IR 05000083/2020202

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University of Florida - U.S. Nuclear Regulatory Commission Routine Safety Inspection Report No. 05000083/2020202
ML20349A142
Person / Time
Site: 05000083
Issue date: 02/09/2021
From: Travis Tate
NRC/NRR/DANU/UNPO
To: Wall D
Univ Of Florida, Gainesville
O'Bryan P, NRR/DANU/UNPO, 301-415-0266
References
IR 2020202
Download: ML20349A142 (15)


Text

February 9, 2021

SUBJECT:

UNIVERSITY OF FLORIDA - U.S. NUCLEAR REGULATORY COMMISSION ROUTINE SAFETY INSPECTION REPORT NO. 05000083/2020202

Dear Dr. Wall:

From November 30 - December 2, 2020, the U.S. Nuclear Regulatory Commission (NRC) staff conducted a routine safety inspection at your University of Florida Training Reactor facility. The inspection results were discussed with you and members of your staff on December 2, 2020.

The enclosed report documents the inspection results.

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

The inspector reviewed selective procedures and records, observed various activities, and interviewed personnel. Based on the results of this inspection, no findings of significance were identified. No response to this letter is required.

In accordance with Title 10 of the Code of Federal Regulations Section 2.390, Public inspections, exemptions, requests for withholding, a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRCs document system (Agencywide 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). Should you have any questions concerning this inspection, please contact Mr. Phil OBryan at (301) 415-0266, or electronic mail at Phil.OBryan@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.50-083 License No. R-56 Enclosure:

As stated cc: w/enclosure: See next page

University of Florida Docket No.50-083 Administrator Department of Environmental Regulation Power Plant of Siting Section State of Florida 2600 Blair Stone Road Tallahassee, FL 32301 State Planning and Development Clearinghouse Office of Planning and Budgeting Executive Office of the Governor The Capitol Building Tallahassee, FL 32301 Chief, Bureau of Radiation Control Department of Health 4052 Bald Cypress Way Tallahassee, FL 32399-1741 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 Brian Shea, Reactor Manager University of Florida 212 Nuclear Science Building Gainesville, FL 32611-8300 Dean Cammy Abernathy University of Florida College of Engineering PO Box 116550 Gainesville, FL 32611

ML20349A142 NRC-002 OFFICE NRR/DANU/UNPO/PM NRR/DANU/UNPO/LA NRR/DANU/UNPO/BC NAME POBryan NParker TTate DATE 12/14/2020 12/14/2020 2/9/2021

U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No.: 50-083 License No.: R-56 Report No.: 05000083/2020202 Licensee: University of Florida Facility: University of Florida Training Reactor Location: Gainesville, Florida Dates: November 30 - December 2, 2020 Inspector: 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 University of Florida University of Florida Training Reactor Inspection Report No. 05000083/2020202 The primary focus of this routine safety inspection was the on-site review of selected aspects of the licensees Class II research reactor facility safety program including: (1) health physics; (2) design changes; (3) committees, audits and reviews; (4) emergency planning; (5) maintenance; (6) fuel handling; and (7) transportation activities. The U.S. Nuclear Regulatory Commission (NRC) staff determined that the licensees program is acceptably directed toward the protection of public health and safety, and complies with NRC requirements.

Health Physics

  • The inspector found that training, surveys, postings, and personnel dosimetry met regulatory requirements.
  • The inspector found that radiation monitoring equipment was maintained and calibrated as required by technical specifications (TSs).
  • The inspector found that calculations of effluents released from the facility met license and regulatory requirements, and releases were within the specified regulatory limits.

Design Changes

  • The inspector found that changes to the facility were evaluated using the criteria specified in Title 10 of the Code of Federal Regulations (10 CFR) 50.59, Changes, tests and experiments, and were reviewed and approved by the Reactor Safety Review Subcommittee (RSRS) as required by TS.

Committees, Audits and Reviews

  • The inspector found that the review, audit and oversight functions required by TSs were acceptably completed by the RSRS.

Emergency Planning

Maintenance Logs and Records

  • The inspector found that the maintenance logs, records, reviews, and performance satisfied TS and procedure requirements.

Fuel Handling Logs and Records

  • The inspector found that no fuel handling operations or inspection activities were performed or required since the last NRC inspection of this program area.

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Transportation Activities

  • The inspector found that the program for shipping radioactive material satisfied regulatory requirements.

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REPORT DETAILS Summary of Facility Status The University of Florida Training Reactor (UFTR) 100-kilowatt Argonaut research reactor operates in support of experiments, reactor operator training, and periodic equipment surveillances. During the inspection, the reactor was shut down.

