IR 05000005/2021201
| ML21223A146 | |
| Person / Time | |
|---|---|
| Site: | Pennsylvania State University |
| Issue date: | 08/31/2021 |
| From: | Travis Tate NRC/NRR/DANU/UNPO |
| To: | Unlu K Pennsylvania State Univ |
| Balazik M | |
| References | |
| IR 2021201 | |
| Download: ML21223A146 (16) | |
Text
SUBJECT:
PENNSYLVANIA STATE UNIVERSITY - U.S. NUCLEAR REGULATORY COMMISSION SAFETY INSPECTION REPORT NO. 05000005/2021201
Dear Dr. Unlu:
From July 26 - 29, 2021, the U.S. Nuclear Regulatory Commission (NRC) staff conducted a routine safety inspection at the Penn State Breazeale Reactor facility. The enclosed report documents the inspection results, which were discussed on July 29, 2021, with Dr. Jeffery Geuther, Associate Director for Operations, Dr. Yuanqing Guo, Radiation Safety Officer, and Dr.
Anthony Atchley, Senior Associate Dean of Engineering.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspector reviewed selected procedures and records, observed 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 NRCs document system (Agencywide Documents Access and Management System (ADAMS)). ADAMS is accessible from the NRC Web site at https://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
August 31, 2021 Should you have any questions concerning this inspection, please contact Michael Balazik at (301) 415-2856, or by electronic mail at Michael.Balazik@nrc.gov.
Sincerely, 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.50-005 License No. R-2 Enclosure:
As stated cc: See next page Signed by Tate, Travis on 08/31/21
Pennsylvania State University Docket No.50-005 cc:
Yuanqing Guo Manager of Radiation Protection The Pennsylvania State University 0201 Academic Project Bldg University Park, PA 16802 Dr. Lora Weiss Senior Vice President for Research The Pennsylvania State University 304 Old Main University Park, PA 16802 Director, Bureau of Radiation Protection Department of Environmental Protection P.O. Box 8469 Harrisburg, PA 17105 Test, Research and Training Reactor Newsletter Attention: Ms. Amber Johnson Dept of Materials Science and Engineering University of Maryland 4418 Stadium Drive College Park, MD 20742-2115 Dr. Jeffrey Geuther Associate Director for Operations Radiation Science & Engineering Center 104 Breazeale Nuclear Reactor Building University Park, PA 16802-1504
ML21223A146 NRC-002 OFFICE NRR/DANU/UNPL/RI NRR/DANU/UNPO/LA NRR/DANU/UNPO/BC NAME MBalazik NParker TTate DATE 8/11/2021 8/11/2021 8/31/2021
Enclosure U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No.:
50-005 License No.:
R-2 Report No.:
05000005/2021201 Licensee:
Pennsylvania State University Facility:
Penn State Breazeale Reactor Location:
State College, PA Dates:
July 26-29, 2021 Inspector:
Michael F. Balazik Accompanied by:
Molly-Kate E. Gavello 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
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EXECUTIVE SUMMARY Pennsylvania State University Penn State Breazeale Reactor Inspection Report No. 05000005/2021201 The primary focus of this routine, announced safety inspection included the on-site review of selected aspects of the Pennsylvania State University (PSU, the licensee) Class II research reactor facility program, including: (1) procedures; (2) experiments; (3) health physics; (4) design changes; (5) committees, audits and reviews; and (6) transportation activities. The U.S. Nuclear Regulatory Commission (NRC) staff determined the licensees program was acceptably directed toward the protection of public health and safety, and in compliance with NRC requirements.
Procedures
The inspector found that procedural review, revision, control, and implementation satisfied technical specification (TS) requirements.
Experiments
The inspector found that the program for reviewing, approving, and conducting experiments satisfied TS and procedural requirements.
Health Physics
The inspector found that radiation surveys were completed and documented in accordance with the radiation protection program and satisfied regulations.
The inspector found that postings met regulatory requirements.
The inspector found that personnel dosimetry was worn as required by regulations and doses were within regulatory limits.
The inspector found that radiation monitoring equipment was maintained and calibrated as required by TS.
The inspector found that radiation protection training was provided to facility personnel in accordance with the radiation protection program.
