ML13155A473
| ML13155A473 | |
| Person / Time | |
|---|---|
| Site: | U.S. Geological Survey |
| Issue date: | 06/05/2013 |
| From: | Gregory Bowman Research and Test Reactors Branch B |
| To: | Adrian B US Dept of Interior, Geological Survey (USGS) |
| Morlang, G | |
| References | |
| IR-13-201 | |
| Download: ML13155A473 (18) | |
See also: IR 05000274/2013201
Text
June 5, 2013
Betty Adrian, Reactor Administrator
Department of the Interior
U.S. Geological Survey
Box 25046., MS 975
Denver, CO 80225
SUBJECT:
UNITED STATES GEOLOGICAL SURVEY - NRC ROUTINE INSPECTION
REPORT NO. 50-274/2013-201
Dear Ms. Adrian:
From May 6-9, 2013, the U.S. Nuclear Regulatory Commission (NRC or the Commission)
conducted an inspection at your U.S. Geological Survey TRIGA reactor facility. The enclosed
report documents the inspection results, which were discussed on May 9, 2013, with you; Mr.
Timothy DeBey, Reactor Supervisor; and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and
compliance with the Commissions rules and regulations and with the conditions of your license.
The inspector reviewed selected procedures and records, observed activities, and interviewed
personnel. Based on the results of this inspection, no findings of significance were identified.
No response to this letter is required.
In accordance with Title 10 of the Code of Federal Regulations Section 2.390, Public
inspections, exemptions, and requests for withholding, a copy of this letter, its enclosure, and
your response (if any) will be available electronically for public inspection in the NRC Public
Document Room or from the NRCs document system (Agencywide Documents Access and
Management System (ADAMS)). ADAMS is accessible from the NRC Web site at
http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Should you have any questions concerning this inspection, please contact Mike Morlang at
(301) 415-4092 or by electronic mail at Gary.Morlang@nrc.gov.
Sincerely,
/RA/
Gregory T. Bowman, Chief
Research and Test Reactors Oversight Branch
Division of Policy and Rulemaking
Office of Nuclear Reactor Regulation
Docket No. 50-274
License No. R-113
Enclosure: NRC Inspection Report No. 50-274/2013-201
cc: See next page
U.S. Geological Survey
Docket No. 50-274
cc:
Environmental Services Manager
480 S. Allison Pkwy.
Lakewood, CO 80226
State of Colorado
Radiation Program
HMWM-RM-B2
4300 Cherry Creek Drive South
Denver, CO 80246
Mr. Timothy DeBey
Reactor Director
U.S. Geological Survey
Box 25046 - Mail Stop 424
Denver Federal Center
Denver, CO 80225
Test, Research, and Training
Reactor Newsletter
University of Florida
202 Nuclear Sciences Center
Gainesville, FL 32611
June 5, 2013
Betty Adrian, Reactor Administrator
Department of the Interior
U.S. Geological Survey
Box 25046., MS 975
Denver, CO 80225
SUBJECT:
UNITED STATES GEOLOGICAL SURVEY - NRC ROUTINE INSPECTION
REPORT NO. 50-274/2013-201
Dear Ms Adrian:
From May 6-9, 2013, the U.S. Nuclear Regulatory Commission (NRC or the Commission)
conducted an inspection at your U.S. Geological Survey TRIGA reactor facility. The enclosed
report documents the inspection results, which were discussed on May 9, 2013, with you; Mr.
Timothy DeBey, Reactor Supervisor; and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and
compliance with the Commissions rules and regulations and with the conditions of your license.
The inspector reviewed selected procedures and records, observed activities, and interviewed
personnel. Based on the results of this inspection, no findings of significance were identified.
No response to this letter is required.
In accordance with Title 10 of the Code of Federal Regulations Section 2.390, Public
inspections, exemptions, and requests for withholding, a copy of this letter, its enclosure, and
your response (if any) will be available electronically for public inspection in the NRC Public
Document Room or from the NRCs document system (Agencywide Documents Access and
Management System (ADAMS)). ADAMS is accessible from the NRC Web site at
http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Should you have any questions concerning this inspection, please contact Mike Morlang at
(301) 415-4092 or by electronic mail at Gary.Morlang@nrc.gov.
