IR 05000184/2017202
| ML17300A802 | |
| Person / Time | |
|---|---|
| Site: | National Bureau of Standards Reactor |
| Issue date: | 11/06/2017 |
| From: | Anthony Mendiola Research and Test Reactors Oversight Projects Branch |
| To: | Dimeo R US Dept of Commerce, National Institute of Standards & Technology (NIST) |
| Bassett C, NRC/DLP, 240-535-1842 | |
| References | |
| IR 2017202 | |
| Download: ML17300A802 (21) | |
Text
November 6, 2017
SUBJECT:
NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY - U.S. NUCLEAR REGULATORY COMMISSION ROUTINE INSPECTION REPORT NO. 50-184/2017-202
Dear Dr. Dimeo:
From October 16-19, 2017, the U.S. Nuclear Regulatory Commission (NRC) conducted an inspection at the National Institute of Standards and Technology Center for Neutron Research.
The enclosed report documents the inspection results, which were discussed on October 19, 2017, with you and Dr. Thomas Newton, Deputy Director.
This 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 observed various activities in progress, interviewed personnel, and reviewed selected procedures and representative records. 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 NRCs document system (Agencywide Documents Access and Management System (ADAMS)). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room). If you have any questions concerning this inspection, please contact Craig Bassett at (240) 535-1842 or by electronic mail at Craig.Bassett@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. 50-184 License No. TR-5
Enclosure:
As stated
cc: See next page
National Institute of Standards and Technology
Docket No. 50-184
cc:
Environmental Program Manager III Radiological Health Program Air & Radiation Management Adm.
Maryland Dept of the Environment 1800 Washington Blvd, Suite 750 Baltimore, MD 21230-1724
Director, Department of State Planning 301 West Preston Street Baltimore, MD 21201
Director, Air & Radiation Management Adm.
Maryland Dept of the Environment 1800 Washington Blvd, Suite 710 Baltimore, MD 21230
Director, Department of Natural Resources Power Plant Siting Program Energy and Coastal Zone Administration Tawes State Office Building Annapolis, MD 21401
President Montgomery County Council 100 Maryland Avenue Rockville, MD 20850
Test, Research and Training Reactor Newsletter P.O. Box 118300 University of Florida Gainesville, FL 32611
Dr. Thomas H. Newton, Deputy Director National Institute of Standards and Technology NIST Center for Neutron Research U.S. Department of Commerce 100 Bureau Drive, Mail Stop 6101 Gaithersburg, MD 20899-6101
ML17300A802; *concurred via e-mail
NRC-002 OFFICE NRR/DLP/PROB*
NRR/DLP/PROB*
NRR/DLP/PROB NAME CBassett NParker AMendiola DATE 11/3/17 11/3/17 11/6/17
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION
Docket No:
50-184
License No:
TR-5
Report No:
50-184/2017-202
Licensee:
National Institute of Standards and Technology
Facility:
National Bureau of Standards Test Reactor
Location:
Gaithersburg, MD
Dates:
October 16-19, 2017
Inspector:
Craig Bassett
Approved by:
Anthony J. Mendiola, Chief Research and Test Reactors Oversight Branch Division of Licensing Projects Office of Nuclear Reactor Regulation
EXECUTIVE SUMMARY
National Institute of Standards and Technology Center for Neutron Research National Bureau of Standards Test Reactor NRC Inspection Report No. 50-184/2017-202
The primary focus of this routine, announced inspection was the onsite review of selected aspects of the National Institute of Standards and Technology (the licensees) Class I 20 megawatt test reactor facility safety program including: (1) organization and staffing, (2) review, audit, and design change functions, (3) reactor operations, (4) operator requalification, (5) maintenance and surveillance, (6) fuel movement, (7) experiments, (8) procedures, and (9) emergency preparedness since the last U.S. Nuclear Regulatory Commission (NRC) inspection of these areas. The licensees safety program was acceptably directed toward the protection of public health and safety and was in compliance with NRC requirements. No violations or deviations were identified.
Organization and Staffing
- The established organization was consistent with technical specification (TS) Section 6.1 requirements.
- Staffing levels at the facility were adequate for the current level of operations.
