IR 05000193/2017201
| ML17069A484 | |
| Person / Time | |
|---|---|
| Site: | Rhode Island Atomic Energy Commission |
| Issue date: | 03/22/2017 |
| From: | Anthony Mendiola Research and Test Reactors Oversight Branch |
| To: | Goodwin C State of RI, Atomic Energy Comm, State of RI, Atomic Energy Comm, Nuclear Science Ctr |
| Bassett C | |
| References | |
| IR 2017201 | |
| Download: ML17069A484 (20) | |
Text
March 22, 2017
SUBJECT:
RHODE ISLAND ATOMIC ENERGY COMMISSION - NUCLEAR REGULATORY COMMISSION ROUTINE INSPECTION REPORT NO. 50-193/2017-201
Dear Dr. Goodwin:
From February 27 - March 2, 2017, the U.S. Nuclear Regulatory Commission (NRC or the Commission) conducted an inspection at the Rhode Island Nuclear Science Center Reactor facility. The enclosed report documents the inspection results which were discussed on March 2, 2017, with you and members of your staff.
This inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with conditions of your license.
The inspector reviewed selected procedures and records, observed various activities, and interviewed personnel. Based on the results of this review, 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, 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). If 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/
Anthony J. Mendiola, 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: See next page
Rhode Island Atomic Energy Commission
cc:
Governor 222 State House Room 115 Providence, RI 02903
Howard Chun, Commissioner Cranston High School East 899 Park Avenue Cranston, RI 02910
Dr. Clinton Chichester, Chairman Rhode Island Atomic Energy Commission College of Pharmacy Pharmacy Building 7 Greenhouse Road Kingston, RI 02881
Dr. John Breen, Chairman Nuclear and Radiation Safety Committee Providence College Department of Chemistry and Biochemistry 1 Cunningham Square Providence, RI 02918
Dr. Nitin Padture, Commissioner School of Engineering, Brown University 184 Hope Street, Box D Barus & Holley Building, Room 608 Providence, RI 02912
Dr. Yana K. Reshetnyak, Commissioner Department of Physics University of Rhode Island East Hall, 2 Lippitt Road Kingston, RI 02881
Dr. Nancy E. Breen, Commissioner Marine and Natural Science Building 226 Roger Williams University One Old Ferry Road Bristol, RI 02809
Docket No. 50-193
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 P.O. Box 118300 University of Florida Gainesville, FL 32611
ML17069A484; *concurred via e-mail NRC-002 OFFICE NRR/DPR/PROB*
NRR/DPR/PROB*
NRR/DPR/PROB NAME CBassett NParker AMendiola DATE 3/17/17 3/16/17 3/22/17
U. S. NUCLEAR REGULATORY COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION
Docket No.
50-193
License No.
R-95
Report No.
50-193/2017-201
Licensee:
Rhode Island Atomic Energy Commission
Facility:
Rhode Island Nuclear Science Center Research Reactor
Location:
Narragansett, Rhode Island
Dates:
February 27 - March 2, 2017
Inspector:
Craig Bassett
Approved by:
Anthony J. Mendiola, 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 Research Reactor Facility NRC Inspection Report No. 50-193/2017-201
The primary focus of this routine, announced inspection was the onsite review of selected aspects of the Rhode Island Atomic Energy Commissions (the licensees) 2 Megawatt Class I research reactor safety program, including: (1) organization and staffing, (2) review and audit functions and design change control, (3) radiation safety, (4) environmental monitoring, (5) procedures, and (6) transportation of radioactive material since the last U.S. Nuclear Regulatory Commission (NRC) inspection in these areas. The licensees program was acceptably directed toward the protection of public health and safety and in compliance with NRC requirements.
Organization and Staffing
- Organizational structure, staffing, and staff responsibilities remain in compliance with the requirements specified in the facilitys Technical Specifications (TSs).
Review and Audit Functions and Design Change Control
- The review and audit program was being conducted acceptably and completed by the Nuclear and Radiation Safety Committee, as stipulated in TS Section 6.2.
