IR 05000020/2017202
| ML18116A492 | |
| Person / Time | |
|---|---|
| Site: | MIT Nuclear Research Reactor |
| Issue date: | 05/02/2018 |
| From: | Anthony Mendiola Research and Test Reactors Oversight Projects Branch |
| To: | Queirolo A Massachusetts Institute of Technology (MIT) |
| Eads J | |
| References | |
| IR 2017202 | |
| Download: ML18116A492 (16) | |
Text
May 2, 2018
SUBJECT:
MASSACHUSETTS INSTITUTE OF TECHNOLOGY - NUCLEAR REGULATORY COMMISSION ROUTINE INSPECTION REPORT NO. 50-020/2017-202
Dear Mr. Queirolo:
December 14, 2017
SUBJECT:
MASSACHUSETTS INSTITUTE OF TECHNOLOGY - NUCLEAR REGULATORY COMMISSION ROUTINE INSPECTION REPORT NO. 50-020/2017-202
Dear Mr. Queirolo:
From December 11-14, 2017, the U.S. Nuclear Regulatory Commission (NRC) conducted an inspection at your Massachusetts Institute of Technology Research Reactor. The enclosed report presents the results of that inspection, which were discussed on December 14, 2017, with 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 selective procedures and records, observed various 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, 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 Publicly Available Records component of 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 Mr. Johnny Eads at (301) 415-0136 or by electronic mail at Johnny.Eads@nrc.gov.
Sincerely,
/RA/
Anthony J. Mendiola, Chief Research and Test Reactors Oversight Branch Division of Licensing Projects Office of Nuclear Reactor Regulation
Docket No.50-020 License No. R-37
Enclosure:
As stated
cc: See next page
Massachusetts Institute of Technology Docket No.50-020
cc:
City Manager City Hall Cambridge, MA 02139
Department of Environmental Protection One Winter Street Boston, MA 02108
Mr. Jack Priest, Director Radiation Control Program Department of Public Health 529 Main Street Schrafft Center, Suite 1M2A Charlestown, MA 02129
Mr. John Giarrusso, Chief Planning and Preparedness Division Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399
Test, Research and Training Reactor Newsletter P.O. Box 118300 University of Florida Gainesville, FL 32611-8300
Ms. Sarah M. Don, Reactor Superintendent Massachusetts Institute of Technology Nuclear Reactor Laboratory Research Reactor 138 Albany Street, MS NW12-116B Cambridge, MA 02139
ML18116A492 *concurred via e-mail NRC-002 OFFICE NRR/DLP/PROB*
NRR/DLP/PROB/LA*
NRR/DLP/PROB/BC NAME JEads NParker AMendiola DATE 4/28/2018 4/27/2018 5/2/2018
Enclosure U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION
Docket No.50-020
License No.
R-37
Report No.
50-020/2017-202
Licensee:
Massachusetts Institute of Technology
Facility:
Nuclear Reactor Laboratory
Location:
Cambridge, Massachusetts
Dates:
December 11-14, 2017
Inspector:
Approved by:
Anthony J. Mendiola, Chief Research and Test Reactors Oversight Branch Division of Licensing Projects Office of Nuclear Reactor Regulation
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EXECUTIVE SUMMARY
Massachusetts Institute of Technology Nuclear Reactor Laboratory NRC Inspection Report No. 50-020/2017-202
The primary focus of this routine, announced inspection was the onsite review of selected aspects of the Massachusetts Institute of Technology (MIT or the licensees) Class I six megawatt research reactor safety program, including: (1) organization and staffing, (2) review and audit and design change functions, (3) radiation protection, (4) effluent and environmental monitoring, and (5) transportation of radioactive materials 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 was in compliance with NRC requirements.
Organization and Staffing
- Organizational structure and staffing were consistent with technical specification (TS)
requirements.
Review and Audit and Design Change Functions
- The MIT Reactor Safeguards Committee (RSC) was meeting as required and reviewing the topics outlined in the TS.
- Quarterly and annual audits of facility programs were generally conducted as required.
- The design change program satisfied NRC requirements.
Radiation Protection
- Surveys were completed and documented as required.
- Postings and notices met regulatory requirements.
- Staff personnel were wearing dosimetry as required and recorded doses were within the NRCs regulatory limits.
- Radiation survey and monitoring equipment was being maintained and calibrated as required.
- Radiation protection training was being conducted as required and was acceptable.
- The radiation protection and as low as reasonably achievable (ALARA) programs satisfied regulatory requirements.
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Effluent and Environmental Monitoring
- Effluent monitoring satisfied license and regulatory requirements and releases were within the specified regulatory and TS limits.