Review, Audit, and Design Change Functions
- The facility Safety Evaluation Committee was meeting as required and reviewing the topics outlined in the TSs.
- Annual independent audits were being conducted by a Safety Assessment Committee as required.
- The design change program being implemented at the facility satisfied NRC requirements.
Reactor Operations
- Acceptable reactor operations were being conducted and the appropriate shift staffing was being maintained.
Operator Requalification
- Operator requalification was being conducted and completed as required by the requalification program and the program was being maintained current.
- Physical examinations for operators were being completed every 2 years as required.
Maintenance and Surveillance
- The maintenance program was being conducted in accordance with applicable procedural requirements.
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The surveillance program was being completed in a timely manner and as specified in the facilitys TSs.
Fuel Movement
- Fuel movement and handling was accomplished in accordance with TSs and procedural requirements.
Experiments
- The program for experiment review and approval satisfied TSs and procedural requirements.
Procedures
- The procedure revision, control, and implementation program satisfied TSs requirements.
- The Emergency Plan (E-Plan) and Emergency Instruction Manual (or implementing procedures) were being audited and reviewed biennially as required.
- Drills and exercises were being held and follow-up critiques were conducted to identify corrective actions that could be taken as needed.
- Emergency preparedness training for staff and offsite personnel was being conducted as stipulated in the E-Plan.
- Adequate offsite emergency support was being provided by various agencies as required.
Enclosure REPORT DETAILS
Summary of Facility Status
The National Institute of Standards and Technology (NIST or the licensee) NIST Center for Neutron Research (NCNR) reactor, a 20 megawatt test reactor commonly known as the National Bureau of Standards Reactor (NBSR), continued to be operated in support of laboratory experiments and various types of research. During the week of the inspection the facility was in an extended maintenance shutdown and no reactor operations occurred.
1.
Organizational and Staffing
a.
Inspection Scope (Inspection Procedure (IP) 69006)
To verify that the licensee was complying with the organizational and staffing requirements specified in NBSR technical specification (TS) Section 6.1 the inspector reviewed selected aspects of the following:
- Current NCNR organization and staffing
Reactor Console Logbooks Numbers (Nos.) 158 through 162
Management and staff responsibilities outlined in the TSs
NBSR Administrative Rules (AR) 1.0, Responsibilities of Operations Personnel
NBSR AR 2.0, Personnel Requirements
NBSR Emergency Instruction (EI) 0.2, Emergency Organization and Phone Numbers, listing emergency contact information for Reactor Operations personnel
b.
Observations and Findings
Through discussions with licensee personnel and review of pertinent documents, the inspector determined that the licensees organizational structure had not changed since the last inspection in the area of reactor operations (refer to NRC Inspection Report No. 50-184/2016-203). Also, the organizational structure remained consistent with the requirements of TS Section 6.1 and Figure 6.1. In addition, the inspector found that the various management and supervisory personnel in the Reactor Operations Group exceeded the minimum qualifications specified in the TSs with regard to education and experience.
In discussing staffing with management personnel, the inspector noted that there were 17 qualified senior reactor operators (SROs) at the facility who were assigned to the various operating crews, in management positions, or working in the Reactor Engineering group. Through interviews with operations personnel, the inspector determined that there were four operating crews at the facility who worked rotating shifts. Additionally, there was a fifth day shift crew and individuals on that crew typically only worked during the weekdays, but also provided coverage on occasions when individuals from the other crews were unavailable. Each crew was typically staffed with three or four individuals who were licensed SROs and possibly a trainee.
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Through a review of selected entries in the console logbooks for the period from January 2016 to the present and through interviews with operations personnel, the inspector verified that staffing during routine reactor operation was as required and appeared to be adequate. It was also noted that a list of reactor facility personnel by name and telephone number was available to the reactor operators in the control room and was updated at least annually as required by TS Section 6.1.3. The list was last updated on July 25, 2017.
c.
Conclusion
The established organization was consistent with TS 6.1 requirements and the operations staffing level appeared to be adequate for the current level of operations.
2.
Review, Audit, and Design Change Functions
a.
