IR 05000184/2020202

National Institute of Standards and Technology - U.S. Nuclear Regulatory Commission Routine Inspection Report 05000184/2020202

ML20294A485
Person / Time
Site:	National Bureau of Standards Reactor
Issue date:	01/06/2021
From:	Travis Tate NRC/NRR/DANU/UNPO
To:	Dimeo R US Dept of Commerce, National Institute of Standards & Technology (NIST)
Roche K , NRR/DANU/UNPO, 301-415-1554
References
IR 2020202
Download: ML20294A485 (18)

Text

January 6, 2021

SUBJECT:

NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY - U.S. NUCLEAR REGULATORY COMMISSION ROUTINE INSPECTION REPORT NO. 05000184/2020202

Dear Dr. Dimeo:

From September 21-24, 2020, the U.S. Nuclear Regulatory Commission (NRC) staff 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 September 24, 2020, with you, Dr. Thomas Newton, Deputy Director, and Daniel Flynn, Acting Chief of Reactor Operations.

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 inspectors 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 Kevin Roche at (301) 415-1554, or by electronic mail at Kevin.Roche@nrc.gov.

Sincerely,

/RA/

Travis L. Tate, Chief Non-Power Production and Utilization Facility Oversight Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities 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 Attention: Amber Johnson Dept. of Materials Science and Engineering University of Maryland 4418 Stadium Drive College Park, MD 20742-2115 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

ML20294A485 *concurred via e-mail NRC-002 OFFICE NRR/DANU/UNPO* NRR/DANU/UNPO* NRR/DANU/UNPO/LA* NRR/DANU/UNPO/BC*

NAME KRoche POBryan NParker TTate DATE 10/23/2020 10/21/2020 10/21/2020 01/06/2021

U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No: 50-184 License No: TR-5 Report No: 050000184/2020202 Licensee: National Institute of Standards and Technology Facility: Center for Neutron Research National Bureau of Standards Reactor Location: Gaithersburg, MD Dates: September 21-24, 2020 Inspector: Kevin Roche Phil OBryan Approved by: Travis L. Tate, Chief Non-Power Production and Utilization Facility Oversight Branch Division of Advanced Reactors and Non-Power Production and Utilization Facilities Office of Nuclear Reactor Regulation Enclosure

EXECUTIVE SUMMARY National Institute of Standards and Technology Center for Neutron Research National Bureau of Standards Test Reactor Inspection Report No. 05000184/2020202 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 megawatts test reactor facility safety program including: (1) operator licenses, requalification, and medical examinations; (2) experiments; (3) organization and operations and maintenance activities; (4) review and audit and design change functions; (5) procedures; (6) fuel movement; (7) surveillance; and, (8) emergency preparedness since the last U.S.

Nuclear Regulatory Commission (NRC) inspection of these areas. The inspectors determined that the licensees safety program was acceptably directed toward the protection of public health and safety and met NRC requirements. The inspectors did not identify any violations or deviations.

Operator Licenses, Requalification, and Medical Examinations

• Operator requalification was conducted and completed as required by the requalification program.

Experiments

• The program for experiment review and approval satisfied technical specification (TS) and procedural requirements.

Organization and Operations and Maintenance

• The established organization was consistent with TS Section 6.1 requirements.

• The operations and maintenance programs were conducted in accordance with applicable procedural requirements.

Review and Audit and Design Change Functions

• The licensee established and conducted review and audit functions consistent with TS requirements and the licensee administrative controls.

• The design change program implemented at the facility satisfied NRC requirements and licensee procedures and Title 10 of the Code of Federal Regulations (10 CFR) 50.59, Changes, tests and experiments.

Procedures

• The procedure revision, control, and implementation program satisfied TS requirements.

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Fuel Movement

• Fuel movement and handling was accomplished in accordance with TS and procedural requirements.

Surveillance

• The surveillance program was completed in a timely manner and as specified in the facilitys TSs.