Calculations of effluents released from the facility satisfied license and regulatory requirements and releases were within the specified regulatory limits.
Design Changes
The inspector found that the review, evaluation, and documentation of changes to the facility satisfied NRC and TS requirements.
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Committees, Audits and Reviews
The inspector found that the review, audit, and oversight functions required by the TS were acceptably completed by the Reactor Safeguards Committee (RSC).
The inspector found that the RSC met as required by TSs.
Transportation Activities
The inspector found that radioactive material was shipped in accordance with the applicable regulations.
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REPORT DETAILS Summary of Facility Status The PSU continues to operate the Penn State Breazeale Reactor (PSBR), a 1-megawatt TRIGA (Training, Research, Isotopes, General Atomics) research reactor in support of education, research, and service.
1.
Procedures a.
Inspection Scope (Inspection Procedure (IP) 69001, Section 02.03)
To verify compliance with the licensees TS requirements for procedures, the inspector reviewed selected aspects of the licensees program, including:
Technical Specifications for Pennsylvania State University Breazeale Reactor, dated November 2009 up to Amendment No. 40
Annual Operating Report for the PSBR for the period of July 1, 2018, through June 30, 2019
Annual Operating Report for the PSBR for the period of July 1, 2019, through June 30, 2020
select administrative procedures (AP), standard operating procedures (SOP),
checks and calibration procedures (CCP), auxiliary operating procedures (AOP), and special procedures (SP)
RSC meeting minutes from June 2019 to March 2021 b.
Observations and Findings The inspector reviewed various completed facility procedures and observed facility personnel following procedures to complete tasks, such as SOP-2, Daily Checkout Procedure, Revision 28. The inspector found that the procedures were developed and approved in accordance with TS 6.3, Operating Procedures, and were of acceptable clarity and detail. The procedures were also revised, reviewed, and approved in accordance with CCP-18, Review of Procedures, and the inspector verified the training of operators on the new and revised procedures. The inspector verified that procedures in use were current and approved versions.
c.
Conclusion The inspector found that procedural review, revision, control, and implementation satisfied TS requirements.
2.
Experiments a.
Inspection Scope (IP 69001, Section 02.06)
To verify compliance with the licensees TS requirements for experiments, the inspector reviewed selected aspects of the licensees program, including:
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Technical Specifications for Pennsylvania State University Breazeale Reactor, dated November 2009 up to Amendment No. 40
Annual Operating Report for the PSBR for the period of July 1, 2018, through June 30, 2019
Annual Operating Report for the PSBR for the period of July 1, 2019, through June 30, 2020
SOP-5, Experiment Evaluation and Authorization, Revision 7
SOP-11, Reactor Operation at the Beam Ports, Revision 4
select records, SOP-5, Experiment Evaluation and Authorization forms numbered in calendar year 2018, 2019, and 2021
PSBR Logbook 2019-1, 2019-2, 2020-1, and 2020-2 b.
Observations and Findings The inspector reviewed the experimental review and approval process at the facility. The inspector verified that experiments utilizing the reactor were evaluated in accordance with TS 3.7, Limitations of Experiments and SOP-5, Experiment Evaluation and Authorization. The inspector noted that no recent experimental authorizations required a Title 10 of the Code of Federal Regulations (10 CFR) 50.59, Changes, tests and experiments, review and subsequent RSC review in accordance with TS 6.2.3, Review Function. The inspector reviewed a sample of the experiments approved for use from May 2019 to present day. In reviewing the logbooks, the inspector verified the reactor operator documented adequate information on each sample irradiated in the PSBR. Based on a review of these records, the inspector determined that experiments conducted at the facility met the reactivity limit, design, and material requirements in TS 3.7 and restrictions on production of Argon-41 in TS 4.6.2, Argon-41.
During the inspection, the inspector observed a sample irradiation based on previously approved experiment evaluation 2021-001 to perform a neutron radiography. The inspector noted this irradiation was performed in accordance with the experiment authorization. During the sample irradiation, the inspector observed proper postings within the irradiation area, the use of procedures by the PSBR staff, and the performance of radiation surveys.
c.
Conclusion The inspector found that the program for reviewing, approving, and conducting experiments satisfied TS and procedural requirements.