- Changes made at the facility were being reviewed using guidance in the licensees Facility Modification Procedure, AP-03, and Title 10 of the Code of Federal Regulations (10 CFR) Section 50.59.
Radiation Safety
- 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 being maintained and calibrated as required.
- The radiation safety training program was acceptable and training was being completed as required.
- The radiation safety and the as low as reasonably achievable [ALARA] programs satisfied regulatory requirements.
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Environmental Monitoring
- Effluent monitoring satisfied license and regulatory requirements and releases were within the specified regulatory and TSs limits.
- The environmental protection program satisfied NRC requirements.
Procedures
- Written procedures were being reviewed, approved, and maintained in accordance with TS Section 6.4 requirements.
- Procedural compliance was acceptable.
Transportation of Radioactive Material
- The shipments of radioactive material made under the reactor license were in compliance with NRC and Department of Transportation regulations.
Enclosure REPORT DETAILS
Summary of Facility Status
The Rhode Island Atomic Energy Commissions (the licensees) Rhode Island Nuclear Science Center (RINSC) 2 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 training classes and to irradiate samples as part of its research mission.
1.
Organization and Staffing
a.
Inspection Scope (Inspection Procedure (IP) 69006)
The inspector reviewed the following regarding the licensees organizational structure, staffing, and staff responsibilities to ensure that the requirements of Section 6.1 of the RINSC Technical Specifications (TSs), dated December 19, 2016, (which is Appendix A to Facility License No. R-95, dated January 5, 2017),
were being met:
- RINSC organization and staffing
Reactor Logbook - Numbers 62 and 63
RINSC Annual Report for the period from July 1, 2014, through June 30, 2015, submitted to the U.S. Nuclear Regulatory Commission (NRC)
on August 28, 2014
RINSC Annual Report for the period from July 1, 2015, through June 30, 2016, submitted to the NRC on August 26, 2016
b.
Observations and Findings
The inspector reviewed the facility organization and staffing. It was noted that the organizational structure had not changed since the previous inspection. The facility organization consisted of the Facility Director, Assistant Director for Operations, Assistant Director for Radiation and Reactor Safety/Radiation Safety Officer (RSO), Reactor Supervisor, Principle Reactor Operator, Facility Engineer, and administrative support staff. The inspector noted that the person who had been the Reactor Health Physicist had left to take a job elsewhere. The facility had gone through the process of interviewing candidates to fill that open position.
The licensee indicated that a person had accepted the job offer and was expected to start about the middle of March (in about two weeks).
The Director continued to have responsibility for all of the administrative and technical programs of the facility as stipulated in TS Section 6.1.2.2. A licensed Senior Reactor Operator was assigned each shift with the responsibility for all operational activities during that shift. The inspector verified that shift staffing met TSs requirements. The RSO, also designated as the Assistant Director for Radiation and Reactor Safety as noted above, continued to be responsible for assuring that adequate radiation monitoring and control were in effect to prevent undue exposure of individuals to radiation as required by TS Section 6.1.2.4. It
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was noted that the Nuclear and Radiation Safety Committee (NRSC) consisted of at least the specified number of individuals with the appropriate backgrounds as required by the TSs. The organizational structure at the facility appeared to be in compliance with the TSs.
c.
Conclusion
The organizational structure, staffing, and staff responsibilities were in accordance with TSs requirements.
2.
Review and Audit Functions and Design Change Control
a.
Inspection Scope (IP 69007)
The inspector reviewed the following to ensure that the requirements of TS Section 6.2 and Title 10 of the Code of Federal Regulations (10 CFR) 20.1101, Radiation protection programs, and 10 CFR 50.59, Changes, tests and experiments, were being implemented effectively:
- NRSC Charter, Revision (Rev.) 4, approval dated November 19, 2015
NRSC meeting minutes for 2015 through the date of this inspection
Various 10 CFR 50.59 screen/review forms concerning modifications or changes at the facility maintained in the Facility Modifications Notebook
Radiation Safety Office Reports for 2015 and 2016 presented to the NRSC by the RSO
RINSC Operating Procedure, AP-03, Facility Modifications, Rev. 1
RINSC Annual Reports for the last two reporting periods
RINSC Radiation Safety Annual Audits performed by the RSO for calendar year (CY) 2015, completed during January 27 - 29, 2016, and for CY 2016, completed during January 24-26, 2017
b.