Emergency Preparedness

• The licensee maintained the emergency preparedness program in a state of readiness in accordance with licensee procedures and NRC requirements.

• The implementation and changes to the emergency preparedness program met regulatory requirements and licensee commitments.

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REPORT DETAILS Summary of Facility Status The National Institute of Standards and Technology (NIST), Center for Neutron Research (NCNR) reactor, a 20 megawatts test reactor commonly known as the National Bureau of Standards Reactor (NBSR), continued to operate in support of laboratory experiments and various types of research.

1. Operator Licenses, Requalification, and Medical Examinations a. Inspection Scope (Inspection Procedure (IP) 69003)

To verify compliance with the operator requalification program for the NBSR, which was last updated March 2009, the inspectors reviewed:

• medical examination records from 2019 through 2020

• current status of selected qualified operators licenses

• NBSR requalification (biennial) examinations for 2019 through 2020

• training provided to the operators during the NBSR 2018-2019 and 2020-2021 requalification training cycles

• operator training records for the years 2019, and 2020 to date, documented on forms entitled, Requalification Program Documentation Review and Reactivity Changes

• supervisors annual operator evaluations documented on forms entitled, Operator Evaluation b. Observations and Findings The inspectors noted that there were 18 qualified and 17 active senior reactor operators (SROs) employed at the facility. In addition, the inspectors noted that there were currently six SRO candidates in training awaiting exam results, and seven recently hired candidates. Through a review of various requalification and training documents, the inspectors verified that the facility SROs licenses were active, and the licensee maintained records of the licensed operators requalification status as required by regulations.

The inspectors also found that operator training was consistent with the NBSR requalification program requirements. The inspectors verified that facility operators completed the requalification training and taken the written biennial requalification examinations. The inspectors reviewed NBSR console logbooks and requalification records to verify that operators maintained active duty status by participating in the reactivity manipulations and document reviews as outlined and required in the requalification program. The inspectors also confirmed that the operators were given annual operating evaluations as required by regulations. Furthermore, the inspectors verified that the qualified operators received the required physical examination every 2 years as well. However, some physicals were delayed because of the Coronavirus Disease 2019 pandemic. The licensee either requested an exemption to allow operators to-4-

remain active or has not allowed operators not meeting requirements to perform licensed activities.

c. Conclusion The inspectors concluded that the licensee conducted the operator requalification as required by regulations and the licensees requalification program.

2. Experiments a. Inspection Scope (IP 69005)

To ensure that the requirements of TS Sections 3.8, 4.8, and 6.5, and administrative procedures were met governing the licensees program for conducting experiments, the inspectors reviewed selected aspects and/or portions of:

• beam experiment subcommittee reports to the NCNR safety evaluation committee (SEC) during meetings held in 2019 and to date in 2020 - In SEC meeting notes

• experimental control procedures summary notebook containing experiments involving 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 as well as a list of authorized users

• experimental proposal approval sheet for No. 682.03.080, Move of the FUND Detector from NG6u to NG6a dated November 17, 2019 b. Observations and Findings Experiments performed at the NBSR included: (1) irradiation experiments and (2)

beam experiments. Irradiation experiments were those conducted in a pneumatic tube or in any of the other NBSR irradiation facilities 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.

The inspectors reviewed the package for a recently approved beam experiment.

The inspectors also noted that the approved beam experiment documentation outlined specific engineering and radiation protection controls that were required to be implemented to limit radiation exposure to, and ensure the safety of, personnel conducting the experiments.

The inspectors determined that the sampled experiments were completed with the cognizance of the reactor operators on duty and in compliance with the applicable procedural precautions and controls and in accordance with requirements in the TS.

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c. Conclusion The inspectors determined that the program for experiment review and approval satisfied TSs and procedural requirements.