Sincerely,
/RA/
Gregory T. Bowman, Chief
Research and Test Reactors Oversight Branch
Division of Policy and Rulemaking
Office of Nuclear Reactor Regulation
Docket No. 50-274
License No. R-113
Enclosure: NRC Inspection Report No. 50-274/2013-201
cc: See next page
DISTRIBUTION:
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ACCESSION NO.: ML13155A473
TEMPLATE#: NRC-002
OFFICE
PROB:RI*
PROB:BC
NAME
GMorlang
GBowman
DATE
6/4/2013
6/5/2013
OFFICIAL RECORD COPY
U. S. NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
Docket No:
50-274
License No:
R-113
Report No:
50-274/2013-201
Licensee:
United States Geological Survey
Facility:
U.S. Geological Survey TRIGA Reactor
Location:
Building 15, Denver Federal Center
Denver Colorado
Dates:
May 6-9, 2013
Inspector:
Mike Morlang
Approved by:
Gregory T. Bowman, Chief
Research and Test Reactors Oversight Branch
Division of Policy and Rulemaking
Office of Nuclear Reactor Regulation
EXECUTIVE SUMMARY
United States Geological Survey
U. S. Geological Survey TRIGA Reactor
Report No. 50-274/2013-201
The primary focus of this routine, announced inspection was the on-site review of selected
aspects of the U.S. Geological Survey (the licensees) Class II research reactor safety program
including: (1) operator requalification; (2) health physics; (3) effluents and environmental
monitoring; (4) design changes; (5) committees, audits, and review; (6) emergency
preparedness; and (7) maintenance since the last U.S. Nuclear Regulatory Commission (NRC)
inspection of these areas. The licensees program was acceptably directed toward the
protection of public health and safety and in compliance with NRC requirements. No violations
or deviations were identified.
Operator Requalification
The requirements of the Operator Requalification Program were being met and the
program was being acceptably implemented.
Health Physics
Periodic surveys were completed and documented as required by procedure.
Postings and signs met regulatory requirements.
Personnel dosimetry was being worn as required and recorded doses were well within
the NRCs regulatory limits.
Radiation survey and monitoring equipment was being maintained and calibrated as
required.
The Radiation Protection and As Low As Reasonably Achievable Programs met
regulatory requirements.
Effluents and Environmental Monitoring
Effluent monitoring was in accordance with license and regulatory requirements and
releases were within the specified regulatory and Technical Specifications limits.
The environmental protection program met NRC requirements.
Design Changes
The licensees design change process had been updated to include a new procedure.
- 2 -
Committees, Audits, and Review
Audits and reviews were being conducted by the Reactor Operations Committee as
required by Technical Specifications.
The facility Emergency Plan was being reviewed by the Reactor Operations Committee
as required.
Emergency response equipment was being maintained and alarms were tested at the
required periodicity.
A letter of agreement had been executed with the new St. Anthonys Hospital.
Annual evacuation drills and biennial emergency drills were being conducted as required
by the emergency plan.
Emergency preparedness training for staff and first responders was being completed as
required.
Maintenance
A detailed facility maintenance plan existed which included detailed procedures.
REPORT DETAILS
Summary of Plant Status
The U.S. Geological Surveys (USGSs or the licensees) one megawatt TRIGA research reactor
was typically operated in support of USGS programs directed at improving methods and
techniques to enhance scientific knowledge about water and earth materials. During the
inspection the reactor was operated daily to support ongoing experimental and research work.
1.
Operator Requalification
a.
