IR 05000274/1999201
| ML20210S412 | |
| Person / Time | |
|---|---|
| Site: | U.S. Geological Survey |
| Issue date: | 08/16/1999 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20210S410 | List: |
| References | |
| 50-274-99-201, NUDOCS 9908180098 | |
| Download: ML20210S412 (13) | |
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U. S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF NUCLEAR REACTOR REGULATION Docket No:
50-274 License No:
R-113 j
l Report No:
50-274/99-201 l
Licensee:
. U.S. Geological Survey l
Facility:
U.S. Geological Survey TRIGA Reactor i
i Location:
Geological Survey TRIGA Reactor Facility I
Building 15, Federal Center, Denver Colorado Dates:
July 13-16.1999
inspector:
Stephen W. Holmes, Reactor inspector i
Approved by::
Ledyard B. Marsh, Chief Events Assessment, Generic Communications and
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Non-Power Reactors Branch Division of Regulatory improvement Programs Office of Nuclear Reactor Regulation 9908190098 990816 PDR ADOCK 05000274 G
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EXECUTIVE SUMMARY This routine, announced inspection consisted of the review of selected conditions and records since the last inspection, verification of corrective actions previously committed to by the (
licensee, and related discussions with licensee personnel. The inspection was conducted J
following the guidance of the NRC Inspection Manual.
ORGANIZATIONAL STRUCTURE AND FUNCTIONS Reactor operations staffing and organizational structure and functions satisfied technical specification (TS) requirements.
EXPERIMENTS Licensee control and performance of experiments met TS and regulatory requirements.
OPERATIONS Operational activities were consistent with applicable requirements.
FUEL HANDLING
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Fuel handling activities and documentation were as required by TS and facility procedures. No safety concerns were identified.
SAFEGUARDS The licensee was in comp!iance with the possession and use limits of the research reactor license, acceptably tracked burn-up and production of special nuclear material (SNM), and had effective control of licensed materials as required.
PROCEDURES Facility procedures and use satisfied TS requirements. Reactor operating records and logs were being maintained as required by TS.
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OPERATOR REQUALIFICATION The requalification program was being acceptably implemented. TS and NRC-approved requalification plan requirements were met.
REVIEW AND AUDIT The Reactor Operations Committee (ROC) performed its safety duties as required by TS and administrative criteria.
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SURVEILLANCE The licensee's program for surveillance and limiting conditions for operation (LCO)
confirmations satisfied TS requirements.
MAINTENANCE Maintenance logs, records, performance, and reviews satisfied TS and procedure requirerpents. Facility condition was well maintained for its intended function and use, i
DESIGN CONTROL Design change procedures were in place and implemented as required.
ENVIRONMENTAL PROTECTION Environmental monitoring satisfied the radiation protection program requirements.
RADIOACTIVE MATERIAL TRANSFER AND DISPOSAL Radioactive material was transferred and disposed of following facility procedures, TS, and regulatory requirements.
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Report Details Summary of Plant Status The reactor was being operated a few days per week at full power in support of U.S. Geological Survey programs.
1.
ORGA*MTIONAL STRUCTURE AND FUNCTIONS a.
Insoection Scone (Inspection Procedure 69001)
The insp3ctor reviewed selected aspects of; organia ation and staffing e
e qualifiertions
managet.sent responsibilities e
administratic9 controls
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Observations and Findinas Licensed staff consisted of the Reactor Supervisor (RS), reactor health physicist, and two Senior Reactor Operators (SROs). The reactor staff satisfied the training and experience required by the TS.
. Since the last inspection no functional changes in the management organization or administrative controls have been inade.
c.
Conclusions Reactor operations staffing, organizational structure, and functions satisfied TS requirements.
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EXPE_RIMENTS a
insoection Scooe (Insoection Procedure 69001)
The inspector reviewed selected aspects of; e
experimental program requirements e
procedures e
logs and records
.e, experimental administrative controls and precautions I
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Observ.tions and Findinos l
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i New experiments or major changes to experiments (Class ll) must be reviewed by the
committee prior to initiation while others (Class l) may be approved by the RS. Record i
reviews and interviews substantiated that experiment approvals satisfHpd license and TS
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requirements.
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2-Review of the experiment data in the reactor log and observations by the inspector indicated that experiments were constrained as required by the TS and experiment authorization, and were installed, performed, and removed as outlined in the experiment authorization and licensee's procedures.
c Conclusions Licensee control and performance of experiments met TS and regulatory requirements.
3.
OPERATIONS a.
Inspection Scooe (Insoection Procedure 69001)
The inspector reviewed selected aspects of:
operational logs and records e
e staffing for operations e
selected operational, startup, or shutdown activities b.
Observations and Findinos Reactor operations were carried out following written procedures and TS. Information on i
operational status of the facility was recorded in log books and checklists as required by
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procedures and TS. Use of maintenance and repair logs satisfied pertinent requirements.
Significant problems and events noted in the operations log were reported and quickly resolved as required by TS and administrative procedures.
