ML13071A424
| ML13071A424 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 03/25/2013 |
| From: | Gregory Bowman Research and Test Reactors Branch B |
| To: | Marlone Davis State of RI, Atomic Energy Comm, Nuclear Science Ctr |
| Bassett, Craig | |
| References | |
| IR-13-201 | |
| Download: ML13071A424 (20) | |
See also: IR 05000193/2013201
Text
March 25, 2013
Mr. M. Jeff Davis, Interim Director
Rhode Island Nuclear Science Center
Rhode Island Atomic Energy Commission
16 Reactor Road
Narragansett, RI 02882-1165
SUBJECT: RHODE ISLAND ATOMIC ENERGY COMMISSION - NRC ROUTINE
INSPECTION REPORT NO. 50-193/2013-201
Dear Mr. Davis:
From February 25-28, 2013, the U.S. Nuclear Regulatory Commission (NRC or the
Commission) conducted an inspection at the Rhode Island Nuclear Science Center Reactor
facility (Inspection Report No. 50-193/2013-201). The enclosed report documents the
inspection results, which were discussed on February 28, 2013, with you and other members of
the staff.
This inspection was an examination of activities conducted under your license as they relate to
safety and compliance with the Commissions rules and regulations. Within these areas, the
inspection consisted of selective examinations of procedures and representative records,
interviews with personnel, and observations of activities in progress. Based on the results of
this inspection, no safety concerns or noncompliances with requirements 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 Document 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 Craig Bassett at
(301) 466-4495 or by electronic mail at Craig.Bassett@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. 50-193
License No. R-95
Enclosure: As stated
cc w/ encl: See next page
Rhode Island Atomic Energy Commission Docket No.: 50-193
cc:
Governor
222 State House Room 115
Providence, RI 02903
Dr. Stephen Mecca, Chairman
Rhode Island Atomic Energy Commission
Providence College
Department of Engineering-Physics Systems
River Avenue
Providence, RI 02859
Dr. Harry Knickle, Chairman
Nuclear and Radiation Safety Committee
University of Rhode Island
College of Engineering
112 Crawford Hall
Kingston, RI 02881
Dr. Andrew Kadak
253 Rumstick Road
Barrington, RI 02806
Dr. Bahram Nassersharif
Dean of Engineering
University of Rhode Island
102 Bliss Hall
Kingston, RI 20881
Dr. Peter Gromet
Department of Geological Sciences
Brown University
Providence, RI 02912
Dr. Alfred L. Allen
425 Laphan Farm Road
Pascoag, RI 02859
Supervising Radiological Health Specialist
Office of Occupational and Radiological Health
Rhode Island Department of Health
3 Capitol Hill, Room 206
Providence, RI 02908-5097
Test, Research, and Training Reactor Newsletter
University of Florida
202 Nuclear Sciences Center
Gainesville, FL 32611
March 25, 2013
Mr. M. Jeff Davis, Interim Director
Rhode Island Nuclear Science Center
Rhode Island Atomic Energy Commission
16 Reactor Road
Narragansett, RI 02882-1165
SUBJECT: RHODE ISLAND ATOMIC ENERGY COMMISSION - NRC ROUTINE
INSPECTION REPORT NO. 50-193/2013-201
Dear Mr. Davis:
From February 25-28, 2013, the U.S. Nuclear Regulatory Commission (NRC or the
Commission) conducted an inspection at the Rhode Island Nuclear Science Center Reactor
facility (Inspection Report No. 50-193/2013-201). The enclosed report documents the
inspection results, which were discussed on February 28, 2013, with you and other members of
the staff.