Inspection Scope (Inspection Procedure (IP) 69001)
To verify that the licensee was complying with the requirements of the NRC-
approved Operator Requalification Program and 10 CFR Part 55, the inspector
reviewed selected aspects of:
Operator competence evaluation and written examination records for
2011-2013
Physical examination records documented on NRC Form 396 records
Geological Survey TRIGA Reactor (GSTR) Reactor Operator
Requalification On the Job Training forms for the 2011-2012 training
cycle
Appendix 3-1 to Reactor Operations Manual (ROM) Section 3, entitled
U.S. Geological Survey TRIGA Reactor Operator Requalification
Program, dated September 1989 with the latest Rev. dated April 2010,
which included the GSTR Fitness for Duty Policy for Licensed Reactor
Operators, dated April 2010
Individual operator training records documented on GSTR Reactor
Operator Requalification On the Job Training forms for the periods from
January 2011-December 2012, and from January 2013-present
b.
Observations and Findings
There were four qualified senior reactor operators at the facility. The inspector
reviewed the various operators training records and confirmed they were being
maintained as required. The records showed that the operators were
knowledgeable of the appropriate subject material required by the program as
demonstrated by successful completion of annual written examinations.
Individual requalification records also showed that each operator demonstrated
operational competence by completing annual operating performance exams
administered by the Reactor Supervisor as required by the requalification
program. The inspector further confirmed that all the operators had completed
the required reactivity manipulations and the quarterly hours of operation
required by the program.
- 2 -
The inspector noted that the operators were also receiving biennial medical
examinations as required by 10 CFR Part 55, Subpart C.
c.
Conclusion
The requirements of the Operator Requalification Program were being met and
the program was being acceptably implemented. Medical examinations were
being completed biennially as required.
2.
Radiation Protection
a.
Inspection Scope (IP 69001)
The inspector reviewed selected aspects of the following to verify compliance
with 10 CFR Parts 19 and 20 and Technical Specifications Section F
requirements:
Radiological signs and posting in various areas of the facility
Training records for GSTR staff and various support personnel
Health Physics Quarterly Reports for 2011 through 2013 to date
USGS TRIGA Reactor Quarterly Reports for 2011 through 2013 to date
U.S. Geological Survey TRIGA Reactor Monthly Checklists for the past
2 years
GSTR Annual Audit of Radiation Exposures and Radioactive Material
Releases for 2011 and 2012
Routine periodic survey and monitoring records for the past 2 years
documented on radiological survey maps
Maintenance and calibration records of radiation monitoring equipment for
the past 2 years documented in the instrument calibration log
GSTR Radiation Protection Program as outlined in ROM, Chapter 8,
Radiation Protection Program, latest revision dated April 22, 2011,
including the following:
Section 8.1, Radiation Protection Policy
Section 8.2, Health Physics Training
Section 8.3, Radioactive Material Control
Section 8.4, Radiation Monitoring
Section 8.5, Instrumentation
Section 8.6, Records
Section 8.7, Emergency Response and Exposure Guidelines
Section 8.8, Declared Pregnant Woman Guidelines
Section 8.9, Planned Special Exposures
ROM GSTR Procedure No. 15, Pocket Dosimeter Drift Check
Procedure, latest revision dated October 2011 and last review dated
April 16, 2010
ROM GSTR Procedure No. 16, Pocket Dosimeter Calibration
Procedure, latest revision dated October 2011 and last review dated
November 9, 2009
- 3 -
ROM GSTR Procedure No. 20, Procedure for Radiation Instrument
Calibrations, latest revision dated October 2011, and last review dated
October 16, 2008
U.S. Geological Survey TRIGA Reactor Annual Report for the period from
January 1, 2011, through December 31, 2011, submitted to the NRC
January 23, 2012
U.S. Geological Survey TRIGA Reactor Annual Reports for the period
from January 1, 2012, through December 31, 2012, submitted to the NRC
January 24, 2013
The As Low As Reasonably Achievable (ALARA) Program outlined in
ROM Chapter 8, dated October 1994, and recent ALARA reviews
Memorandum from the Reactor Supervisor to the Director, U.S.
Geological Survey affirming USGS commitment to ALARA, dated
January 5, 2009
b.