Observations and Findings
(1)
Review and Audit Functions
The inspector reviewed the NRSC meeting minutes and associated records for 2015 through the present. The records showed that meetings were being held more frequently than required in the TSs. Safety reviews and audits were conducted by various members of the NRSC or other designated persons as required. Topics of these reviews and audits were consistent with TSs requirements to provide guidance, direction, and oversight for the facility, and acceptable use of the reactor. It was also noted that the Radiation Safety Program was being audited annually as required by 10 CFR 20.1101.
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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 Control
Through interviews with licensee personnel, the inspector determined that various changes had been initiated and/or completed at the facility since the last NRC inspection. The inspector reviewed the 10 CFR 50.59 review process used at the facility. It was noted that the licensee used 10 CFR 50.59 screenings, reviews, and evaluations. The inspector noted that various screenings and reviews had been completed by the licensee.
The results indicated that no further actions were required.
c.
Conclusion
The NRSC was meeting as required and reviewing the topics outlined in the TSs.
Audits were being completed as required. Procedure and facility changes were being completed using the licensees change review process outlined in Facility Modification Procedure, AP-03.
3.
Radiation Safety
a.
Inspection Scope (IP 69012)
The following documents were reviewed to determine compliance with 10 CFR Part 19 and 10 CFR Part 20 and with TS Sections 3.7.1 and 4.7.1 requirements regarding radiation safety:
- Various RINSC Radiation Safety Procedures
Radiation Safety training modules and records
RINSC Annual Reports for past two reporting periods
RINSC Radiation Safety Annual Audit for the past 2 years
Copies of NRC Form 3, Notice to Employees, posted at the facility
Quarterly dosimetry reports for facility personnel from January 2015 through December 2016
RINSC Radiation Safety Office Radiation Safety Manual dated March 2016
Selected survey program summary data and the associated survey reports for 2016 through the date of this inspection
Selected calibration records of area radiation monitors (ARMs) for the past 2 years
Survey meter calibration files documenting the calibration of various portable survey instruments for the past 2 years
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b.
Observations and Findings
(1)
Surveys
The inspector reviewed selected weekly, monthly, quarterly, and semi-annual radiation and contamination surveys. The surveys, which had been completed by trained staff members, were completed in a timely manner. Some areas/items were noted during these surveys with slightly elevated radiation levels, but no problems were found. When areas were found to be contaminated, they were decontaminated promptly and resurveyed to confirm that the areas were radiologically clean. Results of the surveys were acceptably documented.
During the inspection, the inspector accompanied the facility RSO during completion of routine monthly radiation and contamination surveys of the lunch room and a laboratory where primary water samples were analyzed. The inspector noted that the techniques used by the RSO during the survey were adequate and the survey was conducted and documented as required. The inspector also conducted a radiation survey of these areas using an NRC meter. The radiation levels noted by the inspector were comparable to those found by the licensee RSO 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 and high radiation areas were generally as required in 10 CFR Part 20, Standards for Protection against Radiation, Subparts G and J. The inspector noted that licensee personnel observed the signs and postings and the precautions for access to the various controlled areas in the facility.
During a tour of the Reactor Bay Confinement and the basement auxiliary area, the inspector conducted a radiation survey of the areas and various items. Access to each of these areas was controlled by a locked door.
One area in the basement was noted to contain a piece of equipment with elevated radiation levels. Thus, the area immediately surrounding the equipment required additional posting. The licensee immediately corrected the problem by installing the proper posting.
The inspector verified that 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 prominently posted as required by 10 CFR 19.11, Posting of notices to workers. The locations where these Forms were posted included on the
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main bulletin board in the hallway by the Radiation Safety Office and in the control room.