Inspection Scope (IP 69007)
The inspector reviewed the following to ensure that the requirements of TS Section 6.2 and Title 10 of the Code of Federal Regulations (10 CFR) 50.59 were being implemented effectively:
- NCNR Safety Evaluation Committee (SEC) meeting minutes for May 2016 through the present (Meeting Nos. 381 through 383)
NBSR Procedure No. NBSR-0007-DOC-04, Engineering Manual, Revision 4, which included procedures and instructions for completing changes at the facility
2016 reactor audit conducted in accordance with TS 6.2.4, SEC Audit Function, (1-4) by the NCNR Audit Subcommittee of the SEC, dated October 17, 2016
2015 Annual [Audit] Report of the Safety Assessment Committee, audit conducted during November 2-4, 2015, and report dated March 15, 2016
2016 Annual [Audit] Report of the Safety Assessment Committee, audit conducted during November 14-16, 2016, and report dated March 2, 2017
NCNR SEC Charter, approval dated June 16, 2016
NBSR Engineering Change Request/Engineering Change Notice (ECR/ECN)
No. 985, Storage Pool Data Acquisition and Display System, ECR Level II review dated February 7, 2017, and ECN Level II review and approval dated April 24, 2017, (with the associated 10 CFR 50.59 Evaluation)
NBSR ECR/ECN No. 1009, Normal Air Monitor Upgrade, ECR Level II review dated March 6, 2017, and ECN Level II review and approval dated May 12, 2017, (with the associated 10 CFR 50.59 Evaluation)
NBSR ECR/ECN No. 1018, Replacement of Critical Power Panel CP3, Emergency Lighting Panels X1 and X2, and Automatic Transfer Switch TS-3, ECR Level II review dated April 3, 2017, and ECN Level II review and approval dated August 23, 2017, (the project screened out and no 10 CFR 50.59 Evaluation was needed)
Operations Report No. 68, NBSR Annual Report, for the period from January 1, 2015, through December 31, 2015, issued April 13, 2016
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- Operations Report No. 69, NBSR Annual Report, for the period from January 1, 2016, through December 31, 2016, issued April 25, 2017
b.
Observations and Findings
(1)
Review and Audits Functions
The inspector reviewed the charter of the SEC required by the TSs. It was noted that the charter delineated the committees membership, organization, and responsibilities, as well as quorum and meeting requirements. The charter also authorized the formation of subcommittees to assist the SEC. Four subcommittees had been organized for that purpose including: (1) the Audit Subcommittee, (2) the Beam Experiment Subcommittee (BES), (3) the Irradiation Subcommittee, and (4) the Procedure Review Subcommittee (PRS). A charter had been developed for each subcommittee and the various charters had been reviewed and approved by the SEC.
Records of the meetings held by the SEC from May 2016 through the date of the inspection were reviewed. The meeting minutes showed that meetings were held at least semiannually as required by the SEC Charter and reviews of proposed changes and experiments were completed by the SEC or by a designated subcommittee. The minutes also indicated that the SEC provided appropriate guidance and direction for reactor operations and ensured suitable use and oversight of the reactor.
A review of audit records indicated that the SEC Audit Subcommittee conducted an annual audit of the safety program at the facility in accordance with TS Section 6.2.4. The audits appeared to be appropriate. The audits were reviewed by the full SEC and licensee management responded to the subcommittees findings and recommendations. In addition, corrective actions were taken as warranted.
Other records reviewed by the inspector showed that, as required by TS Section 6.2.5, a Safety Assessment Committee (SAC) was convened annually to conduct an independent audit. The 2016 audit was conducted by individuals from various Research and Test Reactors around the United States including representatives from the University of Maryland, University of Missouri - Columbia, University of Massachusetts - Lowell, and Massachusetts Institute of Technology. The SAC audit provided good insight into the licensees program and made various worthwhile recommendations for program improvement. The licensee responded to the findings and took actions/corrective actions as needed.