This inspection was an examination of activities conducted under your license as they relate to
safety and compliance with the Commissions rules and regulations. Within these areas, the
inspection consisted of selective examinations of procedures and representative records,
interviews with personnel, and observations of activities in progress. Based on the results of
this inspection, no safety concerns or noncompliances with requirements 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 Document 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 Craig Bassett at
(301) 466-4495 or by electronic mail at Craig.Bassett@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. 50-193
License No. R-95
Enclosure: As stated
cc w/ encl: See next page
DISTRIBUTION:
PUBLIC PROB r/f RidsNrrDprPrta Resource
RidsNrrDprPrtb Resource MNorris (MS T3B46M) MCompton (Ltr only O5-A4)
CBassett, NRR XYin, NRR GLappert, NRR
ACCESSION NO.: ML13071A424 * concurrence via e-mail TEMPLATE #: NRC-002
OFFICE PROB:RI * PRPB:LA PROB:BC
NAME CBassett GLappert GBowman
DATE 3/12/2013 3/21/2013 3/25/2013
OFFICIAL RECORD COPY
U. S. NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
Docket No: 50-193
License No: R-95
Report No: 50-193/2013-201
Licensee: Rhode Island Atomic Energy Commission
Facility: Rhode Island Nuclear Science Center Research Reactor
Location: Narragansett, Rhode Island
Dates: February 25-28, 2013
Inspector: Craig Bassett
Approved by: Gregory T. Bowman, Chief
Research and Test Reactors Oversight Branch
Division of Policy and Rulemaking
Office of Nuclear Reactor Regulation
EXECUTIVE SUMMARY
Rhode Island Atomic Energy Commission
Rhode Island Nuclear Science Center Reactor Facility
NRC Inspection Report No. 50-193/2013-201
The primary focus of this routine, announced inspection was the onsite review of selected
aspects of the Rhode Island Atomic Energy Commission (the licensees) Class I research
reactor facility safety program including: (1) organization and staffing, (2) review and audit and
design change function, (3) procedures, (4) radiation protection, (5) effluent and environmental
monitoring, and (6) transportation of radioactive material. The licensees program was
acceptably directed toward the protection of public health and safety and was in compliance
with U.S. Nuclear Regulatory Commission (NRC) requirements.
Organization and Staffing
- Organization and staffing remain in compliance with the requirements specified in the
facilitys Technical Specifications (TS).
Review and Audit and Design Change Functions
- The review and audit program was being conducted acceptably and completed by the
Nuclear and Radiation Safety Committee, as stipulated in TS 6.2.
- Changes made at the facility were being evaluated using the licensees Title 10 of the
Code of Federal Regulations (10 CFR) Section 50.59 safety evaluation process.
Procedures
- Written procedures were being maintained in accordance with TS requirements.
Radiation Protection
- 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 within the
NRCs regulatory limits.
- Radiation survey and monitoring equipment was generally being maintained and
calibrated as required.
- The radiation protection training program was acceptable and training was being
completed as required.
- The radiation protection and the as low as reasonably achievable (ALARA) programs
satisfied regulatory requirements.
-2-
Environmental Protection
- Effluent monitoring satisfied license and regulatory requirements and releases were
within the specified regulatory and TS limits.
- The environmental protection program satisfied NRC requirements.
Transportation
- The shipment of radioactive material under the reactor license was compliant with NRC
(10 CFR Parts 20 and 71) and Department of Transportation (49 CFR Parts 171-178)
regulations.
REPORT DETAILS
Summary of Facility Status
The Rhode Island Atomic Energy Commissions (the licensees) Rhode Island Nuclear Science
Center (RINSC) two megawatt research reactor continued to be operated in support of
education, research, and training. During the inspection, the reactor was operated at various
power levels for a student tour and to irradiate samples as part of its research mission.