Transportation of Radioactive Materials
- The licensee continued to ship radioactive material in accordance with regulatory requirements.
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REPORT DETAILS
Summary of Facility Status
The MITs Nuclear Reactor Laboratory (NRL) 6-megawatt research reactor continued to be operated 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day, 7 days a week in support of educational experiments, research and service irradiations, and reactor operator training. The licensees programs were acceptably directed toward the protection of public health and safety, and were in compliance with NRC requirements.
1.
Organization and Staffing
a.
Inspection Scope (Inspection Procedure (IP) 69006)
The inspector reviewed the following regarding the MIT Reactor (designated as MITR-II) organization, staffing, and management responsibilities to ensure that the requirements of TS Section 7, Revision (Rev.) 6, dated November 1, 2010, were being met:
- Management responsibilities
Qualifications of facility radiation protection personnel
MIT NRL organization chart, dated December 7, 2017
Staffing requirements for operation of the research reactor
MIT Research Reactor, Nuclear Reactor Laboratory, Massachusetts Institute of Technology, Annual Report to U.S. Nuclear Regulatory Commission for the Period January 1, 2016 to December 31, 2016, submitted March 30, 2017
b.
Observations and Findings
The inspector noted that the Director of Reactor Operations was responsible for the safe operation of the facility and reported to the Director of the MIT NRL. The Director, of MIT NRL in turn reported to the President of the University through the Vice President for Research. The inspector also noted that the MITR-II Radiation Protection Officer (RPO) was responsible for radiation protection and advised the Director of Reactor Operations in all matters pertaining to radiation protection. This organization was consistent with that specified in the TS. The organizational structure and the responsibilities of the reactor staff and the radiation protection staff had not changed since the last inspection.
The radiation protection organization staffing levels at the facility remained consistent with those noted during the last inspection of this facility. The current reactor radiation protection organization consisted of the RPO, two Environment, Health, and Safety (EH&S) Officers, a project technician, three part-time EH&S technicians and an administrative assistant. The RPO, who also had the title of Deputy Director, EH&S, reported to the MIT Director of the EH&S Office. The RPO was also a member of the facility RSC. It was noted that the reactor radiation protection personnel provided assistance and job coverage for work done by Operations Group personnel.
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c.
Conclusion
The licensees organization and staffing were in compliance with the requirements specified in TS Section 7.
2.
Review and Audit and Design Change Functions
a.
Inspection Scope (IP 69007)
To verify compliance with TS Section 7.2.1, TS Section 7.2.2 and Title 10 of the Code of Federal Regulations (10 CFR) Section 50.59, the following documents were reviewed:
- Minutes of the MIT RSC, Meeting No. 109, held December 9, 2016
10 CFR Section 50.59 evaluations completed since the last inspection in December 2016
MIT Research Reactor, Nuclear Reactor Laboratory, Massachusetts Institute of Technology, Annual Report to U.S. Nuclear Regulatory Commission for the Period January 1, 2016 to December 31, 2016, submitted March 30, 2017
b.
Observations and Findings
(1)
Review and Audit Functions
The inspector reviewed the revised RSC charter and minutes of the MIT RSC and the minutes of selected special subcommittees for the past year to verify compliance with TS requirements. Members were appointed and designated in writing as stipulated in the TS. A quorum was present for the various meetings and the meeting minutes indicated that a thorough review of the appropriate topics was conducted. The RSC appeared to be appropriately focused on performing both routine reviews and promptly attending to non-routine emerging issues.
As part of its safety oversight program, the licensee and an outside contractor performed audits of the operations and the radiation protection programs. The inspector reviewed the report of recent internal audits and the report of the external audit. No significant problems were identified, although various findings and recommendations were noted. The licensees response to the findings and recommendations appeared to be appropriate.
(2)
Design Change Functions
The licensee has an established design change review function. It includes the screening and safety review of changes, tests, or experiments to determine if, pursuant to 10 CFR Section 50.59, a change required NRC approval prior to being implemented. The inspector found procedures in place to control the review process and evidence of adherence to the procedures.
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The inspector reviewed 10 CFR Section 50.59 evaluations completed since the last inspection in 2016. The licensees 10 CFR Section 50.59 reviews concluded that the changes could be implemented at the facility without prior NRC approval. In each case, the required safety review forms were completed and approved in accordance with facility procedures.
c.
Conclusion
The review and audit program was being conducted in compliance with the TS.
The design change evaluation program was being implemented in accordance with the TS requirements and NRC regulations.
3.
Radiation Protection
a.