3. Organization and Operations and Maintenance Activities a. Inspection Scope (IP 69006)

To verify that the licensee complied with the organizational and staffing requirements specified in NBSR TS Section 6.1; and complied with operating requirements in TS Sections 2.0, 3.0, and procedural requirements; and, to ensure that maintenance activities were completed; the inspectors reviewed selected aspects of the following:

• current NCNR organization and staffing

• NBSR reactor shift supervisor Logbook No. 44

• reactor console logbooks Nos. 167 through 170

• management and staff responsibilities outlined in the TSs

• selected reactor operations shift turnover log notebook entries

• NBSR administrative rules (AR) 1.0, Conduct of Operations, Revision B

• NBSR AR 2.0, Personnel Requirements, Revision B

• NBSR AR 9.0, Reactor Startup and Operation, Revision A

• selected NBSR operating instructions (OIs) (i.e., operating procedures)

• selected Non-TS maintenance schedules for each month for the period from October 2019 to present, which indicated what maintenance activities were due for completion during that month

• NBSR emergency instruction (EI) 0.2, Emergency Organization and Phone Numbers, listing emergency contact information for reactor operations personnel, dated July 24, 2019

• operations report No. 72, NBSR Annual Report, for the period from January 1, 2019, through December 31, 2019, issued April 2, 2020 b. Observations and Findings (1) Organization The inspectors found that the licensees organizational structure remained consistent with the requirements of TS Section 6.1 and Figure 6.1. The inspectors found that the various management and supervisory personnel in the Reactor Operations Group met or exceeded the minimum qualifications specified in the TSs. The Chief of Reactor Operations recently resigned. The acting Chief of Reactor Operations meets the requirements outlined in the TS.

In discussing staffing with management personnel, the inspectors determined that there were 18 qualified SROs at the facility (as noted above) who were assigned to the various operating crews, or in management positions, or working in the Reactor Engineering group.

Through interviews with operations personnel, the inspectors determined-6-

that there were four operating crews at the facility who worked rotating shifts. Additionally, there was a fifth day shift crew composed of individuals who normally only worked during the weekdays, but also provided coverage on occasion when individuals from the other crews were unavailable. Each crew was typically staffed with three individuals who were licensed SROs. New hires, while in operator training, were also assigned to one of the four crews.

Through a review of selected entries in the console logbooks for the period from September 2019 to the present, and through observations of operations crew personnel, the inspectors verified that staffing during routine reactor operation was as required and; therefore, was adequate.

It was also noted that a list of reactor facility personnel by name and telephone number was available to the 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 March 2020.

(2) Operations The inspectors reviewed logs and related records and found that the licensee conducted reactor operations in accordance with facility procedures and TS as required. The inspectors found that the logs and records were clear and provided an indication of ongoing activities. The inspectors also verified that shift staffing during reactor operation was maintained as required by TS 6.1.3.

The inspectors also verified that shift turnover briefings were held prior to each shift change. Activities of the previous shift, and events or job evolutions scheduled for the upcoming shift, were discussed in detail.

Operators maintain a status board in the Control Room to ensure all operators were aware of ongoing work and current plant conditions.

(3) Maintenance The inspectors reviewed various maintenance records, console logbooks, and data sheets and determined that the licensee conducted routine maintenance activities at the required frequency and in accordance with the applicable procedure or equipment manual. The inspectors verified that the licensee included major preventative and corrective maintenance operations having safety significance in the facility Annual Reports submitted to the NRC as required by TS 6.7.1(3).

c. Conclusion The inspectors found that the established organization was consistent with TS 6.1 requirements. Inspectors also determined that operations were conducted in accordance with procedures and TS, and the maintenance program was conducted and documented as required by procedure.

