ML17201Q549
| ML17201Q549 | |
| Person / Time | |
|---|---|
| Site: | MIT Nuclear Research Reactor |
| Issue date: | 07/27/2017 |
| From: | Anthony Mendiola Research and Test Reactors Oversight Branch |
| To: | Queirolo A Massachusetts Institute of Technology (MIT) |
| Eads J | |
| References | |
| 50-020/2017-201, IR 2017201 | |
| Download: ML17201Q549 (17) | |
See also: IR 05000020/2017201
Text
July 27, 2017
Mr. Al Queirolo, Director
of Reactor Operations
Massachusetts Institute of Technology Nuclear Reactor Laboratory
Research Reactor
138 Albany Street, MS NW12-116A
Cambridge, MA 02139
SUBJECT: MASSACHUSETTS INSTITUTE OF TECHNOLOGY - U.S. NUCLEAR REGULATORY COMMISSION ROUTINE INSPECTION REPORT
NO. 50-020/2017-201
Dear Dr. Queirolo:
From April 25-27, 2017, the U.S. Nuclear Regulatory Commission (NRC or Commission)
conducted an inspection at the Massachusetts Institute of Technology Research Reactor facility.
The enclosed report documents the inspection results, which were discussed on April 27, 2017,
with you and members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with Commission's 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 electronica
lly for public inspection in the NRC Public
Document Room or from the NRC's 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).
A. Queirolo - 2 -
Should you have any questions concerning this inspection, please contact Mr. Johnny H. 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
ML17201Q549; *concurred via e-mail NRC-002
OFFICE NRR/DPR/PROB* NRR/DPR/PROB/LA* NRR/DPR/PROB/BC NAME JEads NParker AMendiola DATE 7/24/17 7/21/17 7/27/17
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
Enclosure U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION
Docket No.50-020
License No. R-37
Report No. 50-020/2017-201
Licensee: Massachusetts Institute of Technology
Facility: Nuclear Reactor Laboratory
Location: Cambridge, Massachusetts
Dates: April 25-27, 2017
Inspector: Johnny Eads
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
NRC Inspection Report No. 50-020/2017-201
The primary focus of this routine, announced inspection was the onsite review of selected
aspects of the Massachusetts Institute of Technology (the licensee's) Class I six megawatt
research reactor safety program including: (1) organization and staffing, (2) reactor operations, (3) operator requalification, (4) maintenance and surveillance, (5) fuel handling, (6) experiments, (7) procedures, and (8) emergency preparedness since the last U.S. Nuclear Regulatory
Commission (NRC) inspection of these areas. The licensee's program was acceptably directed toward the protection of public health and safety and in compliance with NRC requirements.
Organization and staffing
- Organizational structure and staffing were consistent with technical specification (TS)
requirements.
Reactor Operations
- Reactor operations were conducted in accordance with procedure and the appropriate logs
were being maintained.
Operator Requalification
- Operator requalification was conducted as required by the Requalification Program and the program was being maintained up-to-date.
- Operators were receiving biennial medical examinations as required.
Maintenance and Surveillance
- The system for tracking and completing maintenance items and surveillance checks and calibrations was adequate and was being maintained as required.
- Maintenance and surveillance records, performance, and reviews satisfied TS and procedure requirements.
Fuel Handling
- Fuel was being controlled as required and fuel movements were conducted in accordance with TS and procedural requirements.
Experiments
- The program for reviewing and conducting experiments satisfied procedural and TS
requirements.
- 2 -Procedures
- The procedure review, revision, control, and implementation program satisfied TS
requirements.
- The emergency preparedness program was conduc
ted in accordance with the Emergency
Plan (E-Plan).
- Emergency response equipment was being maintained and inventoried as required.
- Emergency drills were being conducted annually as required by the E-Plan.
- Emergency preparedness training for licensed operators and personnel from various support organizations was being completed as required.