Inspection Scope (IP 69012)
To ensure that the licensee was following the requirements of TS Section 7.3 and 10 CFR Part 19 and 10 CFR Part 20, the inspector reviewed selected aspects of the following:
- Quarterly Landauer dosimetry reports for fourth quarter 2016, and to date in 2017
Observations of facilities, equipment, operations, and postings during facility tours
Reportable Occurrence Reports, Unusual Occurrence Reports, and Operator Lessons Learned Reports related to radiation protection for the past year
MIT EH&S Reactor Radiation Protection Procedure 3001, Radiological Surveys, Rev. 5, dated March 2003
MIT Research Reactor, Nuclear Reactor Laboratory, Massachusetts Institute of Technology, Annual Report to U.S. Nuclear Regulatory Commission for the Period January 1, 2016 to December 31, 2016, submitted March 30, 2017
b.
Observations and Findings
(1)
Surveys
Daily, weekly, monthly, and other periodic contamination and radiation surveys, outlined in the licensees procedures, were generally completed in a timely manner by radiation protection staff members. Any contamination detected in concentrations above established action levels was noted and the area or item was generally decontaminated. Those that were not immediately decontaminated were located in areas that were established as contaminated areas where work was in progress.
Surveys were completed and documented acceptably to permit evaluation of the radiation hazards present.
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(2)
Postings and Notices
The inspector observed the copies of the notices to workers that were posted in various areas in the facility. The forms were posted on the main bulletin board, in the main hallways, and at the entrance to the reactor building. The inspector determined that radiological signs and, as noted above, survey maps were typically posted at the entrances to controlled areas. Other postings also showed the industrial hygiene hazards that were present in various areas as well.
(3)
Dosimetry Use and Results
Through direct observation the inspector determined that dosimetry was acceptably used by facility and contractor personnel. The inspector determined that the licensee used optically stimulated luminescent (OSL)
dosimetry for whole body monitoring and thermoluminescent dosimeters in the form of finger rings for extremity monitoring. The dosimetry was supplied and processed by a National Voluntary Laboratory Accreditation Program accredited vendor (Landauer).
An examination of the OSL results indicating radiological exposures at the facility for the past year showed that the highest occupational doses, as well as doses to the public, were within 10 CFR Part 20 limits. The records showed that approximately half of the facility personnel received occupational exposures of zero to only a few millirem above background.
(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 the calibration of certain portable survey meters was typically completed by licensee staff personnel. In the event that an instrument could not be calibrated by the licensee, it was taken out of service. Calibration frequency met procedural requirements and records were maintained as required.
Licensee records for calibration and tracking were comprehensive and well maintained.
(5)
Radiation Protection Training
The inspector reviewed the general employee radiation training given to MIT staff members, to those authorized to use the experimental facilities of the reactor, to students, and to visitors. It was noted that the training was available online through the EH&S website and reinforced with hands on, practical training. The training satisfied the requirements of 10 CFR Part 19 and the training program was acceptable. The inspector also noted that any specialized training, including Radiation Worker I and Radiation Worker II training, was provided on an individual basis by the RPO for those who needed it. No problems were noted. The inspector observed one of the refresher courses that are given annually so that current topics could be brought up and discussed by staff members. The
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refresher training given included topics such as the facility ALARA program results, safety culture, emergency response, and new equipment and systems.
(6)
ALARA Program
The MITR management ALARA efforts were well organized and continued to produce dose reduction results. ALARA goals were set and performance indicators were established. Each group in the MITR organization had an established ALARA goal for the year and the facility dose was tracked by group, as well as for each individual.
The facility is proactively taking action to reduce doses to workers through system modifications and radioactive material/waste shipments. The inspector notes that some additional dose will be received in the near term due to making modifications or preparing the material/waste shipments; however, in the long term, an overall reduction in dose should be realized.
The dose goal for 2016 was 2.0 person-rem. The cumulative dose for 2016 was less than the goal. The goal for 2017 is 2.0 person-rem for the facility.
(7)
Facility Tours
The inspector toured the reactor containment, the reactor control room, and selected support laboratories and maintenance areas with licensee representatives on various occasions. The inspector noted that facility radioactive material storage areas were properly posted. Radiation and high radiation areas were posted as required and properly controlled.
c.
Conclusion
The inspector determined that the Radiation Protection and ALARA Programs, as implemented by the licensee, satisfied regulatory requirements based on the following: (1) surveys were completed and documented acceptably to permit evaluation of the radiation hazards present, (2) postings 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 acceptable.
4.
Effluent and Environmental Monitoring
a.