3.
Health Physics a.
Inspection Scope (IP 69001, Section 02.07)
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, TS requirements for health physics, and procedural requirements, the inspector reviewed selected aspects of the licensees program, including:
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Technical Specifications for Pennsylvania State University Breazeale Reactor, dated November 2009 up to Amendment No. 40
Annual Operating Report for the PSBR for the period of July 1, 2018, through June 30, 2019
Annual Operating Report for the PSBR for the period of July 1, 2019, through June 30, 2020
Rules and Procedures for Users of Radioactive Material at the Pennsylvania State University, dated May 2020
AP-18 Radiation Protection Program Review for 2019 and 2020
select records, completed AOP-4 Appendix A, Daily Contamination Check and Response Procedure, from May 2019 to present day
select records, completed AOP-5 forms, Water Collection and Analysis, from May 2019 to present day
select records, completed CCP-8 forms, Calibration of Air Monitors, from May 2019 to present day
select records, completed CCP-10 forms, Calibration of Area Radiation Monitors, from May 2019 to present day
select records, completed CCP-12 forms, Calibration of Portable Survey Instruments and Pocket Dosimeters, from May 2019 to present day
select records, completed Initial/Refresher Radiation Training for 2019-2020
select records, Annual Dosimetry Report [NRC Form 5] from Pennsylvania State University, for 2019 and 2020
select records, Radiation Dosimetry Report, for personnel and environmental from 2019 and 2020 b.
Observations and Findings (1) Surveys During the inspection, the inspector observed Environmental Health & Safety (EHS) staff perform a portion of the weekly radiation and contamination surveys in accordance with AOP-11. The inspector reviewed select radiation and contamination surveys of the Radiation Science and Engineering Center (RSEC) from 2019 to the present day. Additionally, the inspector reviewed daily contamination checks performed in accordance with AOP-4. The inspector verified the results were documented on the appropriate forms and evaluated as required by procedure, comments were provided if readings were other than expected, and corrective actions were taken when readings or results exceeded set action levels. The inspector noted 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 During tours of the facility, the inspector observed that postings and controls are established for radiation, high radiation, and radioactive storage areas and met the requirements of 10 CFR Part 20, Subpart J, Precautionary Procedures. The inspector confirmed that personnel complied with the signs, postings, and controls and copies of notices to workers were posted in
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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.
(3) Dosimetry The inspector observed the use of appropriate dosimetry for monitoring personnel radiation dose. The inspector verified that the dosimetry is regularly processed by an accredited vendor and that the processing technology can provide the Radiation Safety Officer with timely results. In reviewing the dosimetry records for the past 2 years, the inspector noted that the highest occupational doses were well below the limits of Subpart C, Occupational Dose Limits, to 10 CFR Part 20. The inspector also verified that annual dosimetry reports (i.e. NRC Form 5), as required by 10 CFR 19.13, Notifications and reports to individuals, were provided to each employee who received exposure greater than 100 millirem (mrem) at the facility during 2019 and 2020. The inspector determined that the licensee was appropriately monitoring individuals in accordance with the requirements in 10 CFR 20.1502, Conditions requiring individual monitoring of external and internal occupational dose.
(4) Radiation Monitoring Equipment During the inspection, the inspector observed storage and use of portable survey instrumentation at the facility. During tours of the facility, the inspector verified several portable survey instruments were within the required calibration timeframe. The inspector reviewed the calibration records of the area radiation monitors, portable survey instruments, and air monitoring equipment to verify the requirements of TS 3.6.1, Radiation Monitoring Information, and TS 4.6.1, Radiation Monitoring System and Evacuation Alarm, were met. The inspector determined portable survey meters were maintained as required by Subpart F to 10 CFR Part 20.
(5) Radiation Protection Training The inspector reviewed documentation of the initial and annual radiation protection training. The course documentation consisted of training material, evaluation (quiz), and attendance records. Through a review of records, the inspector verified that training was provided to new users as well as refresher training to users who were at the University for over a year. The content of the training program satisfied the requirements in 10 CFR 19.12, Instruction to workers.