1. Organization and Operations and Maintenance Activities
a. Inspection Scope (Inspection Procedure (IP) 69006)
The inspector reviewed the following regarding the licensees organization and
staffing to ensure that the requirements of Sections 6.1 and 6.2 of the RINSC
Technical Specifications (TS), Amendment No. 29, dated December 28, 2004, to
Facility License No. R-95, were being met:
- RINSC organizational structure and staffing
- Résumé of a newly hired health physicist
- Résumé of the recently appointed facility Assistant Director for Radiation
and Reactor Safety/Radiation Safety Officer
a. Observations and Findings
The inspector reviewed the facility organization and staffing. It was noted that
the organization had not changed since the previous inspection. It was noted
that, since the last inspection in the area of radiation protection, a change had
occurred in one of the key positions at the facility. The individual who had held
the position of Assistant Director for Radiation and Reactor Safety/Radiation
Safety Officer had retired. The inspector noted that a staff member, the
individual who was previously the facility health physicist, had been promoted to
fill the vacant position and a new individual was hired to fill the vacated health
physicist position. The inspector reviewed the background of the newly
promoted individual and determined that this individual had the work experience
and educational background required by TS 6.2.2. It was also noted that the new
health physicist appeared to have the appropriate background for that position.
The organizational structure and staffing at the facility appeared to be in
compliance with the TS.
b. Conclusion
The organization structure and staff functions were in accordance with TS
requirements.
2. Review and Audit and Design Change Functions
a. Inspection Scope (IP 69007)
The inspector reviewed the following to ensure that the requirements of TS
-2-
Section 6.0 and Title 10 of the Code of Federal Regulations (10 CFR) Section
50.59 were being implemented effectively:
- Nuclear and Radiation Safety Committee (NRSC) Charter, Revision
(Rev.) 1, approval dated April 25, 2011
- NRSC meeting minutes from July 2010 through the present
- 50.59 Screen/Review Forms for the following modifications or changes:
- Neutron Flux Monitor Non-Op System, review completed
January 11, 2012
- Installation of Digital Instrumentation and Control for the Reactor
Cooling System, review completed February 17, 2012
- RINSC Radiation Protection Annual Audit completed by the radiation
safety officer from February 7-12, 2012
- RINSC Radiation Protection Annual Audit completed by the radiation
safety officer from February 5-20, 2013
- RINSC Annual Report for the period from July 1, 2010, through June 30,
2011, submitted to the NRC on July 27, 2011
- RINSC Annual Report for the period from July 1, 2011, through June 30,
2012, submitted to the NRC on August 30, 2012
b. Observations and Findings
(1) Review and Audit Functions
The inspector reviewed the NRSC meeting minutes and associated
records from July 2010 through the present. The records showed that
meetings were being held and safety reviews and audits were conducted
by various members of the NRSC or other designated persons as
required and at the TS-required frequency. Topics of these reviews and
audits were consistent with TS requirements to provide guidance,
direction, and oversight for the facility, and acceptable use of the reactor.
No significant problems or deficiencies were found during the NRSCs
reviews and audits, but some areas for improvement were noted.
Corrective actions were taken as needed.
(2) Design Change Functions
Through interviews with licensee personnel, the inspector determined that
no changes had been initiated and/or completed at the facility since the
last NRC inspection. Even though no new changes had been proposed,
the inspector reviewed the 10 CFR 50.59 review process used at the
facility. New proposals for facility changes were required to be presented
to the NRSC for review and approval.
It was noted that none of the reviews that had been completed in the past
required that a full safety evaluation be conducted. It was also noted that
none of the changes required NRC approval prior to implementation.
-3-
c. Conclusion
The NRSC was meeting as required and reviewing the topics outlined in the TS.
Audits were being completed as required. Design changes were being
completed using the licensees modification review process.
3. Procedures
a. Inspection Scope (IP 69008)
The inspector reviewed the following to ensure that the requirements of TS 6.4
and 6.5 were being met:
- NRSC meeting minutes from July 2010 through the present
- RINSC Radiation Safety Office Standard Operating Procedures (SOP)
Manual, desk copy maintained by the radiation safety officer
- RINSC Radiation Safety Office SOP No. 420, Receipt of New Fuel,
Rev. 0, NRSC approval dated September 24, 2010
b. Observations and Findings
The inspector observed that the licensee maintained written procedures covering
the areas specified in TS 6.5, Operating Procedures. A systematic approach
was being used to update and reissue procedures. Newly revised procedures
and major changes were reviewed and approved by the NRSC in accordance
with TS 6.4, Review and Audit. The reviews and approvals were documented
in the minutes of the NRSC meetings. The inspector noted that no major
changes had been made since the previous inspection.
c. Conclusion
The licensee was maintaining and implementing written procedures in
accordance with TS requirements.
