IR 05000020/2015203

IR 05000020/2015203, November 16-19, 2015, Massachusetts Institute of Technology

ML15349A897
Person / Time
Site:	MIT Nuclear Research Reactor
Issue date:	12/17/2015
From:	Anthony Mendiola Research and Test Reactors Branch B
To:	Foster J Massachusetts Institute of Technology (MIT)
Eads J
References
IR 2015203
Download: ML15349A897 (17)

Text

December 17, 2015

SUBJECT:

MASSACHUSETTS INSTITUTE OF TECHNOLOGY - U.S. NUCLEAR REGULATORY COMMISSION ROUTINE INSPECTION REPORT NO. 50 020/2015-203

Dear Mr. Foster:

From November 16 -19, 2015, the U.S. Nuclear Regulatory Commission (NRC) conducted an inspection at the Massachusetts Institute of Technology Research Reactor facility. The enclosed report documents the inspection results, which were discussed on November 19, 2015, with you and members of your staff.

The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.

The inspector reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, no findings of significance were identified.

No response to this letter is required.

In accordance with Title 10 of the Code of Federal Regulations Section 2.390, Public inspections, exemptions, 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 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. Should you have any questions concerning this inspection, please contact 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 Policy and Rulemaking 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

Jack Priest, Director Radiation Control Program Department of Public Health 529 Main Street Schrafft Center, Suite 1M2A Charlestown, MA 02129

John Giarrusso, Planning and Preparedness Division Chief 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

ML15349A897; * concurred via e-mail NRC-002 OFFICE NRR/DPR/PROB/PM*

NRR/DPR/PROB/LA*

NRR/DPR/PROB/BC NAME JEads NParker AMendiola DATE 12/14/2015 12/14/2015 12/17/2015

Enclosure U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION

Docket No.: 50-020

License No.:

R-37

Report No.:

50-020/2015-203

Licensee:

Massachusetts Institute of Technology

Facility:

Nuclear Reactor Laboratory

Location:

Cambridge, Massachusetts

Dates:

November 16-19, 2015

Inspector:

Johnny Eads

Accompanied by:

William Schuster

Approved by:

Anthony J. Mendiola, 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 Inspection Report No. 50-020/2015-203

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) 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 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 of Radioactive Materials

• 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 16, 2015

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, 2014 to December 31, 2014, submitted March 31, 2015

Letter from Thomas Newton, Correction to Annual Report, MIT Research Reactor, Docket 50-20, dated May 19, 2015

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.

Due to recent changes in staffing, an Acting Director of Reactor Operations and an Acting Superintendent of Reactor Operations were designated by the facility.

The inspector reviewed the qualifications of both the Acting Director of Reactor Operations and the Acting Superintendent of Reactor Operations and determined that the individuals met the requirements for the positions as described in TS.

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Otherwise, 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 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, Changes, tests and experiments, the following documents were reviewed:

• Minutes of the MIT RSC, meeting No. 106, held December 2, 2014

Minutes of the MIT RSC, meeting No. 107, held May 28, 2015

10 CFR 50.59 Evaluations completed since the last inspection in November 2014

MIT Research Reactor, Nuclear Reactor Laboratory, Massachusetts Institute of Technology, Annual Report to U.S. Nuclear Regulatory Commission for the Period January 1, 2014 to December 31, 2014, submitted March 31, 2015

Letter from Thomas Newton, Correction to Annual Report, MIT Research Reactor, Docket 50-20, dated May 19, 2015

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

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attending to non-routine emerging issues. Meeting frequency met the minimum requirements; the last full committee meeting was completed on May 15, 2015, which satisfied the required annual frequency of the TSs.

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 10 CFR 50.59 evaluations completed since the last inspection in November 2014. The licensees 10 CFR 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 7.10, 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 2014, and to date in 2015

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

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• 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, 2014 to December 31, 2014, submitted March 31, 2015

Letter from Thomas Newton, Correction to Annual Report, MIT Research Reactor, Docket 50-20, dated May 19, 2015

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.

(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

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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 refresher training given included topics such as the facility as low as reasonably achievable (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.

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The dose goal for 2014 was 2.0 person-rem. The cumulative dose for 2014 was 1.7 person-rem. The goal for 2015 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:

• 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, 2014 to December 31, 2014, submitted March 31, 2015

Letter from Thomas Newton, Correction to Annual Report, MIT Research Reactor, Docket 50-20, dated May 19, 2015

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.

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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 Calendar Year 2014 was 48.8 millicuries of tritium and 0.0694 millicuries 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.

Solid waste and tritiated liquid waste 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 7.7.1.9.

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 2014, including:

o NRC Form 540, Uniform Low Level Radioactive Waste Manifest, Shipping Paper o NRC Form 541, Uniform Low Level Radioactive Waste Manifest, Container and Waste Description o NRC Form 542, Uniform Low Level Radioactive Waste Manifest, Manifest Index and Regional Compact Tabulation o Hazardous Goods Declaration forms o Bill of Lading forms o Surveys o MIT sample irradiation forms

2014 DOT Shipping Audit, completed by a senior reactor operator

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• MIT Research Reactor, Nuclear Reactor Laboratory, Massachusetts Institute of Technology, Annual Report to U.S. Nuclear Regulatory Commission for the Period January 1, 2014 to December 31, 2014, submitted March 31, 2015

Letter from Thomas Newton, Correction to Annual Report, MIT Research Reactor, Docket 50-20, dated May 19, 2015

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 Briefing

The inspection scope and results were summarized on November 19, 2015, 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 S. Don

Acting Superintendent of Reactor Operations Acting Director, Reactor Operations E. Lau

Associate Director, Reactor Operations M. Mahowald Technician, Reactor Radiation Protection Office, 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 Senior Technician, Reactor Radiation Protection Office, 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

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