REPORT DETAILS
Summary of Facility Status
The Massachusetts Institute of Technology (MIT or the licensee) Nuclear Reactor Laboratory
(NRL) six megawatt research and test 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. During the inspection, the reactor was shutdown for maintenance.
1. Organization and Staffing
a. Inspection Scope (Inspection Procedure (IP) 69006)
The inspector reviewed the Massachusetts Institute of Technology Reactor (designated as MITR-II) organization and staffing to ensure that the requirements
of technical specification (TS) 7.1, implemented through Renewed Facility
Operating License R-37, Amendment 40 issued August 13, 2015, were being
met regarding the following:
- Management responsibilities
- Qualifications of facility operations personnel
- MIT NRL Organization Chart, dated April 12, 2017
- Reactor Digital Logbook covering the period from March 2016 to present
- Staffing requirements for reactor operation stated in TS 7.1.3
- "MIT Research Reactor, Nuclear Reactor Laboratory, Massachusetts Institute of Technology Annual Report to the U.S. Nuclear Regulatory Commission for
the Period January 1, 2016, to December 31, 2016."
b. Observations and Findings
The inspector noted that the Director of Reactor Operations continued to report to the Director of the MIT NRL, who in turn reported to the President of the
university through the Vice President for Research. This organization was
consistent with that specified in the TS. The organizational structure and the
responsibilities of the reactor staff had not changed since the last inspection.
Staffing levels remained consistent with those noted during the last inspection of
the facility. The current reactor operations organization consisted of the Director
of Reactor Operations, the Deputy Director of Reactor Operations, the Assistant
Director of Operations, the Superintendent of Operations, the Training
Coordinator, a Quality Assurance Supervisor, and various reactor supervisors, and reactor operators (ROs). The Deputy Director of Reactor Operations, the Assistant Director of Reactor Operations, the Superintendent of Operations, the
Quality Assurance Supervisor, the Training Coordinator, and the majority of the
reactor supervisors were licensed senior reactor operators (SROs). In addition to
the operations staff, there were various support groups, including a research staff, a research development group, a reactor engineering staff, maintenance personnel, and a reactor radiation protection group. Through a review of reactor
- 2 - operations logs for the period from March 2016 through the present, and through interviews with operations personnel, the inspector determined that the licensee normally operated 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> a day with three crews and no shift rotation. Each
operating crew was staffed with various personnel (with at least two licensed
operators on duty at the MITR-II per shift). Operations shifts were scheduled for
a period of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. The review of the reactor (console) logbooks and associated
records confirmed that shift staffing during reactor operations met the minimum requirements for duty and on-call personnel specified in TS 7.1.3.
c. Conclusion
The licensee's organization and staffing were in compliance with the requirements specified in TS 7.1.
2. Reactor Operations
a. Inspection Scope (IP 69006)
To verify that the licensee was conducting reactor operations in accordance with
TS Sections 2 and 3 and procedural requirements, the inspector reviewed
selected portions of the following:
- Reactor Digital Logbook covering the period from March 2016 to present
- "MIT Research Reactor, Nuclear Reactor Laboratory, Massachusetts Institute of Technology Annual Report to the U.S. Nuclear Regulatory Commission for
the Period January 1, 2016, to December 31, 2016."
b. Observations and Findings
(1) Reactor Operation
The inspector observed facility activities on various occasions during the week including routine reactor operations and updating the console logs while the reactor was shutdown for maintenance. Written procedures and
checklists were used for each activity as required. It was noted that the
reactor operators followed the appropriate procedures, were
knowledgeable of the required actions, and professional in the conduct of
their duties.
(2) Staff Communication
During the inspection, the inspector observed reactor operator turnover
activities during the shift. The status of the reactor and the facility was discussed on each occasion as required. The oncoming personnel were briefed on the upcoming activities and scheduled events before assuming
the operations duty. Through direct observation and records review, the
inspector verified that the content of turnover briefings was appropriate
- 3 - and that shift activities and plant conditions were discussed in sufficient
detail. c. Conclusion
MITR-II reactor operations, as well as turnovers and operator cognizance of
facility conditions during routine operations, were acceptable.