Inspection Scope (IP 69004)
The inspector interviewed licensee representatives and reviewed the following to verify compliance with the requirements pertaining to discharges from the facility and environmental surveys pursuant to TS 7.7.1:
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- Facility records of measurements and analysis of effluent samples
MIT EH&S Reactor Radiation Protection Procedure 3010, Conduct of Environmental Radiological Surveys, Rev. 1, dated May 2000
MIT Research Reactor, Nuclear Reactor Laboratory, Massachusetts Institute of Technology, Annual Report to U.S. Nuclear Regulatory Commission for the Period January 1, 2016 to December 31, 2016, submitted March 30, 2017
b.
Observations and Findings
The inspector determined that releases continued to be monitored as required in accordance with TS 3.7.2 and were acceptably analyzed. These results were documented in the annual operating reports in accordance with TS 7.7.1.
Airborne concentrations of gaseous releases, principally Argon-41, were well within the concentrations stipulated in 10 CFR Part 20, Appendix B, Table 2, and TS limits.
The licensee reported the annual total activity of liquid released from the facility to the sanitary sewer. The total activity was reported in terms of tritium and all other activity less tritium. The total activity monitored and analyzed by the licensee for calendar year 2016 was 63 millicuries of tritium and 10 microcuries of all other isotopes. The concentration was below the 10 CFR 20.2003 limit with no credit for dilution due to other MIT waste streams. There were two solid waste shipments to a licensed, offsite disposal facility.
There were no investigative studies or human therapy exposures during the year to be reported pursuant to TS 7.7.1.9.
The licensee recorded data throughout the year from five radiation monitors mounted within a quarter mile of the reactor. The predominant source of exposure was noted to be Argon-41. All doses were well within all regulatory limits.
c.
Conclusion
Effluent release measurements and analyses and environmental monitor measurements demonstrated compliance with regulatory requirements.
5.
Transportation of Radioactive Materials
a.
Inspection Scope (IP 86740)
To verify compliance with regulatory requirements for shipping licensed radioactive material, the inspector reviewed the following:
- Various completed forms for 2017, including:
o Hazardous Goods Declaration forms o Bill of Lading forms o Surveys o MIT sample irradiation forms
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- 2015 DOT Shipping Audit, completed by a senior reactor operator
MIT Research Reactor, Nuclear Reactor Laboratory, Massachusetts Institute of Technology, Annual Report to U.S. Nuclear Regulatory Commission for the Period January 1, 2016 to December 31, 2016, submitted March 30, 2017
b.
Observations and Findings
Through records review and discussions with licensee personnel, the inspector determined that the licensee had shipped radioactive waste and other types of radioactive material since the previous inspection in this area. The records of these shipments indicated that the radioisotope types and quantities were calculated and dose rates measured as required. The radioactive material shipment records of these materials had been completed in accordance with Department of Transportation (DOT) and NRC regulations. It was noted that the Operations Group complete the majority of the shipments. The training of the staff members responsible for shipping the material was also reviewed. The inspector verified that the individual staff members designated as shippers had received training in accordance with the requirements of the DOT.
c.
Conclusion
The licensee continued to ship radioactive material in accordance with regulatory requirements.
6.
Exit Interview
The inspection scope and results were summarized on December 14, 2017, with members of licensee management. The inspector described the areas inspected and discussed the preliminary inspection findings. The licensee acknowledged the inspection findings and did not identify any information to be withheld from public disclosure.
Attachment PARTIAL LIST OF PERSONS CONTACTED
Licensee Personnel
J. Bernard
Senior Advisor T. Bork
Irradiation Service Coordinator S. Don
Superintendent of Reactor Operations E. Lau
Associate Director, Reactor Operations M. Mahowald Radiation Protection Program Officer, EH&S W. McCarthy Reactor Radiation Protection Officer and Deputy Director, Environment, Health, and Safety Office, MIT D. Moncton
Director, Nuclear Reactor Laboratory J. Quattrochi Radiation Protection Program Officer, EH&S P. Same
Reactor Supervisor S. Tucker
Quality Assurance Supervisor
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 69012 Class 1 Research and Test Reactor Radiation Protection IP 86740 Transportation of Radioactive Materials
ITEMS OPENED, CLOSED, AND DISCUSSED
Opened:
None
Closed:
None
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LIST OF ACRONYMS USED
10 CFR Title 10 of the Code of Federal Regulations ALARA As Low As Reasonably Achievable DOT
Department of Transportation EH&S Environmental Health and Safety IP
Inspection Procedure MIT
Massachusetts Institute of Technology MITR Massachusetts Institute of Technology Reactor NRC
U.S. Nuclear Regulatory Commission NRL
Nuclear Reactor Laboratory OSL
Optically Stimulated Luminescent Rev.
Revision RPO
Radiation Protection Officer RSC
Reactor Safeguards Committee TS
Technical Specification