1. Health Physics a. Inspection Scope (Inspection Procedure (IP) 69001, Section 02.07)

The inspector reviewed the following to verify compliance with 10 CFR Part 19, Notices, Instructions and Reports to Workers: Inspection and Investigations, 10 CFR Part 20, Standards for Protection against Radiation, and the applicable TS requirements:

  • radiological signs and posting in various areas of the facility
  • radiation protection training records
  • maintenance and calibration of radiation monitoring equipment, including the water radioactivity monitor, area radiation monitors, the stack radiation monitor, and the continuous air monitor
  • UFTR dosimeter and visitor log
  • UFTR dosimetry reports for 2019 and 2020
  • UFTR radiation and contamination survey records for 2019 and 2020
  • Ar-41 release surveillance records for 2019 and 2020
  • UFTR radiation work permits 2019 and 2020
  • UFTR operating logs and procedures b. Observations and Findings (1) Surveys The inspectors review of radiation and contamination survey records found that surveys were completed as required by procedures and in accordance with the requirements in Subpart F, Surveys and Monitoring, to 10 CFR Part 20.

(2) Postings and Notices The inspector toured the facility and observed that signage, posting, and labels were used in accordance with requirements in Subpart J, Precautionary Procedures, to 10 CFR Part 20. The inspector found that radioactive material storage areas were properly posted and no unmarked radioactive material was detected in the facility. The inspector noted that copies of notices to workers were posted in the facility, including a copy of the most recent revision of NRC Form 3, Notice to Employees, as required by 10 CFR 19.11, Posting of notices to workers.

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(3) Dosimetry The inspector determined that the licensee monitors individuals in accordance with the requirements in 10 CFR 20.1502, Conditions requiring individual monitoring of external and internal occupational dose.

An examination by the inspector of the dosimetry records for the past 2 years showed that the highest occupational doses were within 10 CFR 20, Subpart C, Occupational Dose Limits, limits and licensee action levels.

The inspector verified that NRC Form 5 or equivalent reports, as required by 10 CFR 19.13, Notifications and reports to individuals, were completed and provided to each employee who received exposure at the facility during 2019 and 2020.

(4) Radiation Monitoring Equipment The inspector reviewed the records of selected meters, detectors, and air monitoring equipment in use at the facility. The inspector found that calibrations and test frequency of the portable and fixed meters and monitors were consistent with manufacturers recommendations and appropriate calibration records were maintained.

The inspector observed storage and use of portable survey instrumentation at the facility. Portable survey instrumentation capable of measuring beta, gamma, and neutron exposure and dose rates were available and operable.

(5) Radiation Protection Training The inspector reviewed documentation of radiation protection training given to staff and facility users. The inspector found that content of the training program satisfied the requirements in 10 CFR 19.12, Instruction to workers.

(6) Radiation Protection Program The inspector found that the licensees radiation protection program was established and reviewed. The annual UFTR audit verified that the radiation protection program at the facility was conducted as required by the applicable procedures. No deficiencies related to the radiation protection program at UFTR were identified during audits of the program.

(7) ALARA Policy The inspector found that a policy for maintaining radioactive exposure to personnel as low as reasonably achievable (ALARA) was outlined and established in the UFTR procedures. The policy discussed and set expectations for keeping doses ALARA, including local action levels for personnel radiation exposure doses, consistent with the requirements in 10 CFR 20.1101, Radiation protection programs.

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(8) Environmental Monitoring and Effluents The inspectors review of the area radiation monitors and the gaseous effluent (stack) monitor calibration records found that these systems were calibrated and tested in accordance with the TS requirements.

The inspector reviewed the records documenting solid, liquid, and airborne releases to the environment. No releases of solid radioactive material to the environment occurred. There were no liquid releases from operation of UFTR in 2019 or 2020. The inspector determined that gaseous release activity was calculated, and the results were documented. The inspector found releases of activity were in concentrations below the concentration limits specified in Appendix B to 10 CFR Part 20, Annual Limits on intake (ALIs) and Derived Air Concentrations (DACs) of Radionuclides for Occupational Exposure; Effluent Concentrations; Concentrations for Release to Sewerage. The highest calculated dose that could be received by a member of the public as a result of gaseous emissions from reactor operations was determined by the inspector to be below the requirements of 10 CFR 20.1101(d).

The inspector verified the environmental gamma radiation monitoring was conducted using dosimetry in accordance with the applicable procedures.

The inspector found that the data indicated that there were no radiation doses in uncontrolled areas from operation of the reactor that would result in a member of the public exceeding the limits in Subpart D, Radiation Dose Limits for Individual Members of the Public, to 10 CFR Part 20.

c. Conclusion The inspector found that surveys were completed and documented in accordance with facility procedures and TS, postings met regulatory requirements, personnel dosimetry was worn as required, and doses were within regulatory limits. The inspector also determined that radiation monitoring equipment was maintained and calibrated as required by procedures. Radiation protection training was provided to facility personnel. Calculations of effluents released from the facility satisfied license and regulatory requirements and releases were determined to be within the specified regulatory limits.

2. Design Changes a. Inspection Scope (IP 69001, Section 02.08)

The inspector reviewed the following documents to verify compliance with 10 CFR 50.59 and TS requirements for design changes:

  • RSRS meeting minutes for 2019 and 2020
  • UFTR Annual Reports for 2019 and 2020
  • UFTR Operating Procedure 0.4, 10 CFR 50.59 Screening and Evaluation
  • modification screening forms for 2019 and 2020
  • 10 CFR 50.59 evaluations and design change packages for 2019 and 2020-6-

b. Observations and Findings The inspector reviewed the 10 CFR 50.59 evaluations and corresponding design change packages and found that they contained supporting information and evaluations for the modifications to satisfy the regulatory requirements.