The inspector verified that TS and procedure required items were logged and cross referenced with other logs and checklists as required, and that TS cperationallimits had not been exceeded. Start-up, steady state power operation, a shutdown, and several facility checks and tests were observed by the inspector with no problems noted.
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Operation logs and records confirmed that shift staffing met the minimum requirements for duty and on-call personnel.
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Conclusions Operational activities were consistent with applicable requirements.
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3-4.
FUEL HANDLING a.
Inspection Scone (Insoection PrM* dure 69001)
The inspector reviewed selected aspects of:
fuel handling procedures o
fuel handling equipment and instrumentation e
e fuel handling and examination records b.
Observations and Findinas Procedures for refueling. fuel shuffling, and TS required inspections /surveillances were thorough and detailed, ensuring controlled operations. Fuel movement, inspection, tog keeping, and data recording followed the facility's procedures. Data recorded for fuel movement was clear and cross referenced in fuel and operations logs. Radiological controls and procedures conformed to health physics ALARA principles. Log entries clearly identified, as required by procedure, the minimum two persons present when moving fuel. Observation by the inspector of movement of a C-ring element confirmed fuel movement and operations, and fuellog recording was performed as required.
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Conclusions Fuel handling activities and documentation were as required by TS and facility procedures. No safety concerns were identified.
SAFEGUARDS a,
insoection Scope (Insoection Procedure 85102)
The insoectnr reviewed selected aspects of:
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s nuclear material inventory and locations
'e accountability records and reports
. nuclear material accountability program e-
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Findinas and Observations The semiannualinventory of SNM was reviewed and verified. The material control and accountability program tracked locations and content of fuel under the research reactor license. Fuel bum-up-related measurements and calculations were performed on the total core inventory using megawatt-hours produced and industry standard factors. The possession and use of 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. Fuel inventory and movement records were cross referenced and matched.
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The facility representative located and the inspector verified two randoraly selected items listed on the SNM inventory.
The RS stated they were aware that, although tracking fuel bum-up and production on a total core basis was acceptable for operations, for shipping spent fuel, individual element I
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isotopic inventories would be required.
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Conclusions The licensee was in compliance with the possession and us; imits of the research reactor license, acceptably tracked burn-up and production of SNM, and had effective control of licensed materials as required.
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PROCEDURES a.
Inspection Scope (Inspection Procedure 69001)
The inspector reviewed selected aspects of:
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administrative controls J
records for changes and temporary changes I
e proceduralimplementation
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logs and records b
Observations and Findinos Written procedures required by the TS were available and used by the staff. The inspector observed procedure use during operations. Implementation of and adherence to the procedures was acceptable. Procedures were routinely updated as needed.
Review of Procedure H-19 verified that changes had been evaluated and approved by the RS or ROC as required.
Records of power level, operating periods, unusual events, calibration and maintenance procecures, installed experiments, and start-up and shut-down checks were being kept as required by the TS and procedures.
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Conclusions j
l Facility procedures and use satisfied TS requirements. Reactor operating records and logs were being maintained as required by TS.
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OPERATOR REQUALIFICATION a.
Inspection Scooe (Insoection Procedure 69001)
The inspector reviewed selected aspects of:
the Requalification Program e
o operator licenses e
operator training records e
operator physical examination records e.
operator examination records e
operator active duty status b.
Observations and Findinas All currently licensed SROs were successfully completing the emergency procedure and abnormal events training, reactivity manipulations, and participating in the ongoing training as required by the NRC-approved requalification plan Review of records indicated that operator performance and competence evaluations had been given as required. Past test questions covered the material prescribed by the program and demonstrated technical depth. Required quarterly operation hours, as SROs, were being tracked. Biennial'
medical exams had been performed as required.
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Training was provided to the reactor operators on maintenance operations and 10 CFR 50.59 design changes and evaluations.
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Conclusions j
The requalification program was being acceptably implemented. TS and NRC-approved requalification plan requirements were met.
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REVIEW AND AUDIT a.
!nspection Scooe (inspg ction Procedure 69001)
The inspector reviewed selected aspects of:
e safety review records e
audit records e
responses to safety reviews and audits b.
Observations and Findinas
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The ROC meeting schedule and membership satisfied TS requirements and the Committee's procedural rules. Review of the minutes indicated the ROC provided appropnate guidance, direction and oversight, and ensured suitable use of the reactor.
The miroies sesre clear and provided a record of the safety oversight of reactor
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-6-operations. Audits were direct and practical with follow-up on findings. Review and approval of emergency, security, and requalifications plans, procedures, experiments, and subsequent changes as well as year 2000 concems were being performed.
The ROC had reviewed and approved an upgrade and change to the continuous air monitor (CAM) electronics as required.
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Conclusions The ROC performed its safety duties as required by TS and administrative criteria.
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SURVEILLANCE a.
Inspection Scope (Inspection Procedure 69001)
The inspector reviewed selected asoects of:
surveillance and calibration procedures e
surveillance, calibration, and test data sheets and records e
b.
