IR 05000274/1998201
| ML20237A269 | |
| Person / Time | |
|---|---|
| Site: | U.S. Geological Survey |
| Issue date: | 08/11/1998 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20237A267 | List: |
| References | |
| 50-274-98-201, NUDOCS 9808130229 | |
| Download: ML20237A269 (13) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No:
50-274 License No:
R-113 Report No:
50-274/98-201 Licensee:
U.S. Geological Survey Facility:
U.S. Geological Survey TRIGA Reactor I
Location:
Geological Survey TRIGA Reactor Facility Building 15, Federal Center, Denver Colorado Dates:
July 20-23,1998
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Inspector:
Stephen W. Holmes, Reactor inspector l
l Approved by:
Seymour H. Weiss, Director Non-Power Reactors and Decommissioning
Project Directorate
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9808130229 980811 PDR ADOCK 05000274 G
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EXECUTIVE SUMMARY
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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 ths :icensee, and related discussions with licensee personnel. The inspection was conducted following the guidance of NRC Inspection Manual.
The reactor was being maintained and operated as required by the license and applicable regulations. Licensee corrective actions for two reported items were confirmed and found adequate.' One unresolved item was opened regarding calibration of pulse rate meters. No safety concerns were noted.
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Report Details l
Summary of Plant Status The reactor was being operated a few days per week at full power in support of USGS
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programs.
Organization and Administration i
a. Insoection Scoce (Insoection Procedure 40755)
The inspector reviewed organization, staffing and administ'/ative controls and interviewed management and staff.
b. Observations and Findinas Since the last inspection, no functional changes in the management i
organization or administrative controls have been made. Staffing was as required by TS.
c. Conclusions Organizational and administrative controls remain consistent with technical specification (TS) and license requirements and commitments.
Quality Assurance in Operations a. Insoection Scoce (Insoection Procedure 69001)
The inspector reviewed Reactor Operations Committee (ROC) minutes, annual reviews, audits, and interviewed the Reactor Health Physicist (RHP).
b. Observations and Findinas The ROC oversight i.icluded botfi operations and radiation safety. The meeting schedule and membership satisfied TS requirements and the Committee's procedural rules Review of the minutes showed the committee provided appropriate guidance, direction and oversight, and ensured use of the reactor in accordance with TS requirements. The minutes were clear, and provided a record of the safety oversight of reactor and radiation safety operations. Audits and reviews were direct and practical.
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c. Conclusions l
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The ROC performed its duties as required by license, TS, and administrative criteri __
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M8 Miscellaneous Maintenance issues a. Scoce (Insoection Procedure 69001)
The records concerning the year 2000 (Y2K) concerns were reviewed.
b. Observations and Findinas The current computer console upgrade included Y2K compliance in its specifications. The facility was covered under the USGS Y2K program. The staff stated those Y2K concerns such as counting and analysis programs were also being addressed to ensure facility would not be adversely affected.
c. Conclusions Y2K concerns were being addressed.
IV. Plant Sunoort R1 Radiological Protection and Chemistry Controls R1.1 Radiation Protection Postinas a. Scoce (Insoection Procedure 69001)
The inspector reviewed radiological signs and postings, routine radiation surveys, and observed the facility and equipment during accompanied tours.
b. Observations and Firidinas Postings, signs, and survey records at the reactor were acceptable for the hazards involved. The facility and radioactive material storage were secured and properly posted. No unmarked radioactive materials were evident. Current NRC Forms were posted in appropriate areas in the facility as were current notices to workers required by 10 CFR Part 19.
c. Conclusions Radiological postings satisfied regulatory requirements.
R1.2 Gaseous and Liauid Effluent Monitorina and Release a. Scoce finsoection Procedure 69001)
The inspector reviewed annual reports, release records, counting and analysis results, and interviewed staff.
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b. Observations and Findinos i
Routine gaseous releases consisted of noble gases and dosas were calculated using the EPA's COMPLY code and licensee procedures. Releases were documented within the Appendix B concentration limits and satisfied the annual dose constraint requirements of 20.1101(d). Stack effluent monitoring satisfied TS requirements.
Although, no liquid releases were made since the last inspection, review of procedures, equipment, and staff interviews confirmed that releases would be monitored and controlled within regulatory and licensee requirements.
l c. Conclusions Gaseous releases and liquid effluent controls satisfied license and regulatory requirements.
R1.3 Radiation Protection Survevs a. Scone finsoection Procedure 69001)
The inspector reviewed procedures, survey records, observed a survey of a pneumatic tube experiment, and interviewed staff.
b. Observations and Findinas l
Monthly and other periodic contamination and radiation surveys including pool water analyses were done by the RHP and reactor staffs as required by TS and licensee procedures. Results were evaluated and corrective actions taken and documented when readings /results exceeded set action levels.
Survey results verified that contamination ir' the facility was infrequent and that identified contamination and radiation levels were within regulatory and licensee limits.
c. Conclusions Surveys were performed and documented as required by 10 CFR Part 20. TS and licensee requirements were met.
R1.4 Personnel Dosimetrv l
a. Spone (Insoection Procedure 69001)
The inspector reviewed dosimetry records, licensee procedures, and interviewed staff.