Observations and Findings
(1)
Surveys
Selected start-up and monthly radiation and/or contamination surveys
were reviewed by the inspector. The surveys had been completed by
staff members as required. Any contamination detected in concentrations
above established action levels was noted and the area was
decontaminated. Results of the surveys were documented so that facility
personnel would be knowledgeable of the radiological conditions that
existed in the controlled areas of the facility.
(2)
Postings and Notices
Radiological signs were typically posted at the entrances to controlled
areas. Caution signs, postings, and controls for radiologically controlled
areas were as required in 10 CFR Part 20, Subpart J. Other postings at
the facility showed the industrial hygiene hazards that were present in the
areas as well.
Copies of NRC Form 3, Notice to Employees, noted at the facility were
the latest version, as required by 10 CFR 19.11, and were posted in
various areas throughout the facility. These locations included the
bulletin boards in the hallways by each entrance to the facility protected
area and in the hallway by the facility calibration range. Copies of other
notices to workers were posted in appropriate areas in the facility.
(3)
Dosimetry
The inspector determined that the licensee used thermoluminescent
dosimeters (TLDs) for whole body monitoring of beta and gamma
radiation exposure with an additional component to measure neutron
radiation. The licensee used TLD finger rings for extremity monitoring.
- 4 -
The dosimetry was supplied and processed by a National Voluntary
Laboratory Accreditation Program accredited vendor (Mirion
Technologies). An examination of the TLD results, indicating exposure to
radiation at the facility for the past 2 years, showed that the highest
occupational doses, as well as doses to the public, were within
10 CFR Part 20 limits. The records showed that the highest annual whole
body exposure received by a single individual for 2011 was 221 millirem
and for 2012 was 320 millirem deep dose equivalent. The highest annual
extremity exposure for 2011 was 222 millirem and for 2012 was 345
millirem shallow dose equivalent.
The inspector noted that one employee had received more than normal
dose to the extremities. This was the result of a stuck cap on two
different samples that took extra time to remove. The licensee had done
a detailed documentation of the higher than normal dose and included
that in the dosimetry records.
(4)
Radiation Monitoring Equipment
Examination of selected radiation monitoring equipment indicated that the
instruments had the acceptable up-to-date calibration sticker attached.
The instrument calibration records indicated that calibration of portable
survey meters was typically completed by licensee staff personnel.
However, some instruments, including the neutron detection instruments,
were shipped to vendors for calibration. Calibration frequency met
procedural requirements and records were maintained as required. Area
radiation monitors and stack monitors were also being calibrated as
required.
(5)
Radiation Protection Program
The licensees Radiation Protection and ALARA Programs were
established and described in ROM Chapter 8 and through associated
GSTR procedures that had been reviewed and approved. The programs
contained instructions concerning organization, training, monitoring,
personnel responsibilities, audits, record keeping, and reports. The
ALARA Program provided guidance for keeping doses as low as
reasonably achievable and was consistent with the guidance in
The inspector also determined that the licensee had conducted an annual
review of the Radiation Protection Program for 2011 and 2012 in
accordance with 10 CFR 20.1101(c). This had been completed by the
Reactor Supervisor. In addition, annual audits of the ALARA Program
had been conducted by USGS Radiation Safety Committee.
The licensee did not require or have a respiratory protection program.
- 5 -
(6)
Radiation Protection Training
The inspector reviewed the radiation worker training given to staff
members, to those who are not on staff but who are authorized to use the
experimental facilities of the reactor, and to support personnel. Initial
radiation worker training was given to everyone before they started work
in the facility. Refresher training for reactor staff was given every 2 years;
everyone else received refresher training every 3 years. The inspector
noted that the last refresher training had been conducted on
February 1, 2013.
The initial and refresher training covered the topics specified in
10 CFR Part 19 as required. Training records showed that personnel
were acceptably trained in radiation protection practices. The training
program was acceptable.
c.