(3)
Dosimetry Reports/Personnel Exposure
The inspector determined that the licensee used thermoluminescent dosimeters (TLDs) for staff and designated users 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. An examination of the TLD results indicating radiological exposures at the facility for the past 2 years showed that all of the occupational doses for facility personnel, as well as doses to the public, were within 10 CFR Part 20 limits. Through direct observation the inspector determined that dosimetry was acceptably used by facility personnel. It was noted that the licensee provided dosicards for monitoring the radiation exposure of tour groups and other visitors.
(4)
Maintenance and Calibration of Radiation Monitoring Equipment
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 completed by both licensee staff and contractor personnel depending on the type of calibration that was required. The licensee typically conducted electronic calibrations while the vendor conducted source range calibrations. The inspector verified that the survey instruments were calibrated annually as required and the appropriate calibration records were maintained.
The inspector reviewed the calibration and maintenance records of various ARMs. It was noted that the ARMs were being calibrated annually as required and were typically calibrated by licensee staff personnel. Records were current and acceptably maintained.
(5)
Radiation Safety Training
The inspector reviewed the licensees radiation safety training program. It was noted that training was given to RINSC staff members, to those who were not on staff but who were authorized to use the experimental facilities of the reactor (Authorized Users), to students taking classes at the facility, and to visitors. The training was typically given by the RSO at the facility. Initial radiation worker training was given for those new to the facility. Following initial training, refresher training was given on an annual basis.
The initial training consisted of various subjects including: basic concepts and terms, radiobiology, basics of radiation safety, radiation detection,
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personnel dosimetry, as low as reasonably achievable (ALARA), and radioactive waste management. Additional training was given to each person as appropriate based upon the position and/or duties of the individual.
The inspector reviewed the training given to staff members and other radiation workers who used facility resources. The staff refresher training consisted of various subjects including: basics of radiation safety, proper response to radiological accidents, proper use of personnel dosimetry, the ALARA principle, facility procedures and NRC regulations, and the basics of radioactive material shipping. The training appeared to be appropriate.
The inspector verified that initial training was being given to new arrivals and annual refresher training was being conducted as required for staff and non-staff members as well. The training program was acceptable.
(6)
Radiation Safety Program
The licensees Radiation Safety and ALARA programs were established and described in the RINSC Radiation Safety Office Radiation Safety Manual, dated March 2016, The University of Rhode Island Radioactive Material Safety Manual, latest revision dated February 2016, and through RINSC facility radiation safety procedures that had been reviewed and approved. The programs contained instructions concerning organization, training, monitoring, personnel responsibilities, handling radioactive material, and maintaining doses ALARA. The program, as established, appeared to be acceptable and satisfied regulatory requirements.
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.
(7)
Facility Tours
The inspector toured the facility including the reactor bay and Control Room; the basement area; 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.
c.
Conclusion
The inspector determined that the Radiation Safety and ALARA programs, as implemented by the licensee, satisfied regulatory requirements. Specifically, (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
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doses were within the NRCs regulatory limits; (4) radiation survey and monitoring equipment was being maintained and calibrated as required; and (5) the radiation safety training program was being implemented as stipulated in procedure.
4.
Environmental Monitoring
a.
Inspection Scope (IP 69004)
The inspector reviewed the following to verify that the requirements of TS Sections 3.7.2 and 4.7.2 were being met:
- Files containing air monitor data sheets
Main and stack continuous air monitor records
Environmental dosimetry records for 2015 through 2016
Selected RINSC calibration procedures, including CP-06 and CP-07
RINSC Radiation Safety Annual Audits for the past 2 years
RINSC Annual Report for the last two reporting periods
b.
Observations and Findings
(1)
Environmental Radiation Monitoring
Environmental radiation monitoring was accomplished using TLDs placed at three different monitoring stations. Since the areas monitored had limited public access, the licensee adjusted the readings by using an occupancy factor to approximate annual dose. After applying the occupancy factor, the results at those locations indicated dose rates less than the regulatory limit for members of the general public.
(2)
Gaseous Effluent Releases
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 of 10 millirem per year (mrem/yr) specified in 10 CFR 20.1101(d). This was acceptably demonstrated by the licensee through COMPLY code calculations. These calculations indicated an effective dose equivalent to the public of 1.3 mrem/yr for the RINSC fiscal year (FY) 2014-2015 and 1.2 mrem/yr for the FY 2015-2016. Additionally, observations of the interior and exterior of the facility by the inspector indicated no new
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potential release paths.