(2)
Design Change Functions
The inspector reviewed selected requests for changes to the facility (i.e.,
changes to structures, systems, or components) that had been proposed within the last 2 years. At NIST these change proposals were designated as ECRs. Each ECR documented what was proposed to be changed, the
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facility drawings that would need to be changed, the procedures that would require revision, and any tests or measurements that would need to be completed following the change. In order to track the change requests, they were numbered sequentially during the year. These were screened to determine whether or not a 10 CFR 50.59 review would be required. Based on the safety significance and the 10 CFR 50.59 screen results, the changes were classified as either Level I (Minor) or Level II (Major). All Level II ECRs required a 10 CFR 50.59 review which often resulted in the completion of a 10 CFR 50.59 evaluation.
Once an ECR was approved, indicating that the change project could move forward, an ECN was developed which contained various sections.
The sections detailed the design description, safety considerations and analysis, a safety evaluation, and the 10 CFR 50.59 screening or review criteria results.
A review of selected ECRs and ECNs demonstrated that changes were acceptably documented and reviewed in accordance with NRC requirements and the licensees guidelines. It also indicated that the work and the required document revisions were being completed as necessary.
It was noted that the changes were being tracked to completion by the licensee. One change package reviewed by the inspector met one of the criteria of 10 CFR 50.59(c)(2), which would require a change to the TSs and, therefore, required a license amendment from the NRC. The licensee was pursuing a license amendment regarding this change.
c.
Conclusion
The facility SEC was meeting as required and reviewing the topics outlined in the TSs. Independent annual audits were being conducted by a SAC as required.
The licensees design change program satisfied NRC requirements.
3.
Reactor Operations
a.
Inspection Scope (IP 69006)
To verify that the licensee was operating the reactor and conducting operations in accordance with TS Sections 2.0 and 3.0 and procedural requirements, the inspector reviewed selected portions of the following:
- Reactor Console Logbooks Nos. 158 through 162
Various NIST reactor control room log sheets
Selected NIST reactor area inspection log sheets
Shift supervisors instructions and special log sheets
NBSR Reactor Shift Supervisor Logbook Nos. 42 and 43
Selected reactor operations shift turnover log notebook entries
Associated reactor operations records from October 2016 to the present
NBSR AR 2.0, Personnel Requirements
NBSR AR 9.0, Reactor Startup and Operation
Selected NBSR Operating Instructions (OIs) (i.e., operating procedures)
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- Facility NBSR Annual Reports, for the past 2 years (as referenced in Paragraph 2 above)
b.
Observations and Findings
During the inspection, the reactor was shut down for an extended maintenance outage. The planned activities for the outage included replacing the primary pumps and removing and replacing the four shim arms in the reactor. The inspector was able to observe various activities in progress. Although no reactor operations took place during the inspection, a review of logs and related records indicated that, when the reactor was operated, operations were conducted in accordance with facility procedures as required. The logs and records were clear and provided an indication of ongoing activities. The records reviewed demonstrated that shift staffing during reactor operation, as well as during outage maintenance periods, was being maintained as required by TS Section 6.1.3.
The records reviewed also showed that operational conditions and parameters were consistent with TSs and procedural requirements and that these conditions and requirements were satisfied. Reactor startup procedure, NBSR OI 1.1, required verification of each of the limiting conditions for operations specified in TS Sections 3.1 through 3.9 prior to startup. These verifications were being completed and recorded as required. The inspector noted that various other applicable procedural requirements were also being met.
c.
Conclusion
Acceptable shift staffing was being maintained and operations were being conducted in accordance with procedures.
4.
Operator Requalification
a.
Inspection Scope (IP 69003)
To verify compliance with the operator requalification program for the NBSR, which was last updated March 2009, the inspector reviewed:
- Reactor Console Logbooks Nos. 158 through 162
Medical examination records from 2014 through 2017
Current status of selected qualified operators licenses
NBSR requalification (biennial) examinations for 2014 and 2016
Training provided the operators during the NBSR 2014-2015 and 2016-2017 requalification training cycles
Operator training records for the years 2014, 2015, 2016, and 2017 to date, documented on forms entitled, Requalification Program Documentation Review and Reactivity Changes, no revision date
Supervisors annual operator evaluations documented on forms entitled, Operator Evaluation (form revised November 2009)
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b.
Observations and Findings
As mentioned previously, there were 17 qualified SROs employed at the facility.
