IR 05000020/2013203
| ML13352A339 | |
| Person / Time | |
|---|---|
| Site: | MIT Nuclear Research Reactor |
| Issue date: | 12/23/2013 |
| From: | Gregory Bowman Research and Test Reactors Branch B |
| To: | Newton T Massachusetts Institute of Technology (MIT) |
| Eads J, 319-219-9128 | |
| References | |
| IR-13-203 | |
| Download: ML13352A339 (17) | |
Text
December 23, 2013
SUBJECT:
MASSACHUSETTS INSTITUTE OF TECHNOLOGY - NRC ROUTINE INSPECTION REPORT NO. 50-020/2013-203
Dear Dr. Newton:
From November 18-21, 2013, the U.S. Nuclear Regulatory Commission (NRC or the Commission) conducted an inspection at the Massachusetts Institute of Technology Research Reactor facility (Inspection Report No. 50-020/2013-203). The enclosed report documents the inspection results, which were discussed on November 21, 2013, with you; Professor David Moncton, Director, Nuclear Reactor Laboratory; Mitch Galanek, Assistant Director, Environment, Health, and Safety Office and Campus Radiation Safety Officer; and various other members of the reactor facility staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspector reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, no safety concerns or noncompliance with requirements was identified. No response to this letter is required.
In accordance with Title 10 of the Code of Federal Regulations (10 CFR), Section 2.390, Public inspections, exemptions, and requests for withholding, a copy of this letter and its enclosure 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 Document Access and Management System (ADAMS)). ADAMS is accessible from the NRC Web site at (the Public Electronic Reading Room) http://www.nrc.gov/reading-rm/adams.html.
-2-Should you have any questions concerning this inspection, please contact Johnny Eads at (919) 219-9128 or by electronic mail at Johnny.Eads@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.: 50-020 License No.: R-37
Enclosures:
1. NRC Inspection Report No. 50-020/2013-203
cc w/encls: Please 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. Robert Gallagher, Acting Director Radiation Control Program Department of Public Health Schrafft Center, Suite 1M2A 529 Main Street Charlestown, MA 02129
Nuclear Preparedness Manager Massachusetts Emergency Management Agency 400 Worcester Road Framingham, MA 01702-5399
Test, Research, and Training Reactor Newsletter University of Florida 202 Nuclear Sciences Center Gainesville, FL 32611
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Should you have any questions concerning this inspection, please contact Johnny Eads at (919) 219-9128 or by electronic mail at Johnny.Eads@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.: 50-020 License No.: R-37
Enclosures:
1. NRC Inspection Report No. 50-020/2013-203
cc w/encls: Please see next page
DISTRIBUTION:
PUBLIC
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JEads, NRR
ACCESSION NO.: ML13352A339 * concurred via e-mail TEMPLATE #: NRC-002 OFFICE NRR/DPR/PROB*
NRR/DPR/PROB NAME JEads GBowman DATE 12/18/2013 12/23/2013 OFFICIAL RECORD COPY
Enclosure U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION
Docket No.: 50-020
License No.:
R-37
Report No.:
50-020/2013-203
Licensee:
Massachusetts Institute of Technology
Facility:
Nuclear Reactor Laboratory
Location:
Cambridge, Massachusetts
Dates:
November 18-21, 2013
Inspectors:
Approved by:
Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation
EXECUTIVE SUMMARY
Massachusetts Institute of Technology Nuclear Reactor Laboratory NRC Inspection Report No.: 50-020/2013-203
The primary focus of this routine, announced inspection was the onsite review of selected aspects of the Massachusetts Institute of Technology (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) 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 Massachusetts Institute of Technology Reactor Safeguards Committee was meeting as required and reviewing the topics outlined in the TS.
- Quarterly and annual audits of facility programs were conducted as required.
- The design change program satisfied NRC requirements.
Radiation Protection
- Surveys were completed and documented as outlined in the Annual Report.
- 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 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
- The licensee continued to ship radioactive material in accordance with regulatory requirements.
REPORT DETAILS
Summary of Facility Status
The Massachusetts Institute of Technologys (MITs or the licensees) Nuclear Reactor Laboratory (NRL) six 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 U.S. Nuclear Regulatory Commission (NRC) requirements.
