IR 05000005/2020201

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the Pennsylvania State University - U.S. Nuclear Regulatory Commission Routine Safety Inspection Report No. 05000005/2020201
ML20223A009
Person / Time
Site: Pennsylvania State University
Issue date: 09/03/2020
From: Travis Tate
NRC/NRR/DANU/UNPL
To: Unlu K
Pennsylvania State Univ, University Park, PA
Balazik M, NRR/DANU/UNPL, 301-415-2856
References
IR 2020201
Download: ML20223A009 (13)
v • d • e


Text

September 3, 2020

SUBJECT:

THE PENNSYLVANIA STATE UNIVERSITY - U.S. NUCLEAR REGULATORY COMMISSION ROUTINE SAFETY INSPECTION REPORT NO. 05000005/2020201

Dear Dr. Unlu:

From July 27-30, 2020, the U.S. Nuclear Regulatory Commission (NRC) staff conducted an inspection at your Pennsylvania State University Breazeale Reactor facility. The enclosed report presents the results of that inspection that were discussed on July 30, 2020, with you, Dr. Lora Weiss, Senior Vice President for Research; Dr. Anthony Atchley, Senior Associate Dean of Engineering; Dr. Laura Pauly, Chairman of the Penn State Reactor Safeguards Committee; Dr. Yuanqing Guo, Occupational Safety and Environmental Health Manager/Manager of Radiation Protection; and Dr. Jeffrey Geuther, Associate Director for Operations.

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 non-compliance were identified. Therefore, no response to this letter is required.

In accordance with Title 10 of the Code of Federal Regulations 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 and Access 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. Michael Balazik at (301) 415-2856, or by electronic mail at Michael.Balazik@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.50-005 License No. R-2 Enclosure:

As stated cc: See next page

The 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

ML20223A009 *via e-mail NRC-002 OFFICE NRR/DANU/UNPL/PM* NRR/DANU/UNPO/LA* NRR/DANU/UNPO/BC*

NAME MBalazik NParker TTate DATE 8/12/2020 8/12/2020 9/3/2020

U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No.: 50-005 License No.: R-2 Report No.: 05000005/2020201 Licensee: The Pennsylvania State University Facility: Penn State Breazeale Reactor Location: University Park, Pennsylvania Dates: July 27-30, 2020 Inspector: Michael F. Balazik 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 The Pennsylvania State University Penn State Breazeale Reactor Facility Inspection Report No. 05000005/2020201 The primary focus of this routine, announced safety inspection was the onsite review of selected aspects of the Pennsylvania State University (PSU, licensee) Class II research reactor facility safety program, including: (1) organization and staffing, (2) operations logs and records, (3) requalification training, (4) surveillance and limiting conditions for operation (LCO),

(5) emergency planning, (6) maintenance logs and records, and (7) fuel handling logs and records since the last U.S. Nuclear Regulatory Commission (NRC) inspection of these areas.

The NRC staff determined that the licensees programs were acceptably directed toward the protection of public health and safety, and in compliance with NRC requirements.

Organization and Staffing

  • The Penn State Breazeale Reactor (PSBR) organization and staffing were consistent with technical specification (TS) requirements.

Operation Logs and Records

  • The operation logs and records were maintained in accordance with facility procedures and TSs.

Requalification and Training

  • The requalification program was conducted consistently with the TSs and Administrative Procedure (AP)-3, Operator and Senior Operator Requalification.

Surveillance and Limiting Conditions for Operation

  • The operations reviewed by the inspector were in compliance with the LCO and surveillance requirements as required in the TS.

Emergency Planning

  • The records reviewed by the inspector indicated that the PSBR Emergency Preparedness Plan (EPP), oversight, drills, and training were implemented as required by facility procedures and regulations.

Maintenance Logs and Records

  • The licensee maintained records documenting principal maintenance activities in compliance with TS requirements and facility procedures.