In addition, it was noted that, due to anticipated retirements and/or people leaving the facility this year, the licensee was in the process of acquiring administrative approval to fill three more SRO positions at the facility. Through a review of various requalification and training documents, the inspector verified that the facility SRO operators licenses were current and records of the licensed operators requalification status were being maintained as required.
A review of program records also showed that operator training was consistent with the NBSR requalification program requirements. The inspector verified that all operators had completed the requalification training and had taken the written biennial requalification examinations. Additional training on various plant systems and industrial hygiene/safety was also provided. NBSR console logbooks and requalification records showed that operators maintained active duty status by participating in the reactivity manipulations and document reviews as outlined and required in the requalification program. The inspector also confirmed that the operators had been given annual operating evaluations as required. In addition, the inspector verified that the qualified operators were receiving a physical examination every two years as well.
c.
Conclusion
Operator requalification was being conducted and completed as required by the licensees requalification program. Physical examinations for the operators were being completed every 2 years as required.
5.
Maintenance and Surveillance
a.
Inspection Scope (IP 69006 and IP 69010)
To ensure that maintenance activities were being completed and to determine that surveillance activities and calibrations were being completed as required by TS Section 4.0, the inspector reviewed selected aspects of:
- Reactor Console Logbooks Nos. 158 through 162
Selected TSs surveillance schedules for each month for the period from January to October 2017, which indicated which surveillance activities were due for completion during that month
Selected NIST reactor area inspection log sheets (completed every shift during routine operation) for the past 12 months
Selected NIST reactor control room log sheets (data taken every hour during routine operation) for the past 12 months
Selected NBSR Instrument Test Procedures and TS Procedures
NIST Test Reactor (NBSR) Procedure, Reference Procedure 110, Shim Arm Removal and Replacement and Filling of Vessel and Primary Piping, Initial revision, approval dated October 12, 2017
Facility NBSR Annual Reports, for the past 2 years (as referenced in Paragraph 2 above)
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b.
Observations and Findings
(1)
Maintenance Activities
As noted above, the reactor was in an extended maintenance shutdown and various activities were scheduled to be completed. The inspector was able to observe various maintenance activities including the replacement of a shim arm in the reactor. It was noted that operations personnel followed procedure during the replacement work while health physics technicians provided needed support. The procedure and the Radiation Work Permits associated with the work in C-200 and C-100 were adequate and provided appropriate constraints and guidance.
The inspector also reviewed various maintenance records, console logbooks, and data sheets which indicated that routine maintenance activities were conducted at the required frequency and in accordance with the applicable procedure or equipment manual. Maintenance activities ensured that equipment remained consistent with the safety analysis report and TS requirements.
(2)
Surveillance Activities
The inspector reviewed various surveillance and calibration records. The completion and results of these activities were tracked by the Chief of Reactor Operations, as well as by operations personnel. Tracking was done by means of the TSs Surveillance Schedule, which was revised and updated as the tasks were completed. A new surveillance schedule was issued monthly. A review of the monthly surveillance schedules, console logbooks, and related data recorded on the appropriate forms indicated that the surveillances and calibrations were completed at the frequency specified in the TSs and in accordance with procedure. If a surveillance activity could not be completed within the established time frame, the reason for the delay was typically documented in the logs or records. All results reviewed by the inspector were within TSs or procedurally prescribed parameters.
c.
Conclusion
The maintenance program was being conducted and documented as required by procedure. The surveillance program was being conducted as specified by TS requirements.
6.
Fuel Movement
a.
Inspection Scope (IP 69009)
The inspector reviewed selected aspects of the following to verify that fuel movement and handling was being conducted as required by TS Sections 3.9 and 5 3:
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- Reactor Console Logbooks Nos. 158 through 162
NBSR Reactor Shift Supervisor Logbook Nos. 42 and 43
Pool Log No. 3 and fuel transfer records from July 2016 to the present
Core reload/refuel and core defuel/refuel verification and sign-off sheets for Core Nos. 633 through 638
NBSR OI 6.2, Operation of Fuel Transfer System, Revision F
NBSR OI 3.3, Operation of the Storage Pool Cooling System, Revision A
b.