4. Radiation Protection
a. Inspection Scope (IP 69012)
The following documents were reviewed to determine compliance with
10 CFR Parts 19 and 20 and with TS 3.7.1 and 4.7 requirements regarding
radiation protection:
- Radiation safety training records
- Radiation safety training modules
- Copies of NRC Form 3, Notice to Employees, posted at the facility
- Quarterly dosimetry reports for facility personnel for 2010 through 2012
-4-
- Survey program summary data and the associated survey reports for
2012
- RINSC Radiation Protection Annual Audit completed by the radiation
safety officer from February 7-12, 2012
- RINSC Radiation Protection Annual Audit completed by the radiation
safety officer from February 5-20, 2013
- RINSC Radiation Safety Office SOP 101, Radiation Safety Training,
Rev. 0, NRSC approval dated March 23, 2000
- RINSC Radiation Safety Office SOP 201, External Monitoring, Rev. 0,
NRSC approval dated March 23, 2000
- RINSC Radiation Safety Office SOP 202, Bioassay, Rev. 0, NRSC
approval dated March 23, 2000
- RINSC Radiation Safety Office SOP 300, Routine Surveys, Rev. 0,
NRSC approval dated June 21, 2001
- RINSC Radiation Safety Office SOP 801, Instrument Calibration, NRSC
approval dated November 6, 2000
- RINSC Calibration Procedure CP-07, Main Floor Air Monitor Channel
Calibration, Rev. 0, NRSC approval dated July 2, 2003
- Instrumentation calibration of area monitors (for reactor bridge, fuel safe,
thermal column, heat exchanger area, and cleanup-demineralizer rooms)
for the past 2 years
- Survey meter calibration file documenting the calibration of various
portable survey instruments for the past 2 years
- RINSC Radiation Safety Guide, Rev. 0
- RINSC Annual Report for the period from July 1, 2010, through June 30,
2011, submitted to the NRC on July 27, 2011
- RINSC Annual Report for the period from July 1, 2011, through June 30,
2012, submitted to the NRC on August 30, 2012
b. Observations and Findings
(1) Surveys
The inspector reviewed selected weekly, monthly, and quarterly radiation
and contamination surveys. The surveys had been completed by health
physics staff members. No contamination had been detected in
concentrations above established action levels in the surveys reviewed.
Some areas/items were noted with slightly elevated radiation levels, but
no problems were found. Results of the surveys were acceptably
documented.
During the inspection the inspector accompanied a licensee
representative during completion of a routine weekly radiation and
contamination survey of the reactor bay. The techniques used during the
survey were adequate and the survey was conducted and documented in
accordance with the guidance specified by procedure. The inspector
conducted a radiation survey along with the licensee representative using
-5-
an NRC-supplied instrument. The radiation levels noted by the inspector
were comparable to those found by the licensee and no anomalies were
noted.
(2) Postings and Notices
Radiological signs were typically posted at the entrances to controlled
areas. Other postings also showed the industrial hygiene hazards that
were present in the areas. Caution signs, postings, and controls for
radiation areas were as required in 10 CFR Part 20, Subpart J. The
inspector noted that licensee personnel observed the signs and postings
and the precautions for access to radiation areas.
Copies of current notices to workers were posted in appropriate areas in
the facility. The copies of NRC Form 3, Notice to Employees, noted at
the facility were the latest issue and were posted in various areas of the
facility as required by 10 CFR Part 19.11. These locations included the
main bulletin board in the hallway by the radiation safety officers office,
the control room, and the lunch room.