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b. Observations and Findinas The licensee used a National Voluntary Laboratory Accreditation Program-accredited vendor to process personnel thermoluminescent dosimetry. Records were reviewed by the RHP quarterly. ALARA and declared pregnancy programs were in effect. An examination of records for the past year showed that all exposures were within NRC limits, with most less then one milisievert above background.
c. 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.
R1.5 Environmental Monitorina a. Scoce (Insoection Procedure 69001)
The inspector reviewed environmental records, licensee procedures, and interviewed staff.
b. Observations and Findinas The environmental monitoring consists of direct radiation measurements at selected locations near the reactor facility using thermoluminecient dosimeters and biennial analyses 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. With one exception all j
were done within the required time constraints. The Licensee had earlier identified and reported to the NRC that the last environmental soil and water samples were one and a half months late. The Licensee instituted a new tracking procedure to insure monitoring would be done within required time parameters. The inspector verified that the new tracking system was in place and functioning. It should also be noted that similar tracking systems were being used by several non-power facilitie., sith acceptable results.
c. Conclusions Environmental monitoring satisfied the radiation protection program requirements.
R1. Trainino a. Scooe (Insoection Procedure 69001)
The inspector reviewed training records, licensee procedures, observed an experimenter during a pneumatic tube experiment, and interviewed staff and a
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summer Co-Op student.
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b. Observations and Findinos l
HP training, sufficient for the work or visit, is required for personnel who enter restricted areas unless they are escorted by an individual who has had such training.
Review of records and interviews with staff confirmed that the operator requalification training program satisfied this requirement for the operations staff.
Experimental staffs were given individual academic and on-the -job training by their authorized users, and appropriate lectures by the RHP as needed. The inspector verified through an interview with a summer Co-Op that such training had been given, that the scope of the instruction satisfied regulatory and licensee requirements, and the individust had understood the training sufficiently to do their job safely. Observation of an experimenter during a pneumatic run also confirmed that appropriate HP training had been given and mastered to perform required operations safely.
c. Conclusions HP training satisfied regulatory and licensee requirements.
R2 Status of Radiation Protection and Control (RP&C) Facilities and Equipment a. Scooe (Insoection Procedure 69001)
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The inspector reviewed the licensee's inventory, calibration, periodic checks of portable radiation survey and laboratory instruments, and interviewed staff.
b. Observations and Findinas Calibrated instruments were available. Instruments used to perform radiation surveys were calibrated in-house and through outside vendors using radioactive l
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sources traceable to national standards. Calibration frequencies and procedures fcliowed manuf acture's or industry standards with one exception. Count-rate meters to include alpha meters were calibrated at one point on an intermediate range. Although these calibrations used sources traceable to national standards
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they did not appear to meet industry standards for calibration parameters, nor could the inspector determine if they met manufacture's recommendations. The licensee I
stated that they would secure the manufactures' calibration recommendations and follow either manufacture, or industry recommended standards for calibrations. This is an unresolved item (URI-50-274/98-201-01) and will be reviewed in a subsequent inspection.
The calibration of the GeLi multi-channel analyzer, liquid scintillation and gas flow proportional counters followed industry standards or the manufacturer's recommendations. Only those items that had geometrical standards for calibration were analyzed for quantitative results. Others were counted for qualitative results
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only. Allinstruments checked were in calibration. Calibration records were in order.
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c. Conclusions RP&C equipment was being maintained according to industry or equipment l
manufacturer standards. Calibrations satisfied TS requirements.
R3 RP&C Procedures and Documentation R3.1 Procedures a. Scone (Insoection Procedure 83743)
The Radiation Protection Program (RPP) documentation and various HP procedures were reviewed.
b. Observations and Findinos HP procedures were available for those tasks and items required by the TS, applicable requirements and facility directives. Changes were reviewed and i
approved as required. Procedures were clear, concise, and usable.
c. Conclusions HP procedures satisfied regulatory requirements and licensee commitments.
R3.1 Radiation Protection Frooram
a. Scoce (Insoection Procedure 83743)
The Radiation Protection Program (RPP) documentation and various HP procedures were reviewed.
b. Oi;servations and Findinos The RPP was delineated in Section 8. " Radiation Protection Program" of the facility l
operations manual. Documentation was detailed, comprehensive, and practical.
Reviews and audits were performed annually as required and assessed the technical performance, implementation, and effectiveness of the RPP.
c. Conclusions The RPP satisfied 10 CFR 20.1101 and 20.2102.
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R6. RP&C Organization and Administration a. Scooe (Insoection Procedure P'743)
RPP, TS, and various licensee documentation were reviewed and the staff interviewed.
b. Observations and Findinas The HP staff consisted cf the Reactor Health Physicist (RHP). The RHP was responsible for implementing the RPP to include, ALARA reviews, dosimetry, training, technical oversight, and day-to-day activities. The RHP's experience and training were acceptable for the scope of his duties and responsibilities. The RHP also covers the USGS byproduct license.
c. Conclusions HP staffing met TS, pertinent requirements, and facility commitments.