3. Operator Requalification
a. Inspection Scope (IP 69003)
To verify that the licensee was complying with the requirements of Title 10 of the
Code of Federal Regulations (10 CFR) Part 55 and TS 7.2.3.3 (b) and conforming to Chapter 12, Sections 12.1 and 12.10 of the facility safety analysis
report, the inspector reviewed selected aspects of the following:
- Current status of operator licenses
- Reactor Digital Logbook covering the period from March 2016 to present
- Results of the annual written examinations completed in 2016
- Medical examination records for selected operators for the past 2 years
- Procedure Manual (PM) 1.16, "Requalification and Qualification," latest revision dated February 20, 2013.
b. Observations and Findings
There were 21 individuals licensed to operate the reactor at MIT. Of those personnel, 15 were qualified SROs and 6 were ROs. A review of various Requalification Program records indicated that the program was maintained
up-to-date and that SRO and RO licenses were current. MITR-II operator files
and reactor logs also showed that all operators maintained active duty status with
the exception of one SRO who was designated as inactive by the facility. A review of the MITR Safety Committee (MITRSC) meeting minutes and independent audit results indicated that the program was being audited annually
as required by TS 7.2.3.3.(b).
A review of the pertinent logs and records also showed that training was being
conducted in accordance with the licensee's requalification and training program. A series of lectures were given to operators during the 2 year training and requalification cycle. Information regarding facility changes, procedure changes, and other relevant information was routinely routed to all licensed operators for
their review. The inspector verified that the required reactor operations, reactivity
manipulations, other operations activities, and reactor supervisor activities were being completed and the appropriate records were being maintained. The inspector also noted that all operators were receiving biennial medical
examinations within the time frame allowed as required by the program.
- 4 - c. Conclusion
Operator requalification was up-to-date and being completed as required by the
MITR-II Operator Requalification Program. Operators were receiving biennial
medical examinations as required.
4. Maintenance and Surveillance
a. Inspection Scope (IPs 69006 and 69010)
To verify that the licensee was meeting the surveillance requirements specified in
TS Section 4 and that maintenance was being conducted, the inspector reviewed selected aspects of the following:
- MITR-II Job Workbook
- MITR-II Daily Operations Schedule
- Reactor Digital Logbook covering the period from March 2016 to present
- "MIT Research Reactor, Nuclear Reactor Laboratory, Massachusetts Institute of Technology Annual Report to the U.S. Nuclear Regulatory Commission for
the Period January 1, 2016, to December 31, 2016."
b. Observations and Findings
(1) Maintenance
The inspector reviewed the system that the licensee had developed to track and complete maintenance activities. The system was designed to
ensure that all maintenance activities were planned and completed as
scheduled, that post maintenance testing was conducted, and that the
entire process was documented appropriately. The licensee used a
locally developed system called the "Test and Calibration Tracker" which listed nearly all the tests, checks, and calibrations that were due on a monthly basis, as well as MITR-II "Systems, Tests, and Calibrations" notebooks to document completion of the various periodic maintenance
and surveillance activities. The inspector noted that all such tasks were
tracked through this system. The program appeared to be effective.
(2) Surveillance
Various periodic surveillance verifications and calibration records of
equipment, including the testing of various reactor systems, instrumentation, and auxiliary systems
were reviewed by the inspector. TS surveillance items were completed on schedule as required by TS and
in accordance with licensee procedures. The results of selected tests,
checks, and calibrations reviewed by the inspector were noted to be
within the TS and procedurally prescribed parameters.
- 5 -
c. Conclusion
The system for tracking and completing maintenance items and surveillance
checks and calibrations was adequate and was being maintained as required.
Maintenance and surveillance records, performance, and reviews satisfied TS
and procedure requirements.