(6) Radiation Protection Program The inspector determined that the radiation protection program was established in university policies and procedures, as well as through the facility procedures. The inspector verified that the facility conducted an annual audit to review program content and implementation in accordance with AP-18, Radiation Protection Program (RPP), as required by 10 CFR 20.1101, Radiation protection programs, paragraph (c).
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(7) ALARA Policy The inspector noted that a policy for maintaining radioactive exposure to personnel As Low As Reasonably Achievable (ALARA) was outlined and established in Rules and Procedures for Users of Radioactive Material at the Pennsylvania State University. The inspector verified that RSEC implementation of the policy is as described in AP-16, PSBR ALARA Procedure. The inspector also noted that the procedure discussed and set expectations for radiation safety culture and provided guidance for keeping doses ALARA, consistent with the requirements in 10 CFR 20.1101 and TS 3.6.4, As Low As Reasonably Achievable (ALARA).
(8) Environmental Monitoring and Effluents The inspector reviewed the calibration records of the continuous air monitors and area radiation monitors. The inspector verified these systems were channel checked daily, channel tested monthly, and calibrated annually in accordance with TS 4.6.1. During the inspection, the inspector observed both of these systems operating while the reactor was in operation, as required by TS 3.6.1.
The inspector reviewed the annual reports and records documenting solid, liquid, and gaseous releases to the environment and no uncontrolled solid releases occurred under the reactor license during the time period reviewed.
The inspector noted that liquid radioactive waste from RSEC laboratories are controlled under the broad scope license and transferred for disposal with waste from other campus laboratories. The inspector verified that gaseous release activity continued to be calculated and that the results were below the 10 mrem per year limit as required by 10 CFR 20.1101(d).
The inspector verified environmental gamma radiation monitoring was conducted using dosimetry in accordance with the applicable procedures.
The inspector observed that environmental monitoring devices were properly located outside the facility, uniquely identifiable, securely mounted, and protected from the weather elements. The inspector noted the highest measured dose at the unrestricted area (i.e. fence line) was determined to be 29 mrem per year for the 2019 calendar year and 43 mrem per year for the 2020 calendar year. These doses are reported in PSBR annual report to the NRC. The inspector verified that the data indicated no radiation doses in unrestricted areas from reactor operation would result in a member of the public exceeding the limit of 100 mrem per year in Subpart D, Radiation Dose Limits for Individual Members of the Public, to 10 CFR Part 20.
c.
Conclusion The inspector determined that the licensees radiation protection program satisfied regulatory requirements and TSs.
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4.
Design Changes a.
Inspection Scope (IP 69001, Section 02.08)
To verify compliance with 10 CFR 50.59 and TS requirements for design changes, the inspector reviewed selected aspects of the licensees program, including:
Technical Specifications for Pennsylvania State University Breazeale Reactor, dated November 2009 up to Amendment No. 40
Annual Operating Report for the PSBR for the period of July 1, 2018, through June 30, 2019
Annual Operating Report for the PSBR for the period of July 1, 2019, through June 30, 2020
RSC meeting minutes from June 2019 to March 2021
AP-12, Change, Revision 6 dated June 17, 2011
AP-12 Work Package 2020-07, Source Level Interlock Trip Setpoints Adjustment for CL59, dated August 13, 2020
AP-12 Work Package 2021-06, Beam Laboratory Expansion, dated May 13, 2021
AP-12 Work Package 2020-03, Wastewater and Processing Storage Tank Size Reduction, dated April 3, 2020 b.
Observations and Findings The inspector reviewed a sample of completed AP-12, Change forms and corresponding design change packages concerning facility changes since the last inspection in this area. Based on the design change package reviews, the inspector determined that the facility design change evaluations were screened to determine if the change required prior NRC approval along with adequate supporting documentation and information. Additionally, the inspector verified that the RSC reviewed proposed changes in accordance with TS 6.2.3, specification a.
c.
Conclusion The inspector found that changes at the facility were reviewed in accordance with NRC regulations and applicable licensee administrative controls.
5.
Committees, Audits and Reviews a.