(3)
Liquid Effluent Releases
A review of the liquid effluent releases from the facility to the sanitary sewer indicated that proper methods were followed prior to the releases.
This included recirculation and sampling of the liquid, analyses of samples taken, and review and authorization of each batch. The releases were well within the monthly average concentration limits established in 10 CFR Part 20, Appendix B, Table 3.
(4)
Effluent Monitoring Equipment Calibration and Maintenance
The inspector reviewed the calibration and maintenance records of various stack monitors. It was noted that the stack monitors were being calibrated annually as required and were typically calibrated by licensee staff personnel. Records were current and acceptably maintained.
c.
Conclusion
Effluent releases were within the specified regulatory and TSs limits. The environmental protection program satisfied NRC requirements.
5.
Procedures
a.
Inspection Scope (IP 69008)
The inspector reviewed the following to ensure that the requirements of TS Section 6.4 were being met:
- Selected RINSC Operations procedures
NRSC meeting minutes from 2015 through the present
Various RINSC Radiation Safety Office Radiation Safety Procedures including RS-02, RS-03, RS-04, RS-07, RS-08, RS-13, and RS-21
b.
Observations and Findings
The inspector observed that the licensee maintained written procedures covering the areas specified in TS Section 6.4. A systematic approach was being used to update and reissue procedures. New procedures and major changes to existing procedures were required to be reviewed and approved by the NRSC. These reviews and approvals were typically documented in the minutes of the NRSC meetings.
The inspector reviewed selected Radiation Safety Office procedures. It was noted that minor and major changes to various procedures had been made since the previous inspection. Also, several new procedures had been developed.
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The inspector verified that the major procedure changes and the new procedures had been reviewed and approved by the NRSC as required. During the inspection it was noted that various procedures were still being written/revised dealing with calibration of survey instruments, effluent monitors, and analytical equipment.
The activities and operations observed by the inspector during this inspection were completed in accordance with the applicable procedures. These activities included reactor operation and conducting radiation and contamination surveys.
c.
Conclusion
The licensee was maintaining and implementing written procedures in accordance with TS Section 6.4 requirements. Procedural compliance was acceptable.
6.
Transportation of Radioactive Material
a.
Inspection Scope (IP 86740)
The inspector reviewed the following documents to determine compliance with NRC and Department of Transportation (DOT) regulations governing the transportation of radioactive material as specified in 10 CFR Part 20 and 10 CFR 71, Packaging and Transportation of Radioactive Material, and in 49 CFR Parts 171-178.
- Licenses of shipment recipients
Radioactive material shipping papers and related records
Training records for those designated as shippers
RINSC Radiation Safety Annual Audit for the past 2 years
Selected RINSC Radiation Safety Office procedures
b.
Observations and Findings
Through records review and discussions with licensee personnel, the inspector determined that the licensee had not shipped radioactive material (RAM) during 2015 but had made various exempt quantity transfers for training purposes in 2016. The records indicated that the shipments had been surveyed as required.
Although no radioactive material shipments had been made recently, the inspector noted that records of past shipments indicated that the licensee had completed them in accordance with DOT and NRC regulations.
During the inspection it was noted that preparations were being made to ship samples of Holmium-166 material to another university in New England.
However, the other university requested that no material with excessive radiation levels be shipped. The material was being held pending a reduction in the
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radiation levels. Therefore, the licensee was waiting until further radioactive decay occurred so that the material could be shipped as requested.
The inspector verified that the licensee was maintaining a copy on file of each shipment recipients license to possess radioactive material as required. 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 the only person currently designated as a shipper had received the appropriate training covering the DOT, International Air Transport Association, and International Civil Aviation Organization requirements within the past 3 years. The licensee plans to have the new Health Physicist and the Principle Reactor Operator attend a hazardous material transportation course this coming April.
c.
Conclusion
No radioactive material shipments had been completed recently. However, past licensee shipments of RAM under the facilitys reactor license were verified to have been completed in accordance with NRC and DOT requirements.