1.
Organization and Staffing
a.
Inspection Scope (Inspection Procedure (IP) 69006)
The inspector reviewed the following regarding the Massachusetts Institute of Technology Reactor (designated as MITR-II) organization, staffing, and management responsibilities to ensure that the requirements of Technical Specification (TS) Section 7, Administrative Controls, Revision (Rev.) 6, dated November 1, 2010, were being met:
- Management responsibilities
Qualifications of facility radiation protection personnel
MIT NRL Organization Chart, dated November 19, 2013
Staffing requirements for operation of the research reactor
MIT Research Reactor, Nuclear Reactor Laboratory, Massachusetts Institute of Technology Annual Report to the U.S. Nuclear Regulatory Commission for the Period January 1, 2012 to December 31, 2012, submitted March 30, 2013
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, 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. In addition, 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
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RPO was also a member of the facility Reactor Safeguards Committee (RSC). It was noted that the reactor radiation protection personnel provided assistance and job coverage for work done by Operations Group personnel.
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 TSs 7.5.1 and 7.5.2 and Title 10 of the Code of Federal Regulations (10 CFR) Section 50.59, the following documents were reviewed:
- Minutes of the MIT Reactor Safeguards Committee, meeting No. 104, held May 16, 2013
MIT Administrative Procedure 1.4, Review and Approval of Plans, Procedures, and Facility Equipment and Changes Thereto, latest revision dated June 22, 1988, with the associated Safety Review Form, latest for revision dated May 6, 2008
10 CFR 50.59 Evaluation E-13-4, Fission Chamber Signal for Channel #2 Using TKV23 Pre-Amplifier, completed August 1, 2013
10 CFR 50.59 Evaluation E-13-5, Replacement of Existing Primary Flow/Delta T Recorder and Process Flow Recorder, completed October 29, 2013
MIT Research Reactor, Nuclear Reactor Laboratory, Massachusetts Institute of Technology Annual Report to the U.S. Nuclear Regulatory Commission for the Period January 1, 2012 to December 31, 2012, submitted March 30, 2013
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. Meeting frequency met the minimum requirements; the last full committee meeting was completed on May 16, 2013, which satisfied the required annual frequency of the Technical Specifications.
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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 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.
The inspector reviewed two recently completed 10 CFR 50.59 evaluations (SR E-13-4 and SR E-13-5).
The inspector reviewed 10 CFR 50.59 evaluation E-13-4, Fission Chamber Signal for Channel #2 Using TKV23 Pre-Amplifier, completed August 1, 2013. This modification changed the fission chamber used for source range operations of nuclear safety channel #2 from the previous peanut-type detector to a fission chamber installed with the new digital wide range channel system in 2012. The non-discriminated pulse signal from the new fission chamber is designed to pass through the digital wide range system without distortion to the existing single channel analyzer for Channel #2 on the main console. The modification had been installed at the time of the inspection, but was not yet operational as the facility was shut down at the time of the inspection. The required safety review forms were completed and approved in accordance with facility procedures.
The inspector reviewed 10 CFR 50.59 evaluation E-13-5, Replacement of Existing Primary Flow/Delta T Recorder and Process Flow Recorder, completed October 29, 2013. This modification replaces the existing primary flow/delta T analog recorder and the existing secondary shield and D2O flow recorder with a single new digital recorder. In addition, the modification adds three new reactor scrams (primary flow, reflector flow, and shield flow). The licensees 10 CFR 50.59 review concluded that the new recorder and the additional scrams could be added to the facility without prior NRC approval. The required safety review forms were completed and approved in accordance with facility procedures. The inspector determined that additional discussion with NRC headquarters staff concerning the addition of three new scrams is required and follow-up review of this item has been designated as Unresolved Item 50-020/2013-203-01.
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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 7.10, Radiation Protection Program, and 10 CFR Parts 19 and 20, the inspector reviewed selected aspects of the following:
- Quarterly Landauer dosimetry reports for fourth quarter 2012, and to date in 2013
Observations of facilities, equipment, operations, and postings during facility tours
Memorandum from the RPO documenting the annual As Low As Reasonably Achievable (ALARA) Program Review of the radiation protection program for 2012, dated May 9, 2013
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 the U.S. Nuclear Regulatory Commission for the Period January 1, 2012 to December 31, 2012, submitted March 30, 2013
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.