Conclusions
The inspector determined that the Radiation Protection and ALARA Programs, as
implemented by the licensee, were in accordance with regulatory requirements
because: (1) surveys were completed and documented acceptably to permit
evaluation of the radiation hazards present, (2) notices and postings met
regulatory requirements, (3) personnel dosimetry was being worn as required
and recorded doses were well within the NRCs regulatory limits, (4) radiation
survey and monitoring equipment was being maintained and calibrated as
required, and (5) the radiation protection training program was acceptable.
3.
Effluents and Environmental Monitoring
a.
Inspection Scope (IP 69001)
To determine that the licensee was complying with the requirements of 10 CFR
Part 20 and Technical Specifications Section B, the inspector reviewed selected
aspects of:
GSTR Argon-41 Record logbook
Environmental monitoring release records
GSTR Environmental TLD results logbook
GSTR H-3 in Reactor Water logbook tracking gross alpha and beta
activity in reactor water and cooling water
ROM GSTR Procedure No. 17, Procedure for Determining Argon-41
Release, latest revision dated October 2011 and last review dated May
15, 2009
ROM GSTR Procedure No. 20, Procedure for Radiation Instrument
Calibrations, latest revision dated October 2011 and last review dated
October 16, 2008
- 6 -
ROM GSTR Procedure No. 22, Procedure for Analysis of Stack Gas
Radionuclides, latest revision dated October 2011 and last review dated
May 15, 2009
Calibration records for the Ar-41 monitor (stack), area monitors, and the
continuous air monitor for the past 2 years
U.S. Geological Survey TRIGA Reactor Annual Report for the period from
January 1, 2011, through December 31, 2011, submitted to the NRC
January 23, 2012
U.S. Geological Survey TRIGA Reactor Annual Reports for the period
from January 1, 2012, through December 31, 2012, submitted to the NRC
January 24, 2013
b.
Observations and Findings
On-site and off-site gamma radiation monitoring was completed using the reactor
facility stack effluent monitor, various environmental monitoring TLDs, and area
monitors in accordance with the applicable procedures. Data indicated that there
were no measurable doses above any regulatory limits. Biennial environmental
soil and water samples were taken and analyzed. No reactor-produced isotopes
were identified in the samples.
The inspector determined that gaseous releases continued to be monitored and
calculated as required, were acceptably documented, and were within the annual
dose constraint of 10 millirem stipulated in 10 CFR 20.1101(d), 10 CFR Part 20,
Appendix B concentrations, and Technical Specification limits. Environmental
Protection Agency COMPLY code calculations indicated that the facility was in
compliance with effluent emissions.
The program for the monitoring, storage, or transfer of radioactive liquid and
solids was consistent with applicable regulatory requirements. No liquid
discharges had been made during 2011 and 2012. Solid radioactive material
was monitored and released when below acceptable limits or was shipped to a
waste processing facility for disposal. The principles of ALARA were acceptably
implemented to minimize radioactive releases. Monitoring equipment was
acceptably maintained and calibrated. Records were current and acceptably
maintained.
c.
Conclusions
Effluent releases were within the specified regulatory and Technical Specification
limits. The environmental protection program was in accordance with NRC
requirements.
- 7 -
4.
Design Changes
a.
Inspection Scope (IP 69001)
In order to verify that the licensee had met the design change requirements of
Title 10 of the Code of Federal Regulations (10 CFR) Section 50.59, the
inspector reviewed selected aspects of:
Technical Specifications through Amendment 11, January 7, 2006
Facility configuration records
GSTR Experiment Review Checklist
Facility design change records for the past 2 years
Safety review records and audit reports for the past 2 years
Responses to the safety reviews and audit reports for the past 2 years
Reactor Operations Committee meeting minutes from May 2, 2011,
October 4, 2011, April 5, 2012, and October 29, 2012
Reactor Operations Committee charter, outlined in the U.S. Geological
Survey Manual, 308.44, Reactor Operations Committee, dated
February 5, 1999
ROM Section 3, Nuclear Center Organization, Rev. dated April 30, 2012
b.