7.
Follow-up on Previously Identified Item
a.
Inspection Scope (IP 92701)
The inspector reviewed the licensees actions taken in response to an Inspector Follow-up Item (IFI) and an Unresolved Item (URI) which were identified during previous inspections.
b.
Observation and Findings
(1)
IFI 50-193/2015-201-01 - Follow-up on the licensees actions to complete the review and revision of the RINSC Radiation Safety Office procedures.
During an inspection in February 2015, it was noted that various RINSC Radiation Safety procedures were being reviewed by the RSO. These procedures were to be either revised or eliminated and replaced with new procedures as deemed necessary. The licensee was informed that completion of the review and revision of all necessary RINSC Radiation Safety procedures would be considered an Inspector Follow-up Item.
During this inspection it was noted that the majority of the Radiation Safety procedures had been revised/written and submitted to the NRSC. Some procedures dealing with calibration of survey meters, effluent monitors, and analytical equipment were still in the process of being rewritten/revised. The licensee anticipated that all the radiation safety procedures would be
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completed and submitted to the NRSC for review by the middle of 2017. The inspector noted that, although progress had been made in this area, this issue will not be closed until all the required Radiation Safety procedures are written/revised. This issue remains open.
(2)
URI 50-193/2016-203-01 - Review the results of the licensees 10 CFR 50.59 review of the upgrades to the ARMs in the Reactor Bay Confinement.
During an inspection in September 2016, it was noted that one recent Screening Form indicated that an upgrade to the Reactor Bay ARMs had screened out and therefore did not require a 10 CFR 50.59 review. This issue was discussed with the licensee. The licensee indicated that what they believed to be the current safety analysis report (SAR), specifically the low enriched uranium (LEU) SAR, did not mention the monitors. Because they were not mentioned in the LEU SAR, the issue had screened out. The NRC indicated that the SAR currently in effect for the facility was the original SAR. The LEU SAR was essentially an amendment to the original SAR and did not completely replace it.
The original SAR, as amended by the LEU SAR, did mention radiation monitors, and therefore a more complete 10 CFR 50.59 review was required. The licensee was informed that the issue of completing a 10 CFR 50.59 review of the upgrades to the reactor confinement ARMs would be considered an URI and would be reviewed during a future inspection or would be resolved during the pending license renewal.
The inspector discussed this issue with the licensee. It was agreed that a review/evaluation would be performed. As a result of the review, it was concluded that no TS changes were needed and none of the conditions of the eight criteria specified in 10 CFR 50.59 were met. This issue is considered closed.
c.
Conclusion
One IFI and a URI were reviewed. The IFI will remain open while the URI is considered closed.
8.
Exit Interview
The inspection scope and results were summarized on March 2, 2017, 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 as proprietary any material provided to or reviewed by the inspector during the inspection of these program areas.
PARTIAL LIST OF PERSONS CONTACTED
Licensee
J. Davis Assistant Director for Operations Director, Rhode Island Nuclear Science Center M. Marrapese Principal Reactor Operator P. Martin Reactor Supervisor S. Nam Assistant Director for Radiation and Reactor Safety/Radiation Safety Officer B. Sirr Facility Engineer
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
None
Closed
50-193/2016-203-01 URI Review the results of the licensees 10 CFR 50.59 review of the upgrades to the ARMs in the Reactor Bay Confinement.
Discussed
50-193/2015-201-01 IFI Follow-up on the licensees actions to complete the review and revision of the RINSC Radiation Safety Office procedures.
LIST OF ACRONYMS USED
10 CFR Title 10 of the Code of Federal Regulations ALARA As Low As Reasonably Achievable ARM Area Radiation Monitor CY Calendar Year DOT Department of Transportation FY Fiscal Year HP Health Physicist IFI Inspector Follow-up Item IP Inspection Procedure LEU Low Enriched Uranium Mrem/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 RSO
Radiation Safety Officer SAR
Safety Analysis Report TLD
Thermoluminescent Dosimeter TSs
Technical Specifications URI
Unresolved Item