5. Fuel Handling
a. Inspection Scope (IP 69009)
To ensure that the licensee was following the requirements of TSs 3.1.4, 3.1.6, 4.1.5, and 5.4, the inspector reviewed selected aspects of the following:
- Reactor Digital Logbook covering the period from March 2016 to present
- Approved packets for core configurations completed in 2016 and 2017, including:
"Fuel Loading Permission" Form (form revision dated February 20, 2013), completed for fuel element transfers in 2016 and 2017 to date
b. Observations and Findings
The inspector reviewed the fuel movement process and verified that fuel moves were conducted according to established procedure and documented on specific
fuel movement sheets developed by the Reactor Engineer. The inspector
reviewed selected fuel movement sheets for 2016 and to date in 2017. They had
been developed and used for each specific core refueling as required.
c. Conclusion
Fuel was being controlled as required and fuel movements were performed in
accordance with approved procedures and TS requirements.
6. Experiments
a. Inspection Scope (IP 69005)
To verify compliance with the licensee's procedures, TSs 6, 7.5, and 10 CFR 50.59 the inspector reviewed the following:
- Reactor Digital Logbook covering the period from March 2016 to present
- Experiment Review Process documented in PM 1.10, "Experiment Review and Approval," latest revision dated February 20, 2013.
b. Observations and Findings
The inspector reviewed the experimental review and approval process described
in PM 1.10. The inspector reviewed selected safety review forms and irradiation
- 6 - request forms for experiments that were currently active. The experimental facilities and/or equipment had been evaluated in accordance with TS requirements and the associated data sheets indicated that the experiments
would be within the specified limits. The analysis for each had been performed
and the reviews and approvals completed. The appropriate reviews and
approvals had also been completed for the samples and/or materials to be
irradiated and the experiments were conducted under the cognizance of the reactor supervisor and in accordance with the specified requirements.
c. Conclusion
Conduct and control of experiments met the requirements of the TS and the applicable facility procedures.
7. Procedures
a. Inspection Scope (IP 69008)
To verify that the licensee was meeting the requirements of TS 7.4, the
inspectors reviewed selected aspects of the following:
PM 1.4, "Review and Approval of Plans, Procedures and Facility Equipment and Changes Thereto," which included:
- PM 1.4.1, "Plan, Procedure, and Equipment Change Classification," latest revision dated February 20, 2013 - PM 1.4.2, "Class C Review and Approval," latest revision dated
February 20, 2013 - PM 1.4.3, "Class B Review and Approval," latest revision dated
February 20, 2013 - PM 1.4.4, "Class A Review and Approval," latest revision dated
February 20, 2013 - PM 1.4.5, "Safety Review Form," latest revision dated
February 20, 2013 - PM 1.4.6, "Procedure Manuals," latest revision dated
February 20, 2013
PM 1.5, "Procedure Adherence and Temporary Change Method," latest revision dated February 20, 2013
b. Observations and Findings
The inspector noted that procedures had been developed for reactor operations
and safety as required by the TS 7.4. The licensee's procedures were found to
be acceptable for the current facility status and staffing level. The inspector noted that the administrative procedure specified the responsibilities of the various positions and for the MITRSC.
- 7 - Operations procedures were typically reviewed by operators and support personnel prior to being used/implemented and were revised as needed. The inspector noted that abnormal and emergency procedures were reviewed
annually by all licensed operators as required and revised when needed. Major
procedure revisions were reviewed and approved by the Director of Reactor
Operations and submitted to the MITRSC for review. All procedure changes
were routinely routed to all operators for review as well.