Observations and Findings
The inspector determined that design changes at the GSTR were initiated by a
facility staff review followed by a Reactor Operations Committee review and
subsequent approval of the changes. The licensee had been following a protocol
for change reviews and as of May 1, 2013, had developed a procedure defining
the entire process. This new procedure had been approved by the Reactor
Operations Committee. The inspector determined that all staff members were
familiar with the new procedure and would follow it if a change to the facility or to
an experiment were proposed.
Two facility changes were proposed during 2011 and 2012, all of which followed
the design change protocol. From review of these changes, as well as through
interviews with licensee personnel, the inspector determined that an actual
written procedure stipulating the steps to be taken to complete a 10 CFR 50.59
design change evaluation were completed.
c.
Conclusion
The licensees design change procedure was being followed and design changes
were conducted in accordance with 10 CFR 50.59.
- 8 -
5.
Committees, Audits, and Reviews
a.
Inspection Scope (IP 69001)
In order to verify that the licensee had established and conducted reviews and
audits as required by Technical Specifications Section H.2, the inspector
reviewed selected aspects of:
Technical Specifications through Amendment 11, January 7, 2006
GSTR Experiment Review Checklist
Safety review records and audit reports for the past 2 years
Responses to the safety reviews and audit reports for the past 2 years
Reactor Operations Committee meeting minutes from May 2, 2011,
October 4, 2011, April 5, 2012, and October 29, 2012.
Reactor Operations Committee charter outlined in the U.S. Geological
Survey Manual, 308.44, Reactor Operations Committee, dated
February 5, 1999
ROM Section 3, Nuclear Center Organization, revision dated
April 30, 2012
b.
Observations and Findings
The Reactor Operations Committee was meeting semiannually as required and
the committee membership satisfied Technical Specifications Section H.2, the
Reactor Operations Committee charter, and ROM Section 3.8 requirements.
Review of the meeting minutes for 2011 and 2012 indicated that the committee
provided guidance, direction, and oversight for the reactor and ensured suitable
and safe reactor operations.
The Reactor Operations Committee minutes and audit records showed that
safety reviews and individual audits had been completed at the required
frequency for the functional areas specified by Technical Specifications Sections
H.2, H.5, and I.3. The inspector noted that audit topics included reactor
operations, maintenance and operations logs, facility procedures, the operator
requalification program, fuel movement, physical security plan and the radiation
protection program. The inspector reviewed the results of the audits that had
been completed. The inspector determined that the audit findings, and licensee
actions taken in response to the findings, were acceptable.
c.
Conclusion
Audits and reviews conducted by the Reactor Operations Committee were in
accordance with the requirements specified in Section H.2 of the Technical
Specifications and Section 3 of the ROM.
- 9 -
6.
a.
Inspection Scope (IP 69001)
To verify compliance with the facility Emergency Plan entitled, Emergency Plan
for the U.S. Geological Survey TRIGA Reactor Facility, dated February 2005,
the inspector reviewed selected aspects of:
Training records for the past 2 years
Emergency drills and critiques for 2012 and 2013
GSTR Emergency Call List, last updated November 2012
Offsite support agreement with St. Anthonys Hospital
Emergency response facilities, supplies, equipment, and instrumentation
Emergency Plan implementing procedures contained in ROM Section 7,
Emergency Procedures, revision dated October 2012
U.S. Geological Survey TRIGA Reactor Annual Report for the period from
January 1, 2011, through December 31, 2011, submitted to the NRC
January 23, 2012
U.S. Geological Survey TRIGA Reactor Annual Reports for the period
from January 1, 2012, through December 31, 2012, submitted to the NRC
January 24, 2013
b.
Observations and Findings
The inspector verified that the Emergency Plan in use at the facility was the
same as the version most recently submitted to the NRC. The Emergency Plan
was audited and reviewed at least biennially (this was typically done annually) by
the Reactor Operations Committee as required by Technical Specifications
Section H.5. The implementing procedures were also reviewed and revised as
needed.
During observation of two emergency drills, the inspector determined that the
emergency equipment and portable detection instrumentation listed in the
emergency procedures were available and being maintained as required by the
Emergency Plan. The inspector also verified that a letter of agreement with
St. Anthonys Hospital was in place.