R8 Radioactive Material Transfer / Disposal a. Scooe (Insoection Procedure 86740)
The transfer documentation, and shipping and disposal records were reviewed.
b. Observations und Findinas Production of radioactive waste at the facility was minimal. All transfers were recorded on the applicable forms. Transfer documentation was kept on file as required.
Material transferred to authorized investigators on the USGS byproduct license was documented, to include exit surveys, on the experimental request forms as required
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by licensee procedures.
c. Conclusions
Radioactive material was transferred and disposed of following facility procedures,
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TS, and regulatory requirements.
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P1 Conduct of Emergency Preparedness Activities and Staff Training a. Insoection Scoce (Insoection Procedure 69001)
The inspector reviewed the emergency plan (EP) procedures, training and drill records for the reactor and interviewed licensee employees to determine compliance with regulatory, TS, and licensee requirements.
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b. Observations and Findinas The last two drill scenarios included an injury with contamination and a fire with hazardous material. The drills were held as required. The exercises were conducted according to, and fulfilled, the requirements stipulated in the EP. Key licensee emergency response personnel demonstrated that they could respond to emergencies as required. Offsite response by security, law enforcement, and other responders were acceptable for the scenarios involved. Involvement of offsite personnel was well coordinated.
Training records verified that acceptable training had been provided to in-house staff and outside responders.
c. Conclusions The licensee's emergency plan was effectively carried out as required. EP drills and training were acceptably being conducted.
P2 Status of EP Facilities, Equipment, and Resources a. Insoection Scoce (Insoection Procedure 69001)
The inspector reviewed inventory records, checked EP facilities, equipment and-supplies, and interviewed staff.
b. Observations and Findinas
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Equipment and supplies were as required by the EP and inventory records. Support facilities and communications were also as specified by EP requirement.
c. Conclusions EP facilities, equipment, and resources satisfied the approved plan requirements.
i P3 EP Procedures and Documentation a. Insoection Scoce (Insoection Procedure 69001)
The inspector reviewed the EP documents and implementing procedures and interviewed staff.
b. Observations and Findinas The plan and procedures were current, had been reviewed and approved as required and were readily available for use by response personnel. They acceptably addressed classification, notification, and protective actions required during an o
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emergency to protect the health and safety of the public. Implementing procedures were consistent with the EP requirements. Emergency phone list and on-call lists were also readily available and up-to-date.
c. Conclusions l
EP procedures and documentation were as required by the NRC approved EP and licensee requirements.
S1 Conduct of Security a.
Insoection Scoce (Insoection Procedure 69001)
I The inspector reviewed the NRC-approved security plan, toured the facility, reviewed security logs, reports, and security related drill documents, and interviewed reactor staff.
b. Observations and Findinas The laboratory and reactor facility were individually secured with only authorized l
persons having unescorted access to the reactor facility. Federal Protective
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Services (FPS) officers provided security as required by the plan. The Licensee had
earlier identified and reported to the NRC that a periodic test of the alarm system I
had been late. The Licensee instituted a new procedure to ensure testing would be done within required time parameters. The inspector verified that the new system was in place and that all subsequent reactor tests / verifications of the security systems had been performed as required. Communication between the staff and the FPS were acceptable.
c. Conclusions Conduct of security activities satisfied the NRC-epproved plan.
S2 Status of Security Facilities, Equipment, and, Procedures.
a. insoection Scooe (Insoection Procedure 69001)
The inspector reviewed the NRC-approved security plan, toured the facility, reviewed reports, and security related drill documents, and interviewed react : ;taff.
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l The inspector verified that the security system was as described in the NRC approved plan. The system provided detection and assessment of unauthorized removal of special nuclear material from the f acility. The inspector verified that the alarms, devices, and procedures were adequate to allow the FPS to detect and respond to unauthorized activities. Response rosters were current and posted as required.
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c. Conclusions Security facilities, equipment, and, procedures satisfied plan requirernents.
j V. Manaaement Meetinas i
X1 Exit Meeting Summary The inspector presented the inspection results to members of licensee l
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management at the conclusion of the inspection on July 23,1998. The licensee l
acknowledged the findings presented.
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s PARTIAL LIST OF PERSONS CONTACTED Licensee E. Brouwers Associate Regional Geologist T. DeBey Reactor Supervisor T.Fouch Regional Geologist P. Helfer Senior Reactor Operator B. Lewis Associate Regional Geologist for Reimbursable Programs D. Liles Reactor Health Physicist M. Neilson Co-Op student R. Perryman Senior Reactor Operator INSPECTION PROCEDURE USED 69001: CLASS ll NON POWER REACTORS ITEMS OPENED, CLOSED, AND DISCUSSED Ooened URI-50-274/9S-201-01 UPDATE COUNT-RATE AND ALPHA METER CALIBRATIONS Closed None PARTIAL LIST OF ACRONYMS USED HP Health Physics EP Emergency Plan NRC Nuclear Regulatory Commission RHP Reactor Health Physicist RPP Radiation Protection Program ROC Reactor Operations Committee TS Technical Specifications
.Y2K Year Two thousand
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