Observations and Findings
Licensee procedures and operator instructions provided approved methods to move and handle fuel consistent with the provisions of the TSs and the licensee safety analysis. The inspector reviewed the core loading and fuel handling records for recent refueling cycles and found them to be complete and properly documented. Fuel movement, fuel loading/reloading, and fuel examination records documented that fuel was moved and controlled as required. The records also showed that the fuel movements were verified by various individuals as required and that fuel elements were in the designated locations. Records further showed that fuel handling and monitoring equipment was operable.
Personnel were knowledgeable of the procedural requirements that ensured criticality control and fuel integrity.
As noted above, the facility was in an extended shutdown to replace the shim arms. As a result, the core had been unloaded and all the fuel elements placed in temporary storage in the Spent Fuel Pool. Following completion of the outage, the core will be reloaded and normal operations will resume. The licensee planned to restart the reactor in January 2018.
c.
Conclusion
The licensee maintained and followed procedures which effectively implemented TSs requirements for fuel handling.
7.
Experiments
a.
Inspection Scope (IP 69005)
To ensure that the requirements of TS Sections 3.8, 4.8, and 6.5, and licensees administrative procedures were being met governing the experimental program, the inspector reviewed selected aspects and/or portions of:
- BES Report to the SEC: Meeting 383 (held April 19, 2017)
- Experimental control procedures for various instruments located in the C-100 area and the guide hall
- Rabbit Request List maintained in the Control Room which contained the irradiation requests authorized for the pneumatic system
- Experimental Proposal Approval Sheet for Activity No. 610.02.0019, Very Small Angle Neutron Scattering (VSANS) Instrument on NG-3, approval by the NCNR Director, dated August 30, 2017
- Experimental Proposal Approval Sheet, No 508, NG7 PHADES (Polarized
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He3 and Detector Experiment Station, approval by the NCNR Director, dated July 14, 2015 and reconfigured June 21, 2016
b.
Observations and Findings
Experiments at the NBSR included: (1) irradiation experiments and (2) beam experiments. Irradiation experiments were those conducted in a pneumatic tube or in any other NBSR irradiation facility inside the thermal shield. Beam experiments were ones which were conducted in or with experimental instruments outside the reactor thermal shield. Beam experiments were typically conducted in the C-100 area or the guide hall. For irradiation experiments, the reactivity worth and other criteria were delineated in the TS; no criteria were listed in the TS for beam experiments. Depending upon the type of experiment being proposed, either the Irradiation Subcommittee or the BES reviewed the experimental proposal as required and provided recommendations. Since the TSs did not include criteria for beam port experiments, the licensee developed administrative guidelines to extend the review and approval requirements in TS Section 6.5 to include the beam port and guide hall experiments.
The inspector interviewed the Chair of the BES. He explained the procedure followed for experiment approval and discussed two recent experiments that were reviewed by his committee. The inspector reviewed the approval procedure and package for two recent beam experiments and noted that the BES had reviewed these experiments. The NCNR Hazards Review Committee had reviewed these experiments as well. The inspector verified that the beam experiment proposals were forwarded to the SEC for review and subsequently to the Director for approval. The inspector also noted that the approved beam experiment documentation specified certain engineering and radiation protection controls that were required to be implemented to limit radiation exposure to personnel conducting the experiments.
The inspector also interviewed the Chair of the Irradiation Subcommittee. It was noted that no new proposals dealing with experiments in the thermal shield or the pneumatic system had been forwarded to the subcommittee. The review and approval process for the Irradiation Subcommittee remained in effect. The inspector verified that any new experiments involving the thermal shield or the pneumatic system would receive a 10 CFR 50.59 review.
c.
Conclusion
The program for experiment review and approval satisfied TSs and procedural requirements.
8.
Procedures
a.
Inspection Scope (IP 69008)
The inspector reviewed the following to ensure that the requirements of TS Section 6.4 were being met concerning written procedures:
- Procedure change, review, and approval process
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- NBSR AR 5.0, Procedures and Manuals, Revision A, dated April 25, 2016
NBSR-0005-CH-00, Charter for the NCNR Safety Evaluation Committee Procedure Review Subcommittee, approval dated June 16, 2016
SEC meeting minutes for May 2016 through the present (Meeting Nos. 381 through 383)
Facility NBSR Annual Reports, for the past 2 years (as referenced in Paragraph 2 above)
b.
