S1 Conduct of Security
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l Inroaction Scone (Insoection Procedures 69001 & 81401)
The inspector reviewed the NRC-approved security plan, toured the facility, i reviewed security test records, reports, and security related training records, and j interviewed reactor and university police staff, i
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10- Observations and Findinas The laboratory and reactor facility were individually secured with only authorized persons having uaescorted access to the reactor facility. University police provided security as required by the plan. Periodic checks and tests of the security system were performed as well as security screening of personnel imposed by the plan. Related key control activities also satisfied plan requirements. Fuel inventories had been performed as require Training is provided to both the Nuclear Research Center staff, which includes the reactor staff, and the university police. The 1997 training for the police was !
late, in discussion with the police representative, the inspector found that this )
was in part due to shift staffing and duty requirements. The police i representative stated that recent changes had been made to have specific
" train!ng days" for their officers. The licensee and university police representatives stated that they would coordinate future training to ensure it is on time. This failure constitutes a violation of minor significance and is being treated as a Non-Cited Violation, consistent with Section IV of the NRC Enforcement Polic I Conclusions Conduct of security activities satisfied the NRC-approved pla S2 Status of Security Facilities, Equipment, and, Procedures, insoection Scooe (Insoection Procedures 69001 & 81401)
The inspector reviewed the NRC-approved security plan, toured the facility, reviewed reports, and security related documents, and interviewed reactor staff.
~ Observations and Findinas The inspector verified that the security system was as described in the NRC
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approved plan. The system provided detection and assessment of unauthorized removal of special nuclear material from the facility. The inspector verified that the alarms, devices, and procedures were adequate to allow the university police to detect and respond to unauthorized activities. Response rosters and emergercy phone lists were current and posted, Conclusions
Security facilities, equipment, and, procedures satisfied plan requirements.
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-11-V. Management Meetings X1 Exit Meeting Summary The inspector presented the inspection results to members of licensee management at the conclusion of the inspection on September 10,1997. The licensee acknowledged the findings presente i
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PARTIAL LIST OF PERSONS CONTACTED LIGantat I D. Baker Vice Provost Academic Affairs J. Becker Acting Assist and Director, Facilities Development K. Bloom Building Constructor Specialist, Facilities Development B. Bunce Senior Reactor Operator S. Eckberg Assistant Director, Rad;ation Safety Office K. Fox Reactor Operator M. Miles Chairman, Reactor Safeguards Committee J. Neidiger Reactor Supervisor L. Porter Director, Radiation Safety Office G. Tripard Director, Nuclear Radiation Center INSPECTION PROCEDURE (IP) USED IP 69001: CLASS 11 NON-POWER REACTORS IP 81,J1: PLANS, PP.OCEDURES, AND REVIEWS ITEMS OPENED, CLOSED, AND DISCUSSED D&lled NONE Closed IFl 027-97-201-01 Licensee to check on liquid scintillation counter for a recommended manufacturer calibration
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NCV 027 98-201-01 Failure to provide annual training for University police staff as l required by the NRC approved Security Plan.
l PARTIAL LIST OF ANACHRONISMS USED l
l ALARA As Low As Reasonably Achievable l DIR Director, Nuclear Radiation Center l FD Facilities Development
! LCO Limiting Conditions for Operations RSC Reactor Safeguards Committee T Technical Specifications
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