(3) Dosimetry
The inspector determined that the licensee used pocket ion chambers
and thermoluminescent dosimeters (TLDs) for whole body monitoring of
x-ray, beta, gamma, and neutron radiation exposure. The licensee also
used TLD finger rings for extremity monitoring. The dosimetry was
supplied and processed by a National Voluntary Laboratory Accreditation
Program accredited vendor, Radiation Detection Company. An
examination of the TLD results indicating radiological exposures at the
facility for the past 3 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 reactor staff member for 2010 was 16 millirem (mr)
deep dose equivalent (DDE) and 127 mr shallow dose equivalent (SDE).
The highest annual extremity exposure for an individual for 2010 was
below the minimum measurable quantity for that period. The highest
annual whole body exposure received by a reactor staff member for 2011
was 115 mr DDE and 115 mr SDE. The highest annual extremity
exposure for an individual for 2011 was 270 mr SDE. The records also
showed that the highest annual whole body exposure received by a single
staff member for 2012 (through October) was 59 mr DDE and 85 mr SDE.
The highest annual extremity exposure for 2012 (through October) was
142 mr SDE.
Through direct observation the inspector determined that dosimetry was
acceptably used by facility personnel.
-6-
(4) Maintenance and Calibration of Radiation Monitoring Equipment
(a) Calibration of Portable Survey Meters
Examination of selected items of radiation monitoring equipment
indicated that the instruments had the acceptable up-to-date
calibration sticker attached. Review of the instrument calibration
records for various meters indicated the calibration of portable
survey meters was typically completed by licensee staff
personnel. However, some instruments were shipped to vendors
for repair and calibration as needed. The inspector verified that
the survey instruments were calibrated semiannually, which met
procedural requirements, and that calibration records were
maintained as required.
(b) Calibration of Area Radiation Monitors (ARMs) and Neutron
Detectors
The inspector also reviewed the calibration records of ARMs and
stack monitors. It was noted that these monitors were being
calibrated annually as required and were typically calibrated by
licensee staff personnel.
During the review of calibration records and the associated
procedures, it was noted that there were no procedures for
calibrating the ARMs and the neutron detectors in use at the
facility. A protocol had been developed for calibrating each type
of monitor/detector, but nothing had been formalized. The
protocols appeared to be suitable in that various ranges of the
instruments were checked using the appropriate sources.
However, no written procedures existed that had been reviewed
and approved by the NRSC. The inspector evaluated this issue
and determined that it represented a minor violation of TS 6.5.4.
The licensee was informed that the development of appropriate
calibration procedures for the ARMs and the neutron detectors
would be followed by the NRC as an inspector follow-up item (IFI)
and would be reviewed during subsequent inspections (IFI 50-
193/2013-201-01).
(c) Calibration Tracking
On October 25, 2011, the reactor was moved from the high power
section to the low power section of the pool. In this position the
reactor core is positioned adjacent to an area known as the dry
irradiation facility (DIF). With the core in this location, the DIF is a
high radiation area and the dose rates can reach as high as
30 rem/hr. At approximately 11:15 a.m., a student trainee
-7-
mistakenly entered the DIF to calibrate a radiation probe. It was
initially thought that the student had received a radiation exposure
of approximately 2.5 rem total effective dose equivalent during the
5 minutes he was in the area. The individuals dosimeter was
immediately sent off to be read and it was determined that he had
actually received a dose of only 115 millirem. Various corrective
actions were taken, including installing an ARM in the DIF in
January 2012. (For further information concerning this event,
refer to NRC Inspection Report No. 50-193/2011-204.)
During a tour of the reactor bay, the inspector observed the ARM
installed in the DIF and asked a licensee representative about the
calibration of the monitor. The inspector was informed that this
ARM was not on the list of monitors to be calibrated and had not
been calibrated since it was installed. The inspector made
licensee management aware of this issue. The licensee was
informed that completion of a proper calibration of the ARM in the
DIF and the inclusion of this monitor on the list of instruments to
be calibrated on an annual basis would be identified as an IFI and
would be reviewed during a subsequent NRC inspection (IFI 59-
193/2013-201-02).