Observations and Findings
Written procedures for the activities listed in TS Section 6.4 were available as required. Those activities included normal reactor operations, abnormal operations, emergency conditions involving the potential or actual release of radioactivity, radiation protection, site emergency actions, and fuel handling. The inspector noted that the licensee had completed reformatting nearly all procedures associated with operation of the reactor so that they were all in a standard format. This project has required a great deal of time and effort by all the groups involved.
In 2014, the licensee established a PRS which reported to the SEC to review all the reformatted and revised procedures and any new procedures that might be developed. The inspector verified that the revised procedures were being reviewed by the SEC PRS as required. The procedures were then approved by the Chief of Reactor Operations or the Chief of Reactor Operations and Engineering as required in the TSs. The inspector also verified that the official, approved copies of reactor operations procedures were kept in the control room as stipulated.
c.
Conclusion
The procedure revision, control, and implementation program satisfied TSs requirements.
9.
a.
Inspection Scope (IP 69011)
In order to verify compliance with the NBSR Emergency Plan (E-Plan) dated December 2008 (as amended July 1, 2017), the inspector reviewed selected aspects of:
- Emergency preparedness training records for 2016 and 2017
Selected NIST reactor area inspection log sheets for the past 12 months
Assistance provided by support groups (i.e., NIST Fire Department (FD),
NIST Police Department (PD), and law enforcement officials from Montgomery County, Maryland)
Records documenting annual evacuation drills and the latest biennial emergency exercise
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- Documentation of inventories of emergency response supplies, equipment, and instrumentation
NBSR EI Manual (containing the E-Plan implementing procedures)
NBSR EI Procedure 0.2, Emergency Organization Phone Numbers
NBSR EI Procedure 0.3, Emergency Classification and Criteria
b.
Observations and Findings
The E-Plan in use at the reactor and support facilities was the same as the latest version submitted to the NRC. The E-Plan was being audited and reviewed biennially as required. It was noted that operators were required to review the emergency procedures and be cognizant of their responsibilities in case of an emergency. The inspector verified that operators were reviewing the emergency procedures and understood their duties in response to emergency conditions.
Records showed that radio communications with the NIST PD were checked weekly. Other communications capabilities were checked periodically and phone numbers for the various support organizations were verified annually, as stipulated in the TSs. The inspector conducted an onsite tour of the licensees Emergency Support Center and determined that communication equipment, radiological response supplies, and radiation detection equipment were available as stipulated.
The most recent biennial emergency exercise was conducted September 9, 2015. A critique was held following the drill to discuss those things that were done well and how to correct the problems that occurred. A biennial emergency exercise had been scheduled for October 12, 2017, but had to be postponed. A new date for the exercise had not been established to date.
Emergency preparedness and response training for NBSR personnel was being completed as required. This was accomplished through the initial training for incoming personnel and the refresher training provided for all NCNR employees.
The licensees health physics group conducted biennial emergency response training for the NIST FD and PD personnel, as well. The inspector verified that the last training for these groups had been conducted during June and July 2016.
The inspector reviewed the results of selected emergency equipment inventories required by Section 8.5 of the E-Plan. It was noted that the emergency equipment in the lockers located in the A-wing front lobby/break area, in Basement Level 2, and in the C-200 area had been inventoried monthly. The lockers were being inventoried more frequently than the TSs required (an annual inventory was required).
The inspector verified that the memorandum of understanding between Montgomery County and NIST concerning firefighting assistance, dated October 16, 2007, remained in effect.
During the inspection, the inspector and a licensee representative visited the NIST Emergency Services building which housed the PD and FD offices and the central Dispatch Center. The inspector met with a PD Lieutenant and a FD
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Captain and discussed the actions each group would take in response to an emergency at the NCNR. Each group understood their respective roles and responsibilities. There appeared to be a good working relationship between the NCNR and these support groups.
c.
Conclusion
The emergency preparedness program was being conducted in accordance with the E-Plan.
10.
Follow-up on Previously Identified Item
a.