Fuel Handling Logs and Records

  • The licensee conducted and documented fuel handling activities in accordance with TS requirements and facility procedures.

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REPORT DETAILS Summary of Facility Status The PSU operates a 1-megawatt TRIGA (Training, Research, Isotopes, General Atomics)

nuclear reactor in support of education, research, and service. During the inspection, reactor utilization was in support of ongoing research and development.

1. Organization and Staffing a. Inspection Scope (Inspection Procedure (IP) 69001-02.01)

To ensure that the requirements of TS 6.1, Organization, were met, the inspector reviewed the following:

  • Facility Operating License No. R-2, Docket No. 50-5, Amendment No. 40
  • Appendix A to Facility Operating License No. R-2, Amendment No. 39
  • Organization Chart, Radiation Science and Engineering Center
  • PSBR staffing contact list, dated June 9, 2020
  • Standard Operating Procedure (SOP)-1, Reactor Operator Procedure
  • PSBR annual operating report, fiscal year (FY) 2017-2018 and FY 2018-2019
  • PSBR console logbooks 104, 105, 106, 107 b. Observations and Findings The inspector found that since the previous NRC inspection (Inspection Report No. 50-5/2018-201), there was personnel changes in the organization at the PSBR as specified by TS 6.1.1, Structure. A new Senior Vice President of Research (Level 1) and a Manager of Radiation Protection were selected. The inspector determined that these individuals meet the requirements specified in TS 6.1.2 and the guidance in American National Standards Institute/American National Standards-15.4-1988, as required by TS 6.1.4, Selection and Training of Personnel.

A list of facility personnel is posted in the control room in accordance with TS 6.1.3, Staffing, item b. Additionally, the list is posted in the emergency support center (ESC) as required by procedure Checks and Calibrations Procedures (CCP)-21, Emergency Support Center Supplies. The inspector found the list to contain the names and contact information for management, operations, radiation safety, and other support personnel. In discussions with the licensee and review of documents, the inspector verified the current management and operational personnel are listed. Further, the inspector verified the accuracy of the contact information for a few offsite support organizations.

The inspector reviewed PSBR logbook entries and determined that staffing satisfied the requirements of TS 6.1.3.a.

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c. Conclusion The inspector determined the PSBR organization and staffing were consistent with the requirements in TS 6.1.1 and 6.1.3.

2. Operations Logs and Records a. Inspection Scope (IP 69001-02.02)

To ensure that the requirements of TS 6.7, Records, were met, the inspector reviewed the following:

  • SOP-1, Reactor Operating Procedure
  • AP-3, Operator and Senior Operator Requalification
  • AP-4, Identification, Evaluation and Documentation of Safety System Failures, Abnormal Events, and Operational Events
  • PSBR console logbooks 104, 105, 106, and 107 b. Observations and Findings The inspector observed that logbook entries were maintained in accordance with approved procedures and uniformity. By PSBR procedures, certain items were to be entered in the console logbook, such as requalification requirements, staffing requirements, completed compliance checks, maintenance items, and core position within the pool. The inspector observed the compliance checks were stamped with retention times in accordance with TS 6.7.

c. Conclusion The inspector determined the licensees logbook records and record keeping programs were maintained as required by PSBR administrative procedures and met the retention requirements of the TSs.

3. Requalification Training a. Inspection Scope (IP 69001-02.04)

To ensure that the requalification training requirements of TS 6.1.4, TS 6.2.4, Audit; TS 6.7.2, Records to be Retained for at Least One Training Cycle; and, Title 10 of the Code of Federal Regulations (10 CFR) 55.53, Conditions of licenses, paragraphs (e) and (h), were met, the inspector reviewed the following:

  • AP-3, Operator and Senior Operator Requalification
  • operation and emergency procedures exam results, 2018-2020
  • requalification training records and presentations, 2018-2020
  • written requalification exams, 2018-2020
  • annual key-on hours and manipulations spreadsheet
  • operators license medical matrix-4-
  • active operator license list
  • audit 2018
  • PSBR console logbooks 104, 105, 106, and 107 b. Observations and Findings The requalification plan is captured in AP-3 and contains annual on the job training, oral test, and operational test requirements. The inspector verified that training lectures in the areas required by AP-3 were performed throughout the training cycle. The inspector verified that written, operations, and emergency preparedness exams were completed during the training cycle, as required. The inspector verified a sample of operators with an active license performed the required quarterly hours of reactor operations. The inspector verified the licensee conducted an independent audit of the requalification program as required by TS 6.2.4. Further, the inspector verified by record review that all active operators completed a biennial medical examination.

c. Conclusion The inspector determined that the PSBR requalification program was conducted as required by NRC regulations, PSBR TSs, and procedures.

4. Surveillance and Limiting Conditions for Operation a. Inspection Scope (IP 69001-02.05)

To ensure that the requirements of TS 3.0, Limiting Conditions for Operation, and TS 4.0, Surveillance Requirements, were met, the inspector reviewed the following:

  • SOP-4A, Radiation, Evacuation, and Alarm Checks, and completed forms
  • SOP-2, Daily Checkout Procedure, and completed forms
  • CCP-13, Annual Pulse Comparison, and completed forms
  • CCP-16, Inspection of Fuel Elements, and completed forms
  • CCP-25, Emergency-Fill: Fire Hose Inspection, and completed forms
  • AP-15, CCP/SOP Implementation Relations to Technical Specifications Surveillance Requirements
  • PSBR console logbooks 104, 105, 106, and 107 b. Observations and Findings The inspector selected a sample of the TS-required surveillances to verify implementation and determined that the frequency and outcome met TS requirements. During the inspection, the inspector observed the performance of SOP-4A and SOP-2 that support power operations to ensure certain LCOs are-5-

met. The inspector verified surveillance results were retained as required by TS 6.7.1, Records to be Retained for at Least Five Years, and licensees procedural requirements.

c. Conclusion The inspector determined that PSBR operations were in compliance with the LCOs and surveillance requirements as stated in the TSs.

5. Emergency Planning a. Inspection Scope (IP 69001-02.10)

To ensure that the emergency preparedness requirements of 10 CFR 50.34, Contents of applications; technical information, Appendix E, and TS 6.3, Operating Procedures, item u. are met, the inspector reviewed the following:

  • emergency procedure (EP)-1, EPP Implementation
  • EP-3, Building Evacuation
  • CCP-20, University Police Training
  • CCP-21, Emergency Support Center Supplies Check
  • CCP-22, Emergency Drill and Preparedness
  • memorandum of understanding (MOU) with University Police
  • MOU with Alpha Fire Company
  • MOU with Mount Nittany Medical Center
  • emergency contact list
  • audit report in 2018 b. Observations and Findings The inspector reviewed the EPP and implementing procedures to verify they were current, approved by management, and readily available in several locations for use as required. The licensee arranged for an independent biennial audit of the emergency plan and implementing procedures that was performed in in December 2018, as required by TS 6.2.4.d. The inspector reviewed the equipment check semi-annual surveillance completed forms for the emergency supply cabinets located in the ESC to ensure the availability and operability of emergency equipment. The inspector observed the performance check for the facility evacuation alarm to ensure operability.

The inspector confirmed through document review that the licensee continues to maintain a current MOU with the University Police, Alpha Fire Company, and the Mount Nittany Medical Center to support both onsite and offsite emergency response. The inspector reviewed training records for reactor staff and University Police and verified training was completed annually, as required.

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Additionally, the facility is required to perform an annual emergency drill in accordance with PSBR EPP. The inspector verified that emergency drills for calendar year 2018 and 2019 were conducted resulting in evacuations of the facility and participation of offsite organizations. In addition, the facility considered actual events (e.g. medical emergency) and incorporated lessons learned into emergency planning.

c. Conclusion The records reviewed by the inspector indicated that the PSBR EPP, oversight, and training were implemented as required by TSs and licensee procedures.