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4. Review and Audit and Design Change Functions a. Inspection Scope (IP 69007)

The inspectors reviewed the following to ensure that the requirements of TS Section 6.2 and 10 CFR 50.59 were implemented effectively:

• NBSR Procedure No. NBSR-0007-DOC-04, Engineering Manual, Revision 4, which included procedures and instructions for completing changes at the facility

• NBSR-0003-DOC-06, Guidelines for Completing Engineering Changes, Revision 6

• NBSR Engineering Change Request/Engineering Change Notice (ECR/ECN)

No. 1117, Relocate Shim Arm Control Wiring, Revision 2

• NBSR ECR/ECN No. 1012, Mercury Wetted Relay Replacement Project, Revision 0

• NBSR ECR/ECN No. 1133, Remove Failing Indication on 5K Hot Waste Tanks, Revision A

• NBSR ECR/ECN No. 1096, Addition of Numerical Identification to Annunciator Panel, Revision 0

• operations report No. 72, NBSR Annual Report, for the period from January 1, 2019, through December 31, 2019, issued April 2, 2020 b. Observations and Findings (1) Design Change Functions The inspectors reviewed selected requests for changes to the facility (i.e., changes to structures, systems, and components (SSCs)) that were proposed and/or closed out within the last year. At NIST these change proposals were designated as ECRs. Each ECR documented what was proposed to be changed, the 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 a 10 CFR 50.59 review would be required. Based on the safety significance and the results of the 10 CFR 50.59 screens, 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, the associated ECN was implemented 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.

The inspectors reviewed selected ECRs and ECNs to determined that facility changes were acceptably documented and reviewed in-8-

accordance with NRC requirements and the licensees guidelines. The inspectors noted that the changes were tracked to completion by the licensee.

c. Conclusion The inspectors concluded that the licensees design change program satisfied both licensee and NRC requirements.

5. Procedures a. Inspection Scope (IP 69008)

The inspectors reviewed the following to ensure that the requirements of TS Section 6.4 concerning written procedures were met:

• NBSR AR 5.0, Procedures and Manuals, Revision A

• NBSR-0005-CH-02, Charter for the NCNR Safety Evaluation Committee Procedure Review Subcommittee, approval dated August 19, 2020

• NCNR SEC meeting minutes for Fall of 2019 through the present (Meeting Nos. 389 and 390)

• operations report No. 72, NBSR Annual Report, for the period from January 1, 2019, through December 31, 2019, issued April 2, 2020 b. Observations and Findings The inspectors found that 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 inspectors noted that the licensee completed revising and reformatting all procedures associated with operation of the reactor so that they were all in a standard format.

The procedures review subcommittee (PRS), which was initially established in 2014, was created to review new procedures and substantive changes to existing ones. The inspectors verified that new and revised procedures were reviewed by the SEC PRS as required by TSs. The procedures were then forwarded for review and approval to the Chief of Reactor Operations or the Chief of Reactor Operations and Engineering as required in the TSs. The inspectors also verified that the official, approved copies of reactor operations procedures were kept in the control room as stipulated.

c. Conclusion The inspectors determined the procedure revision, control, and implementation program satisfied TS requirements.

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6. Fuel Movement a. Inspection Scope (IP 69009)

The inspectors reviewed selected aspects of the following to verify that fuel movement and handling was conducted as required by TS Sections 3.9 and 5.3:

• reactor console logbooks Nos. 167 through 170

• NBSR reactor shift supervisor logbook No. 44

• Core reload/refuel and core defuel/refuel verification and sign-off sheets for core Nos. 649 through 652 which were completed to ensure accurate records were maintained in the control room, at the reactor top, and in the storage pool room

• NBSR OI 6.1, Fueling and Defueling Procedures, Revision E

• NBSR OI 6.2, Operation of Fuel Transfer System, Revision M

• NBSR OI 3.3, Operation of the Storage Pool Cooling System, Revision C b. Observations and Findings The inspectors verified that the 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. Various other records of fuel loading/reloading and fuel examination documented that fuel was moved and controlled as required by procedures. The inspectors found that the records also showed that operators verified the fuel movements by assigned individuals as required and that fuel elements were maintained in the authorized and specifically designated locations.

c. Conclusion The inspectors concluded that the licensee maintained and followed procedures which effectively implemented TS requirements for fuel handling.