Inspection Scope (IP 92701)
The inspector reviewed the actions taken by the licensee to address a previously identified inspector followup item (IFI) concerning facility procedures.
b.
Observation and Findings
50-184/2016-203-01 - IFI - Follow-up on licensees action to correct page 11 of the NBSR E-Plan regarding notification requirements to the NRC Operations Center, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of discovery, for an ALERT declaration involving a security breach.
During an inspection in October 2016, one inspector reviewed the NBSR E-Plan dated December 21, 2015 and found a discrepancy on page 11 regarding emergency notification to the NRC during an ALERT declaration, specifically for an event involving a security breach. This was identified by the NRC as an IFI.
During this inspection the inspector reviewed the NBSR E-Plan. It was noted that the licensee had corrected the E-Plan to require that the NRC Operations Center be notified within one hour of discovery of a security breach affecting the reactor facility. The E-Plan is now in compliance with 10 CFR Part 73 Appendix G. The appropriate implementing procedures and instructions had also been revised. This issue is considered closed.
c.
Conclusions
One IFI was reviewed. The issue is closed.
11.
Exit Interview
The inspection scope and results were summarized on October 19, 2017, with members of licensee management. The inspector described the areas inspected and discussed the inspection findings. The licensee acknowledged the findings presented and did not identify as proprietary any of the material provided to or reviewed by the inspector during the inspection.
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PARTIAL LIST OF PERSONS CONTACTED
Licensee
P. Brand Chief, Reactor Engineering and Chair, Hazards Review Committee D. Brown Senior Reactor Health Physicist, Leader, Reactor HP Group, and Chair, Irradiation Subcommittee F. Clark Reactor Supervisor/Senior Reactor Operator Director, NCNR D. Hughes Chief, Reactor Operations T. Johnston Reactor Health Physicist B. Kirby Chair of the Beam Experiment Subcommittee S. MacDavid Engineering Technician T. Newton Chief, Reactor Operations and Engineering and Deputy Director, NCNR R. Strader Quality Assurance Program Manager R. Sprow Reactor Supervisor/Senior Reactor Operator D. Wilkison Reactor Supervisor/Senior Reactor Operator R. Williams Senior Nuclear Engineer and Chair, Safety Evaluation Committee
Other Personnel
C. Clary Captain, Fire Protection Group, Emergency Services Division, Office of Facilities and Property Management, NIST A. Washington Lieutenant, Police Department, Emergency Services Division, Office of Facilities and Property Management, NIST
INSPECTION PROCEDURES USED
IP 69003:
Class I Research and Test Reactor Operator Licenses, Requalification, and Medical Activities IP 69005:
Class I Research and Test Reactors Experiments IP 69006:
Class I Research and Test Reactors Organization, Operations, and Maintenance Activities IP 69007:
Class I Research and Test Reactors Review and Audit and Design Change Functions IP 69008:
Class I Research and Test Reactor Procedures IP 69009:
Class I Research and Test Reactors Fuel Movement IP 69010:
Class I Research and Test Reactors Surveillance IP 69011:
Class I Research and Test Reactors Emergency Preparedness IP 92701 Follow-up on Open Items
ITEMS OPENED, CLOSED, AND DISCUSSED
Opened
None
Closed
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50-184/2016-203-01 IFI Follow-up on licensees action to correct page 11 of the NBSR E-Plan regarding notification requirements to the NRC Operations Center, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of discovery, for an ALERT declaration involving a security breach.
LIST OF ACRONYMS USED
10 CFR Title 10 of the Code of Federal Regulations AR
Administrative Rule BES
Beam Experiment Subcommittee ECN
Engineering Change Notice ECR
Engineering Change Request EI
Emergency Instruction E-Plan
Fire Department IFI
Inspector Follow-up Item IP
Inspection Procedure NBSR
National Bureau of Standards Reactor NCNR
NIST Center for Neutron Research NIST
National Institute of Standards and Technology No.
Number NRC
U.S. Nuclear Regulatory Commission OI
Operating Instruction PD
Police Department PRS
Procedure Review Subcommittee SAC
Safety Assessment Committee SEC
Safety Evaluation Committee SRO
Senior Reactor Operator TS
Technical Specification