(5) Radiation Protection Training
The inspector reviewed the training given to RINSC staff members, to
those who are not on staff but who are authorized to use the experimental
facilities of the reactor, and to students taking classes at the facility. The
training program was outlined online at the University of Rhode Island
website. It included initial radiation worker training for those new to the
facility. The training consisted of various modules including: facility
orientation, basic concepts and terms, radiobiology, basics of radiation
protection, radiation detection, personnel dosimetry, as low as reasonably
achievable (ALARA), practical radiation protection, and radioactive waste
management. Additional training was provided each person based upon
the position and/or duties of the individual. No refresher training was
typically offered, but additional training was given on an as needed
basis, such as following a radiological event or problem. The training
program was acceptable.
(6) Radiation Protection Program
The licensees radiation protection and ALARA programs were
established and described in the RINSC Radiation Safety Guide, Rev. 0,
and through associated health physics procedures that had been
reviewed and approved. The program contained instructions concerning
organization, training, monitoring, personnel responsibilities, handling
radioactive material, and maintaining doses ALARA. The program, as
-8-
established, appeared to be acceptable and was consistent with the
guidance in 10 CFR Part 20.
The licensee did not have a respiratory protection program or planned
special exposure program; neither program was required based on the
current level of activity at the facility.
(8) Facility Tours
The inspector toured the reactor bay; the basement area, including the
heat exchanger room and auxiliary areas; and selected support
laboratories with licensee representatives on various occasions. The
inspector noted that facility radioactive material storage areas were
properly posted. No unmarked radioactive material was noted. Radiation
areas and radioactive material storage areas were posted as required.
c. Conclusion
The inspector determined that the radiation protection and ALARA programs, as
implemented by the licensee, satisfied regulatory requirements because:
(1) periodic surveys were completed and documented acceptably to permit
evaluation of the radiation hazards present, (2) postings and signs met regulatory
requirements, (3) personnel dosimetry was being worn as required and recorded
doses were 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 being implemented as stipulated in
procedure.
5. Effluent and Environmental Monitoring
a. Inspection Scope (IP 69004)
The inspector reviewed the following to verify that the requirements of TS 4.7
were being met:
- Air monitor data sheet file to present
- Main and stack continuous air monitor file
- Dosimetry records for 2011 through 2013 to date
- Survey meter calibration file to present
- RINSC Calibration Procedures CP-06, Stack Monitor Channel
Calibration, Rev. 0, NRSC approval dated July 2, 2003
- RINSC Calibration Procedure CP-07, Main Floor Air Monitor Channel
Calibration, Rev. 0, NRSC approval dated July 2, 2003
- RINSC Radiation Protection Annual Audit completed by the radiation
safety officer from February 7-12, 2012
- RINSC Radiation Protection Annual Audit completed by the radiation
safety officer from February 5-20, 2013
-9-
- RINSC Annual Report for the period from July 1, 2010, through June 30,
2011, submitted to the NRC on July 27, 2011
- RINSC Annual Report for the period from July 1, 2011, through June 30,
2012, submitted to the NRC on August 30, 2012
b. Observations and Findings
On-site and off-site gamma radiation monitoring was accomplished using three
environmental monitoring station TLDs. Since the areas monitored had limited
public access, the licensee adjusted the readings by occupancy times which
resulted in dose rates at those locations less than a tenth of the regulatory limit.