Observations and Findinas Daily and other periodic checks, tests, and verifications for TS required LCOs were completed as required. All surveillance and LC,0 verifications were completed on schedule as required by TS and in accordance with licensee procedures. A number of the surveillances and LCO verifications were performed at intervals more frequent than required by TS. All were within prescribed TS and procedure parameters and in close agreement with the previous surveillance results.
Some of the daily and periodic checks of equipment operability included recording system parameters such as temperature, pressure, and flow. All values checked by the inspector satisfied the limits / parameters listed in the procedure or checklist.
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Conclusions
k The I;censee's program for survemance and LCO confirmations satisfied TS requirements.
10. MAINTENANCE a.
Insoection Scooe (Insoection Procedure 69001)
The inspector reviewed selected aspects of:
maintenance procedures o
e equipment maintenance records
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Observations and Findinos j
Reactor maintenance was noted in a maintenance log and the reactor logbook as required by procedures. Maintenance was performed and documented consistent with the TS and licensee procedures. Maintenance procedures made staff aware that repair or maintenance beyond a certain point could become a facility change requiring an evaluation under 10 CFR 50.59.
. During a facility tour it was noted that control and reactor room equipment was operational. No missing or malfunctioning equipment was noted.
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Conclusions Maintenance logs, records, performance, and reviews satisfied TS and procedure requirements. Facility condition was well maintained for its intended function and use.
11. DFSIGN CONTROL a.
Inspection Scooe (Insoection Procedure 69001)
The inspector reviewed selected aspects of; e
facility design changes and records e
facility configuration b
Observations and Findinos Since the last inspection an upgrade and change was made to the CAM electronics. The
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10 CFR 50.59 change package included new updated procedures, the manufacture's manual for the upgrade instrument package, and the review and approval by the ROC.
The inspector confirmed that the operrition tests of the CAM varified that it met TS requirements and was operational.
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Conclusions The licensee's design change procedures were in place and were implemented as required.
i 12. ENVIRONMENTAL PROTECTION a.
Inspection Scooe (inscection Procedure 69001)
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The inspector reviewed selected aspects of:
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e the environmental monitoring program L
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Observations and Findinas j
The' environmental monitoring consists of direct radiation measurements at selected locations at the facility using thermoluminescent dosimeters (TLD) and biennial analyses
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of soil and water samples. Results in unrestricted areas were not statistically different from background readings, and environmental soil and water results were consistent with historical background averages.
The licensee stated that they were considering using more than one background TLD and placing them in more representative locations than present. This would be a reasonable enhancement to their monitoring program.
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. Conclusions Environmental monitoring satisfied the radiation protection program requirements.
13. PAROACTIVE MATERIAL TRANSFER AND DISPOSAL (
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Scope (Insoection Procedure 69001)
The inspector reviewed selected aspects of; L
e radioactive material transfer documentation
' shipping and disposal records b.
Observations and Findinos Production of radioactive waste at the facility was minimal. With one exception, transfers
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were recorded on applicable forms, and documentation kept on file as required.
Reactor waste is transferred to the byproduct licente and is dinposed of when enough waste has been collected for shipment. On June 16,1998, the resins were changed, as annotated in the reactor log, however, no transfer documentation could be found.
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Transfer to the byproduct license is normslly done on the radioisotope request and receipt forrr.. Since the resins were not irradiated as an experiment, no radioisotope request and receipt form was available, and since they are changed so infrequently, no formal written method of license transfer had been deemed necessary for resins.
The licensee stated that, after the resins were dried, they were physically moved from the L
' reactor to the byproduct license storage area and then added to its inventory. This was
confirmed by the inspector. The licensee stated that in the future, besides recording in j.
the reactor log the date of the resin change, the actual date of physical transfer to the byproduct license would also be recorded. This would acceptably documere. sud. an intamal transfer.
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Conclusions -
Radioactive material was transferred and disposed of following facility procedures TS, and regulatory requirements.
14. EXIT MEETING SUMMARY The inspector presented the inspection results to members of licensee management at the conclusion of the inspection on July 15,1999. The licensee acknowledged the findings presented and did not identify as propriety any of the material provided to or I
reviewed by the inspector during the inspection.
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PARTIAL LIST OF PERSONS CONTACTED Licensee
- T. DeBey, Reactor Supervisor
- P. Helfer, Senior Reactor Operator
- D. Liles, Reactor Health Physicist
- R. Perryman, Senior Reactor Operator
- Attended exit meeting INSPECTION PROCEDURES USED IP 69001:
CLASS 11 NON-POWER REACTORS IP 85102 MATERIAL CONTROL AND ACCOUNTING ITEMS OPENED. CLOSED. AND DISCUSSED Opened NONE Closed NONE PARTIAL LIST OF ACRONYMS USED CAM continuous air monitor LCO limiting conditions for operation NRC Nuclear Regulatory Commission ROC Reactor Operations Committee RS Reactor Supervisor SNM special nuclear material SRO Senior Reactor Operator TLD thermoluminescent dosimeters TS technical specification i
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