Results of the surveys were typically documented on survey maps and posted at the entrances of the various areas surveyed so that facility workers and visitors would be aware of the radiological conditions that existed therein.
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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 2 years showed that the highest occupational doses, as well as doses to the public, were within 10 CFR Part 20 limits. The records showed that 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. Certain instruments were shipped to a vendor for calibration. Calibration frequency met procedural requirements and records were maintained as required. Area radiation monitors and stack monitors were also being calibrated as required.
These monitors were typically calibrated by licensee staff personnel.
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
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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 licensee indicated that a refresher course was given annually so that current topics could be brought up and discussed by staff members.
Through records review the inspector found that the refresher training given during the first part of 2013 included topics such as the use of new equipment and the proper reporting of personal contamination.
(6)
MIT 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 dose goal for 2012 was 3.0 person-rem. The cumulative dose for 2012 was 2.8 person-rem. The goal for 2013 is 2.7 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 because:
(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 7.13.5.f and h:
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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 the U.S. Nuclear Regulatory Commission for the Period January 1, 2012 to December 31, 2012, submitted March 30, 2013
b.
Observations and Findings
The inspector determined that gaseous releases continued to be monitored as required, were acceptably analyzed, and were documented in the annual operating reports in accordance with TS 7.13.5. Airborne concentrations of gaseous releases, principally Argon-41, were well within the concentrations stipulated in 10 CFR 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 CY 2012 was 130.9 millicuries of tritium and 0.168 millicuries of all other isotopes. The predominant source was acknowledged to be the cooling tower blowdown. The concentration was below the 10 CFR 20.2003 limit with no credit for dilution due to other MIT waste streams (estimated at 2.7 million gallons per day).
Solid waste and tritiated liquid waste was shipped to a licensed, offsite disposal facility. There were no investigative studies or human therapy exposures during the year to be reported pursuant to TS 7.13.5.i.
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
a.
Inspection Scope (IP 86740)
To verify compliance with regulatory requirements for shipping licensed radioactive material, the inspector reviewed the following:
- Various completed forms, including NRC Form 540, Uniform Low Level Radioactive Waste Manifest, for 2012
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2012 DOT Shipping Audit, completed by a senior reactor operator
MIT Research Reactor, Nuclear Reactor Laboratory, Massachusetts Institute of Technology Annual Report to the U.S. Nuclear Regulatory Commission for the Period January 1, 2012 to December 31, 2012, submitted March 30, 2013
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 completed the majority of the shipments.
The inspector also verified that the licensee maintained copies of consignees licenses to possess radioactive material as required and that the licenses were verified to be current prior to initiating a shipment. 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 Briefing
The inspection scope and results were summarized on November 21, 2013, 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.
PARTIAL LIST OF PERSONS CONTACTED
Licensee Personnel
J. Bernard
Senior Advisor T. Bork
Irradiation Service Coordinator D. Cormier
Senior Technician, Reactor Radiation Protection Office, EH&S J. Foster
Superintendent of Reactor Operations E. Lau
Associate Director, Reactor Operations W. McCarthy Reactor Radiation Protection Officer and Deputy Director, Environment, Health, and Safety Office, MIT D. Moncton
Director, Nuclear Reactor Laboratory Director of Reactor Operations J. Quattrochi Staff Officer, Reactor Radiation Protection Office, EH&S P. Same
Reactor Supervisor S. Tucker
Quality Assurance Supervisor M. Young
Administrative Officer
INSPECTION PROCEDURES USED
IP 69004 Class 1 Research and Test Reactor Effluent and Environmental Monitoring IP 69005 Class 1 Research and Test Reactors Experiments 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:
50-020/2013-203-01 URI Addition of three new reactor scrams for Primary Flow, Reflector Flow, and Shield Flow.
Closed:
None
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LIST OF ACRONYMS USED
10 CFR Title 10 of the Code of Federal Regulations ADAMS Agencywide Documents Access and Management System 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 No.
Number 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