Inspection Scope (IP 69001, Section 02.09)
To verify compliance with the TS requirements for review and audit, the inspector reviewed selected aspects of the licensees program, including:
Technical Specifications for the Pennsylvania State University Breazeale Reactor, dated November 2009 up to Amendment No. 40
Annual Operating Report for the PSBR for the period of July 1, 2018, through June 30, 2019
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Annual Operating Report for the PSBR for the period of July 1, 2019, through June 30, 2020
RSC meeting minutes from June 2019 to March 2021
PSBR audit performed in accordance with TS 6.2.4, Audit dated October 2019
PSBR audit performed in accordance with TS 6.2.4 dated October 2020
AP-6 Pennsylvania State Reactor Safeguards Committee Charter and Operating Procedure, Revision 4 dated April 20, 2006 b.
Observations and Findings The inspector reviewed the RSC meeting minutes from June 2019 to March 2021 and the RSC meeting minutes demonstrated consistency with the committee composition, rules, and review function of TS 6.2.1, Safeguards Committee Composition, TS 6.2.2, Charter and Rules, and TS 6.2.3. The inspector verified the meeting minutes were also consistent with the requirements of the RSC charter and operating procedure, AP-6. The inspector reviewed the audits of the facilitys conformance to procedures, requalification program, corrective actions, and emergency plan and implementing procedures were performed, within the specified periodicity and by a qualified person, in accordance with TS 6.2.4.
c.
Conclusion The inspector found that the review, audit, and oversight functions required by the TS were completed by the RSC.
6.
Transportation Activities a.
Inspection Scope (IP 86740)
To verify compliance with the regulations in 10 CFR, Energy, 49 CFR, Transportation, and procedural requirements for transferring or shipping licensed radioactive material, the inspector reviewed selected aspects of the licensees program, including:
select records, training materials and certificates for authorized shippers
select records, radioactive material shipping paperwork
annual review of the Radiation Protection Program 2019 and 2020
RPO-SHIP-01, Radioactive Material Receipt and Shipment Procedure, Revision 01 b.
Observations and Findings Through records review and discussions with licensee personnel, the inspector determined that the licensee shipped various types of radioactive material since the last previous inspection in this area. The inspector noted that the reactor facility staff performed low level (i.e. Limited Quantity) radioactive material shipping, typically of customer samples from approved experiment irradiations; other shipments were completed by EHS staff. The inspector verified radioactive
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material shipping records indicated that the radioisotopes present were identified, quantities were calculated, dose rates measured, and contamination checks performed, as required. The inspector noted that staff members received training every 2 years and were certified for shipping radioactive material by EHS staff, as required by Subpart H of 49 CFR 172, Training. All radioactive material shipment records reviewed by the inspector were completed in accordance with Department of Transportation and NRC regulatory requirements.
c.
Conclusion The inspector found that radioactive material was shipped in accordance with the applicable regulations.
7.
Exit Interview The inspection scope and results were summarized on July 29, 2021, with members of licensee management. The inspector described the areas inspected and discussed the inspection findings. The licensee acknowledged the results of the inspection.
Attachment PARTIAL LIST OF PERSONS CONTACTED Licensee A. Atchley Senior Associate Dean of Engineering D. Beck Senior Reactor Operator T. Daubenspeck Activation and Irradiation Specialist J. Geuther Associate Director, RSEC C. Jones Senior Reactor Operator A. Portanova Senior Reactor Operator B. Schmoke Senior Reactor Operator A. Tong Research and Development Manager Other Personnel D. Bertocchi Health Physics Specialist, EHS Y. Guo Radiation Safety Officer, EHS INSPECTION PROCEDURES USED IP 69001 Class II Research and Test Reactors IP 86740 Inspection of Transportation Activities ITEMS OPENED, CLOSED, AND DISCUSSED None PARTIAL LIST OF ACRONYMS USED 10 CFR Title 10 of the Code of Federal Regulations ALARA As Low As Reasonably Achievable AOP Auxiliary Operating Procedure AP Administrative Procedure CCP Checks and Calibrations Procedure EHS Environmental Health and Safety IP Inspection Procedure NRC U.S. Nuclear Regulatory Commission PSBR Penn State Breazeale Reactor RSC Reactor Safeguards Committee RSEC Radiation Science and Engineering Center SOP Standard Operating Procedure TRIGA Training, Research, Isotopes, General Atomics TS Technical Specification(s)