6. Maintenance Logs and Records a. Inspection Scope (IP 69001-02.11)

To ensure that the maintenance requirements of TS 6.7.1.c., and 6.7.1.g. were met, the inspector reviewed the following:

  • AP-4, Identification, Evaluation and Documentation of Safety System Failures, Abnormal Events, and Operational Events
  • PSBR Annual Operating Report, FY 2017-2018 and FY 2018-2019
  • electronic maintenance log
  • PSBR console logbooks 104, 105, 106, and 107 b. Observations and Findings The inspector reviewed a selection of maintenance logs and console logbooks.

The inspector determined that the selected significant maintenance items reviewed are documented and resolved as required by the licensees administrative procedures. Additionally, the inspector verified by document review that maintenance records were retained for at least five years as required by TS 6.7.1.

c. Conclusion The inspector determined the licensee maintained records documenting maintenance activities in compliance with TS requirements and PSBR procedures.

7. Fuel Handling Logs and Records a. Inspection Scope (IP 69001-02.12)

To ensure that the requirements of TS 3.1.6 and TS 4.1.3, TRIGA Fuel Elements, were met, the inspector reviewed the following:

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  • CCP-16, Inspection of Fuel Elements
  • SOP-3, Core Loading and Fuel Handling
  • current fuel element storage location map
  • current core configuration map
  • AP-12, Work Package 2020-1, Core 59
  • PSBR console logbooks 104, 105, 106, and 107 b. Observations and Findings The inspector reviewed the fuel movement and surveillance records and determined that one fuel inspection has occurred since this module was previously inspected. During the July 2020 fuel inspection, all 104 fuel elements and three fuel-followed control rod elements were inspected in accordance with TS 3.1.6 and TS 4.1.3. The inspector reviewed the results of CCP-16 and verified that all fuel elements passed the TS requirements.

The inspector reviewed core configuration changes and determined that one core (Core 59) was installed since this module was previously inspected. The inspector verified through review of documents and discussions with the licensee that two fuel elements were removed from the core because of high burnup levels, two fuel elements were installed in the core, and numerous fuel elements were shuffled within the core. The inspector verified changes were documented and followed established procedures.

c. Conclusion The inspector determined that the licensee conducted and documented fuel handling activities in accordance with TS requirements and licensee procedures.

8. Exit Interview The inspector reviewed the inspection results with members of licensee management to include the Senior Vice President of Research (Level 1), Senior Associate Dean of Engineering, Chairman of the Penn State Reactor Safeguards Committee, Director of the PSBR Facility (Level 2), Manager of Radiation Protection, and the Associate Director for Operations (Level 2) at the conclusion of the inspection on July 30, 2020. The licensee acknowledged the results and conclusions presented by the inspector.

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PARTIAL LIST OF PERSONS CONTACTED Licensee J. Geuther, Associate Director for Operations S. Herrmann, Reactor Operations Coordinator A. Tong, Senior Research Engineer K. Unlu, Director of the PSBR Facility L. Weiss, Senior Vice President for Research INSPECTION PROCEDURES USED IP 69001 Class II Research and Test Reactors ITEMS OPENED, CLOSED, AND DISCUSSED Opened None Closed None Discussed None LIST OF ACRONYMS USED 10 CFR Title 10 of the Code of Federal Regulations AP Administrative Procedure CCP Checks and Calibrations Procedures EP Emergency Procedure EPP Emergency Preparedness Plan ESC Emergency Support Center FY Fiscal Year IP Inspection Procedure LCO Limiting Conditions for Operation NRC U.S. Nuclear Regulatory Commission PSBR Penn State Breazeale Reactor SOP Standard Operating Procedure TRIGA Training, Research, Isotopes, General Atomics TS Technical Specification Attachment

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