Additionally, the inspector found that the modifications were reviewed and approved by the RSRS.

c. Conclusion The inspector found that changes to the facility were evaluated using the 10 CFR 50.59 criteria and were reviewed and approved by the RSRS as required.

3. Committees, Audits and Review a. Inspection Scope (IP 69001, Section 02.09)

The inspector reviewed the following to ensure that the audits and reviews stipulated in TS Section 6.2 were completed:

  • membership of the UFTR RSRS
  • UFTR RSRS meeting minutes for 2019 and 2020
  • UFTR Annual Reports for 2018 and 2019
  • UFTR annual audits for 2018 and 2019 b. Observations and Findings The inspectors review verified that the RSRS met at least annually as required by Section 6.2.2 of the facility TS.

The inspector found that since the last inspection, all required audits of reactor facility activities and reviews of programs, procedures, equipment, and proposed tests or experiments were completed and documented as required. The audits were completed by designated individuals and reviewed by the RSRS.

c. Conclusion The inspector found that RSRSs review and audit program was conducted as required by the TS.

4. Emergency Planning a. Inspection Scope (IP 69001, Section 02.10)

The inspector reviewed selected aspects of the following to verify compliance with the UFTR EP:

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  • EP audits for 2018 and 2019
  • memorandum of understanding (MOU) with Alachua County Emergency Management
  • MOU with the University of Florida Department of Emergency Medicine
  • emergency supplies and equipment
  • emergency procedures
  • emergency drills for 2019 and 2020
  • training records for licensee staff and support personnel
  • American National Standards Institute/American Nuclear Society (ANSI/ANS)-15.16, Emergency Planning for Research Reactors.

b. Observations and Findings (1) Observations The inspector found that EP training was conducted, drills were performed, emergency response call lists were maintained and posted, emergency equipment was maintained and available, and that MOUs were established with outside organizations as required by the EP and implemented procedures.

(2) Inspector Follow-up Item As stated in Section 1.2 of the UFTR EP, the UFTR EP is based on ANSI/ANS 15.16. The inspector found the UFTR emergency response organization (ERO) is defined by Figure 3.1 of the UFTR EP and is consistent with ANSI/ANS-15.16. However, the inspector determined that there is an inconsistency in the UFTR EP in that Section 3.5 of the UFTR EP may be interpreted to require that one or more reactor operators are available when reactor experiments are in progress or during fuel handling operations. The inspector found that UFTR met TS organizational requirements and the ERO requirements of Figure 3.1 of the UFTR EP. The inspector found that the UFTR EP should be revised to eliminate the inconsistency regarding the ERO.

c. Conclusion The inspector determined the emergency preparedness program was conducted in accordance with the EP.

5. Maintenance Logs and Records a. Inspection Scope (IP 69001, Section 02.11)

To verify that the licensees operational and maintenance activities are conducted in accordance with regulatory and TS requirements, the inspector reviewed selected aspects of:

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  • UFTR maintenance log
  • UFTR Annual Reports for 2018 and 2019
  • UFTR surveillance records b. Observations and Findings The inspector observed that routine and preventive maintenance was controlled and documented in the appropriate logs.

c. Conclusion The inspector determined the licensees maintenance program is conducted and documented in accordance with TS and licensee procedure requirements.

6. Fuel Handling Logs and Records a. Inspection Scope (IP 69001, Section 02.12)

To ensure that the licensee was following the requirements specified in TS 3.9.2 and TS 5.3, the inspector reviewed fuel handling and training records for 2019 and 2020 to date.

b. Observations and Findings The inspector found that no fuel handling activities were performed since the last NRC inspection of this program area.

c. Conclusion The inspector determined that no fuel handling activities were performed since the last NRC inspection of this program area.

7. Transportation Activities a. Inspection Scope (IP 86740)

To verify compliance with regulatory and procedural requirements for transferring or shipping licensed radioactive material, the inspector reviewed UFTR radioactive material shipping and transfer records for 2019 and 2020 to date.

b. Observations and Findings Through records review and discussions with licensee personnel, the inspector found that no shipments of radioactive material occurred since the last NRC inspection.

c. Conclusion The inspector determined that no radioactive material shipments were made under the reactor license since the last NRC inspection.

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8. Exit Interview The inspector presented the inspection results to licensee management at the conclusion of the inspection on December 2, 2020. The inspector described the areas inspected and discussed in detail the inspection findings.

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PARTIAL LIST OF PERSONS CONTACTED Licensee B. Shea Reactor Manager Facility Director INSPECTION PROCEDURES USED IP 69001 Class II Non-Power Reactors ITEMS OPENED, CLOSED, AND DISCUSSED Opened:

IFI 05000083/2020202-01 Emergency Plan Inconsistency Associated with the Emergency Response Organization.

Closed:

None Discussed:

None Attachment