Through reviews of training records, observation of drills, and through interviews
with GSTR personnel, the inspector confirmed that emergency response training
was given as required by the Emergency Plan and that emergency responders
were knowledgeable of the proper actions to take in case of an emergency. It
was noted that annual evacuation drills and biennial emergency drills had been
conducted as required by the Emergency Plan. Each emergency drill provided a
practical and reasonable test of the participants knowledge and skills. Critiques
were held following the drills to discuss the strengths and weaknesses identified
during the exercise and to develop possible solutions for any problems identified.
- 10 -
c.
Conclusion
The inspector concluded that the emergency preparedness program was
conducted in accordance with the Emergency Plan because: (1) the Emergency
Plan and implementing procedures were being reviewed biennially as required,
(2) emergency response equipment was being maintained and alarms were
being tested as required, (3) a letter of agreement with St. Anthonys hospital
was being maintained, (4) drills were being conducted as required, and
(5) emergency preparedness training was being completed.
7.
Maintenance
a.
Inspection Scope (IP 69001)
To verify that the maintenance and surveillance programs were being conducted
as required in Technical Specifications Sections C through E, the inspector
reviewed selected aspects of:
GSTR Procedure No. 12, Procedure for Changing Demineralizer Resin,
dated April 1990 and last reviewed October 24, 2011
GSTR Procedure No. 13, Procedure for Use of Leak Testing Device,
dated April 1990 and last reviewed April 5, 2012
GSTR Procedure No. 19, Procedure for Test Equipment Calibration,
dated April 30, 1993 and last reviewed May 3, 2013
GSTR Procedure No. 21, Procedure for Measuring Control Rod Drop
Time, dated October 5, 1992 and last reviewed May 3, 2013
U.S. Geological Survey TRIGA Reactor Annual Report for the period from
January 1, 2011, through December 31, 2011, submitted to the NRC
January 23, 2012
U.S. Geological Survey TRIGA Reactor Annual Reports for the period
from January 1, 2012, through December 31, 2012, submitted to the NRC
January 24, 2013
b.
Observations and Findings
The inspector reviewed selected maintenance guidance documents and records,
including the maintenance log. This log was used effectively to document
detailed maintenance activities completed on specific items of equipment
including the primary and secondary pumps, exhaust fans, the cooling tower, and
the sump pump. The records reviewed indicated that routine and preventive
maintenance was controlled, conducted, and documented in the maintenance or
operations log consistent with licensee procedures. Verifications and operational
systems checks were performed to ensure system operability before an item of
equipment or a system was returned to service. Unscheduled maintenance or
repairs were reviewed to determine if they required a 10 CFR 50.59 evaluation.
- 11 -
c.
Conclusion
The licensees maintenance program was being implemented as required by
GSTR procedures
8.
Exit Meeting Summary
The inspector reviewed the inspection results with members of licensee management at
the conclusion of the inspection on May 9, 2013. The licensee acknowledged the
findings presented and did not identify as proprietary any of the material provided to or
reviewed by the inspector during the inspection.
PARTIAL LIST OF PERSONS CONTACTED
Licensee Personnel
B. Adrian
Reactor Administrator
A. Buehrle
Senior Reactor Operator
T. DeBey
Manager, GSTR and Reactor Supervisor
C. Farwell
Senior Reactor Operator
B. Roy
Senior Reactor Operator
Other Personnel
S. Mahan
Reactor Oversight Committee Member
K. Schneider
West Metro Fire Department Battalion Chief
INSPECTION PROCEDURE (IP) USED
Class II Research and Test Reactors
ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
None
Closed
None
PARTIAL LIST OF ACRONYMS USED
10 CFR
Title 10 of the Code of Federal Regulations
As Low As Reasonably Achievable
GSTR
Geological Survey TRIGA Reactor
IP
Inspection Procedure
No.
Number
NRC
U.S. Nuclear Regulatory Commission
ROM
Reactor Operations Manual
Thermoluminescent Dosimeter
United States Geological Survey