The inspector determined that gaseous releases continued to be monitored as
required, calculated according to procedure, and acceptably documented in the
annual reports. The predominant environmental release from the facility was
argon-41 resulting from activated air entrained in the reactor pool water, present
in beam tubes, and used for cooling pneumatic transfer tubes. The airborne
concentrations of the gaseous releases were within the concentrations stipulated
in 10 CFR Part 20, Appendix B, Table 2. Also, the dose rate to the public, as a
result of the gaseous releases, was well below the dose constraint specified in
10 CFR 20.1101(d) of 10 millirem per year (mr/yr). This was acceptably
demonstrated by the licensee through computer code calculations. These
calculations indicated an effective dose equivalent to the public of 1.6 mr/yr for
the period from July 2010 to June 2011 and 2.6 mr/yr for the period from July
2011 to June 2012. It was noted that monitoring equipment was acceptably
maintained and calibrated. Records were current and acceptably maintained.
Observation of the facility by the inspector indicated no new potential release
paths.
A review of the liquid effluent releases from the facility to the sanitary sewer
indicated that a total of 7.719 microCuries was released during the period from
July 2010 to June 2011; no liquid effluent was released during the period from
July 2011 to June 2012. The great majority of this activity was in the form of
tritium. The releases were well within the monthly average concentration limits
established in 10 CFR 20, Appendix B, Table 3.
c. Conclusion
Effluent releases were within the specified regulatory and TS limits. The
environmental protection program satisfied NRC requirements.
6. Transportation
a. Inspection Scope (IP 86740)
The inspector reviewed the following documents to determine compliance with
NRCs standards for protection against radiation and packaging and
transportation of radioactive material (10 CFR Parts 20 and 71) and Department
- 10 -
of Transportation (DOT) transport regulations (49 CFR Parts 171-178):
- Licenses of shipment consignees
- Radioactive material (RAM) shipping notebook
- Training records for those designated as shippers
- RINSC Radiation Protection Annual Audit completed by the radiation
safety officer from February 7-12, 2012
- RINSC Radiation Protection Annual Audit completed by the radiation
safety officer from February 5-20, 2013
- RINSC RAM Shipping Procedure SHP-02, ATR-FFSC Fuel Cask
Receipt, Rev. 0, NRSC approval dated September 27, 2010
- RINSC Radiation Safety Office SOP No. 420, Receipt of New Fuel,
Rev. 0, NRSC approval dated September 24, 2010
- RINSC Radiation Safety Office SOP No. 501, Radioactive Waste
Packaging, Rev. 0, NRSC approval dated November 6, 2000
b. Observations and Findings
Through records review and discussions with licensee personnel, the inspector
determined that the licensee had shipped various types of radioactive material
during 2011 and 2012. The records indicated that the shipments had been
surveyed as required. All radioactive material shipment records reviewed by the
inspector had been completed in accordance with DOT and NRC regulations.
The inspector verified that the licensee maintained copies of shipment recipients
licenses to possess radioactive material as required and that the licenses were
verified to be current prior to initiating a shipment. The inspector also reviewed
the training of RINSC staff members responsible for shipping radioactive
material. The inspector verified that licensee personnel designated as shippers
had received the appropriate training covering the DOT, International Air
Transport Association, and International Civil Aviation Organization requirements
within the past 3 years.
c. Conclusion
The licensee shipments of radioactive material under the facilitys reactor license
were in accordance with NRC and DOT requirements.
7. Follow-up on Previously Identified Item
The inspector reviewed the actions taken in response to an NRC-identified
violation and an IFI.
b. Observation and Findings
(1) IFI-50-193/2012-201-01 - Follow-up on the successful completion of the
process of obtaining a Masters degree by the new Assistant Director for
Radiation and Reactor Safety.
- 11 -
During a previous inspection in October 2012, the inspector noted that the
previous Assistant Director for Radiation and Reactor Safety had retired
and another individual had been chosen to take his place. The inspector
reviewed the background of the newly promoted individual and
determined that this individual had the work experience required by TS 6.2.2. However, it was also noted that the person did not yet have a
Masters degree, as required by the TS. The licensee was informed that
the successful completion of this process and the obtaining of a Masters
degree by the new Assistant Director for Radiation and Reactor Safety
would be followed by the NRC as an IFI.