7. Surveillance a. Inspection Scope (IP 69010)

To determine that surveillance activities and calibrations were completed as required by TS Section 4.0, the inspectors reviewed selected aspects of:

• reactor console logbooks Nos. 167 through 170

• selected TS surveillance schedules for each month for the period from October 2019 to present, which indicated what 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

• OI 1.1 CL-A, Reactor Startup Checklist (Shutdown >24 hours), Revision M

• OI 1.1 CL-B, Reactor Startup Checklist (Shutdown <24 hours), Revision A

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b. Observations and Findings The inspectors 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 TS Surveillance Schedule, which was revised and updated as the tasks were completed. A new surveillance schedule was issued monthly. The inspectors reviewed the monthly surveillance schedules, console logbooks, and related data recorded on the appropriate forms and found that the licensee completed surveillances and calibrations 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. The inspectors determined that all results reviewed by the inspectors were within TSs or procedurally prescribed parameters.

c. Conclusion The inspectors concluded that the surveillance program was conducted as specified by TS requirements.

8. Emergency Preparedness 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 inspectors reviewed selected aspects of:

• selected NIST reactor area inspection log sheets for the past 12 months

• records documenting the latest biennial emergency exercise

• 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

• NSBR EI Procedure 4.4, Emergency Equipment b. Observations and Findings The inspectors found that the E-Plan in use at the reactor and support facilities was the same as the latest version submitted to the NRC. The inspectors verified that the licensee audited the E-Plan biennially as required. The inspectors noted that operators were required to review the emergency procedures and be cognizant of their responsibilities in case of an emergency.

Communications capabilities were checked periodically and phone numbers for the various support organizations were verified annually. The inspectors conducted an onsite tour of the licensees Emergency Support Center and

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determined that communication equipment, radiological response supplies, and radiation detection equipment were available as stipulated in the E-Plan.

The inspectors found the most recent biennial emergency exercise was conducted July 2020. Because of the ongoing pandemic, the exercise was held as a table-top discussion. A critique was held following the exercise to discuss those things that were done well and how to correct the problems that occurred.

The inspectors also noted that evacuation drills were conducted annually as required in the E-Plan. The inspectors determined emergency preparedness and response training for NBSR operators was completed as required.

The inspectors 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 was inventoried annually.

c. Conclusion The inspectors concluded that the emergency preparedness program was conducted in accordance with the E-Plan.

9. Exit Interview The inspection scope and results were summarized on September 24, 2020, with members of licensee management. The inspectors described the areas inspected. The licensee did not identify as proprietary any of the material provided to or reviewed by the inspectors during the inspection.

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PARTIAL LIST OF PERSONS CONTACTED Licensee D. Flynn Deputy Chief, Reactor Operations D. Griffin Security Specialist J. Hudson Senior Reactor Operator M Schwaderer Chief, Reactor Operations Acting Director, NCNR R. Strader Quality Assurance Program Manager S. Dewey Chief, NCNR Health Physics T. Newton Chief, Reactor Operations and Engineering; and, Deputy Director, NCNR INSPECTION PROCEDURES USED IP 69003: Class I Research and Test Reactor Operator Licenses, Requalification, and Medical Examinations IP 69005: Class I Research and Test Reactors Experiments IP 69006: Class I Research and Test Reactors Organization and 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 ITEMS OPENED, CLOSED, AND DISCUSSED Opened None Closed None LIST OF ACRONYMS USED 10 CFR Title 10 of the Code of Federal Regulations AR Administrative Rule ECN Engineering Change Notice ECR Engineering Change Request EI Emergency Instruction E-Plan Emergency Plan IP Inspection Procedure NBSR National Bureau of Standards Reactor NCNR NIST Center for Neutron Research NIST National Institute of Standards and Technology NRC U.S. Nuclear Regulatory Commission OI Operating Instruction Attachment

PRS Procedure Review Subcommittee SEC Safety Evaluation Committee SRO Senior Reactor Operator SSCs Structures, Systems, and Components TS Technical Specification-2-