It was also noted that management and supervisory oversight was focused on
proper implementation and adherence to procedures. Through observation of
various activities in progress during the inspection, the inspector noted that
adherence to procedures was adequate.
c. Conclusion
Procedures were properly prepared and implemented in compliance with license
requirements.
a. Inspection Scope (IP 69011)
The inspector reviewed selected aspects to verify compliance with TS 7.2.3.d and the licensee's Emergency Plan and associated procedures of the following:
- Training records for MITR Support Personnel
- Review and Critique of the 2016 Emergency Exercise conducted on August 16, 2016
- Review and Critique of the 2016 actual medical emergencies which occurred on February 13, 2016 and July 6, 2016
- PM 4.0, "MITR-II Emergency Plan and Procedures," revision dated June 20, 2013
- PM 4.4.4, "Emergency Operating Procedures"
b. Observations and Findings
The inspector reviewed the Emergency Plan (EP) and implementing procedures
in use at the reactor and verified that the procedures were reviewed annually by all licensed operators in accordance with the Operator Requalification Program.
Through records reviews and interviews with facility emergency personnel (i.e.,
licensed operators or emergency responders), the inspector determined that they
were knowledgeable of the proper actions to take in case of an emergency. Training for staff members had been conducted annually as required and documented acceptably.
Emergency training for MIT Police Department personnel was required to be
conducted annually by EP Section 4.10.1.1. The inspector reviewed the training
records and noted that the most recent training had been completed as required.
- 8 - The inspector verified that letters of agreement with various emergency support organizations were on file and being maintained.
Communications capabilities with support groups were acceptable and were
verified annually through a communications check with the various organizations.
Emergency call lists had been revised and updated as needed and were
available in various areas of the facility, including in controlled copies of the Emergency Procedures Manuals. The inspector also verified that emergency equipment was being inventoried quarterly as required.
The inspector verified compliance with the EP requirement for annual emergency
plan drills. The licensee met this requirement by conducting radiological emergency and medical emergency drills each year or by taking credit for an actual emergency. Following each drill, a critique was conducted to identify
areas of strength and weakness. Drills and critiques were documented in writing
as referenced above. The drills appeared to be challenging and provided a good
indication of each organization's responsiveness and capabilities.
c. Conclusion
The licensee was maintaining acceptable emergency preparedness in
accordance with TS and E-Plan requirements.
9. Exit Interview
The inspection scope and results were summarized on April 27, 2017, with members of
licensee management. The inspector described the areas inspected and discussed the
preliminary inspection findings. The licensee acknowledged the results of the inspection and did not identify as proprietary any of the material provided to or reviewed during the inspection.
PARTIAL LIST OF PERSONS CONTACTED
Licensee Personnel:
J. Bernard Senior Advisor, Research Staff
S. Don Superintendent Operations
J. Foster Deputy Director of Reactor Operations
E. Lau Assistant Director of Reactor Operations W. McCarthy Reactor Radiation Protection Officer and Deputy Director, MIT Environment, Health, and Safety Office
A. Queirolo Director of Reactor Operations
S. Tucker Quality Assurance Supervisor
INSPECTION PROCEDURES USED
IP 69003 Class 1 Research and Test Reactor Operator Licenses, Requalification, and Medical Examinations IP 69005 Class 1 Research and Test Reactor Experiments IP 69006 Class 1 Research and Test Reactors Organization and Operations and
Maintenance Activities IP 69008 Class 1 Procedures
IP 69009 Class 1 Research and Test Reactor Fuel Movement
IP 69010 Class 1 Research and Test Reactor Surveillance IP 69011 Class 1 Research and Test Reactor Emergency Preparedness
ITEMS OPENED, CLOSED, AND DISCUSSED
Opened: None
Closed: None
LIST OF ACRONYMS USED
CFR Code of Federal Regulations
IP Inspection Procedure
MIT Massachusetts Institute of Technology
MITR Massachusetts Institute of Technology Reactor
MITRSC Massachusetts Institute of Technology Reactor Safety Committee NRC U.S. Nuclear Regulatory Commission NRL Nuclear Reactor Laboratory
PM Procedure Manual
RO Reactor Operator
SRO Senior Reactor Operator TS Technical Specification