During this inspection the inspector reviewed this issue. It was noted that
the new Assistant Director for Radiation and Reactor Safety had
successfully prepared his thesis and defended it in October 2012. He
had subsequently received his Masters degree in December 2012. The
inspector reviewed a copy of the degree and verified that it had been
presented in December 2012. This issue is considered closed.
(2) IFI-50-193/2012-201-02 - Follow-up on the implementation of a facility
modification procedure, to include the 10 CFR 50.59 review process, by
the licensee.
During the NRC inspection in October 2012, the inspector reviewed the
process used by the licensee to conduct some of their 10 CFR 50.59
reviews. It was noted that it was a process that had been acceptable
prior to the current revision of 10 CFR 50.59, which was promulgated by
the NRC in 1999. The licensee indicated that they were in the process of
finalizing a procedure to be used for completing changes or modifications
to the facility or reactor systems that could have a significant effect on
reactor safety. The licensee was informed that the implementation of a
facility modification procedure, to include the 50.59 review process, will
be followed by the NRC as an IFI.
During this inspection the licensees actions with respect to developing a
procedure for completing changes and/or modifications at the facility were
reviewed. The inspector noted that a procedure had been drafted to
address the change and modification process. The NRSC was scheduled
to review and possibly approve the procedure on March 1, 2013. This
issue is considered closed.
c. Conclusion
Two IFIs were reviewed and closed.
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8. Exit Interview
The inspection scope and results were summarized on February 28, 2013, with
members of licensee management and staff. The inspector described the areas
inspected and discussed in detail the inspection findings. The licensee acknowledged
the results of the inspection and did not identify any information reviewed as proprietary.
PARTIAL LIST OF PERSONS CONTACTED
Licensee
M. Damato Health Physics Technician and Senior Reactor Operator
J. Davis Interim Director, Rhode Island Nuclear Science Center
S. Guarino Assistant Director for Radiation and Reactor Safety and Campus
Radiation Safety Officer
C. Hathaway Health Physicist
Z. Richards Reactor Supervisor and Senior Reactor Operator
INSPECTION PROCEDURES USED
IP 69004 Class 1 Research and Test Reactor Effluent and Environmental Monitoring
IP 69006 Class 1 Research and Test Reactors Organization and Operations and
Maintenance Activities
IP 69007 Class 1 Research and Test Reactors Review and Audit and Design Change
Functions
IP 69008 Class 1 Research and Test Reactors Procedures
IP 69012 Class 1 Research and Test Reactor Radiation Protection
IP 86740 Transportation
IP 92701 Follow-up on Previously Identified Items
ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
50-193/2013-201-01 IFI Follow-up on the licensees actions to develop appropriate
calibration procedures for the ARMs and the neutron
detectors used at the facility.
50-193/2013-201-02 IFI Follow-up on the licensees actions to complete a proper
calibration of the ARM in the DIF and include this monitor
on the list of instruments to be calibrated on an annual
basis.
Closed
50-193/2012-202-01 IFI Follow-up on the successful completion of the process of
obtaining a Masters degree by the new Assistant Director
for Radiation and Reactor Safety.
50-193/2011-202-02 IFI Follow-up on the implementation of a facility modification
procedure, to include the 10 CFR 50.59 review process, by
the licensee.
-2-
LIST OF ACRONYMS USED
ADAMS Agencywide Document Access Management System
ALARA As low as reasonably achievable
ARM Area radiation monitor
10 CFR Title 10 of the Code of Federal Regulations
DIF Dry irradiation facility
DOT Department of Transportation
IFI Inspector follow-up item
IP Inspection procedure
mr millirem
mr/yr millirem per year
NRC U.S. Nuclear Regulatory Commission
NRSC Nuclear and Radiation Safety Committee
RAM Radioactive material
Rev. Revision
RINSC Rhode Island Nuclear Science Center
SDE Shallow dose equivalent
SOP Standard Operating Procedure
TLD Thermoluminescent dosimeter
TS Technical Specification