IR 05000128/2013201
| ML13330B712 | |
| Person / Time | |
|---|---|
| Site: | 05000128 |
| Issue date: | 12/05/2013 |
| From: | Gregory Bowman Research and Test Reactors Licensing Branch |
| To: | Banks K Texas A&M Univ |
| Morlang G | |
| References | |
| IR-13-201 | |
| Download: ML13330B712 (18) | |
Text
ber 5, 2013
SUBJECT:
TEXAS ENGINEERING EXPERIMENT STATION, NRC ROUTINE INSPECTION REPORT NO. 50-128/2013-201
Dear Dr. Banks:
On November 4-7, 2013, the U. S. Nuclear Regulatory Commission (NRC, the Commission)
conducted an inspection at your Nuclear Science Center TRIGA Research Reactor Facility.
The enclosed report documents the inspection results, which were discussed on November 7, 2013, with Dr. R. Skoda, Director of the Nuclear Science Center, and other members of your staff.
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 inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, no findings of significance were identified.
In accordance with Title 10 of the Code of Federal Regulations Section 2.390 Public inspections, exemptions and requests for withholding a copy of this letter, its enclosure, and your response (if any) will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) 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).
Dr. Should you have any questions concerning this inspection, please contact Mr. Mike Morlang at (301) 415-4092 or by electronic mail at Gary.Morlang@nrc.gov.
Sincerely,
/RA P. Isaac Acting for/
Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-128 License No. R-83 Enclosure:
NRC Inspection Report No. 50-128/2013-201 cc: Please see next page
Texas A&M University System Docket No. 50-128 cc:
Mayor, City of College Station P.O. Box Drawer 9960 College Station, TX 77840-3575 Governors Budget and Planning Office P.O. Box 13561 Austin, TX 78711 Texas A&M University System ATTN: Dr. Dimitris C. Lagoudas Interim Deputy Director Nuclear Science Center Texas Engineering Experiment Station 1095 Nuclear Science Road MS 3575 College Station, Texas 77843 Texas A&M University System ATTN: Associate Director Nuclear Science Center Texas Engineering Experiment Station 1095 Nuclear Science Road MS 3575 College Station, Texas 77843 Radiation Program Officer Bureau of Radiation Control Dept. Of State Health Services Division for Regulatory Services 1100 West 49th Street, MC 2828 Austin, TX 78756-3189 Susan M. Jablonski Technical Advisor Office of Permitting, Remediation &
Registration Texas Commission on Environmental Quality P.O. Box 13087, MS 122 Austin, TX 78711-3087 Test, Research and Training Reactor Newsletter 202 Nuclear Sciences Center University of Florida Gainesville, FL 32611
-2-Should you have any questions concerning this inspection, please contact Mr. Mike Morlang at (301) 415-4092 or by electronic mail at Gary.Morlang@nrc.gov.
Sincerely,
/RA P. Isaac Acting for/
Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation Docket No. 50-128 License No. R-83 Enclosure:
NRC Inspection Report No. 50-128/2013-201 cc: Please see next page DISTRIBUTION:
PROB r/f RidsNrrDprPrta RidsNrrDprPrtb MCompton PBlauchman AAdams ADAMS ACCESSION NO.: ML13330B712 * via e-mail NRC-002 OFFICE NRR/DPR/PROB NRR/DPR/PROB NAME OFont for PIsaac for GMorlang GBowman DATE 12/ 5 /13 12/ 5 /13 OFFICIAL RECORD COPY
U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No: 50-128 License No: R-83 Report No: 50-128/2013-201 Licensee: Texas A&M University Facility: Nuclear Science Center Reactor Location: College Station, TX Dates: November 4-7, 2013 Inspectors: Mike Morlang Approved by: Gregory T. Bowman, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation
-2-EXECUTIVE SUMMARY Texas A&M University Nuclear Science Center Reactor Inspection Report No. 50-128/2013-201 The primary focus of this routine, announced inspection included onsite review of selected aspects of the Texas A & M University (the licensee's) Class II research and test reactor safety programs including: organization and staffing, operations logs and records, requalification training, surveillance and limiting conditions for operation, emergency preparedness, maintenance logs and records, and fuel handling logs and records.
The licensee's programs were acceptably directed toward the protection of public health and safety, and in compliance with U. S. Nuclear Regulatory Commission (NRC) requirements.
Organization and Staffing
- The licensees organization and staffing and assignment of responsibilities remained in compliance with the requirements specified in Technical Specification Section 6.
Operations Logs and Records
- Operational activities were generally consistent with applicable Technical Specification and procedural requirements.
Requalification Training
- The Requalification Program was being completed as required and records were being maintained.
Surveillance and Limiting Conditions for Operation
- The program for Surveillance and Limiting Conditions for Operations was implemented in accordance with Technical Specifications Sections 3.0 and 4.0 requirements.
- The emergency preparedness program was conducted in accordance with the E-Plan.
Maintenance Logs and Records
- Maintenance was completed and documented as required.
Fuel Handling Logs and Records
- The fuel handling activities and documentation were conducted in accordance with the facility Technical Specifications and procedures.
REPORT DETAILS Summary of Plant Status The Texas A&M University (the licensees) TRIGA research reactor, licensed to operate at a maximum steady-state thermal power of one megawatt (1 MW), continues to be operated in support of operator training, surveillance, research, and utilization involving isotope production.
During the inspection the reactor was operated each day at full power to conduct sample irradiations.
1. Organization and Staffing a. Inspection Scope (Inspection Procedure [IP] 69001)
To verify that the licensees organization and staffing were as stated in Section 6.1 of the Technical Specifications for the Texas Engineering Experimental Station (TEES), Texas A&M University (TAMU) System Nuclear Science Center Reactor (NSCR) Facility, Amendment No 17, dated July 22, 2009, the inspector reviewed:
- Organization and staffing for the TAMU Nuclear Science Center (NSC)
- Administrative controls and management responsibilities specified in the NSC Technical Specification Section 6
- Annual Report for the Texas A&M University Nuclear Science Center for 2011, dated April, 2012
- Annual Report for the Texas A&M University Nuclear Science Center for 2012, dated April, 2013
- NSC Standard Operating Procedure (SOP),Section I, Procedure C, Administration, Revision (Rev.) 0, dated March 6, 1990
- Radiation Safety Board Meeting Minutes for May 26, 2011
- Radiation Safety Board Meeting Minutes for November 27, 2012
- Radiation Safety Board Meeting Minutes for September 19, 2013 b. Observations and Findings The structure and functions of the licensees organization at the TEES, NSCR Facility had not functionally changed since the last NRC inspection (refer to NRC Inspection Report No. 50-128/2011-201). The TEES Director, NSCR Director, NSCR Assistant Director and Reactor Manager positions had changed. The Reactor Supervisor position was currently vacant but expected to be filled shortly. All other positions reviewed were filled with qualified personnel. Review of records verified that management responsibilities were generally administered as required by Technical Specification Section 6.1.2 and applicable procedures.
-2-The Radiation Safety Board (RSB) held meetings at a frequency required by Technical Specifications (minimum one per year). A quorum and a minimum number of voting members were present.
Operations logs and records also documented that shift staffing met the minimum requirements for duty and on-call personnel.
c. Conclusions The licensees organization and staffing and assignment of responsibilities remained in compliance with the requirements specified in Technical Specification Section 6.
2. Operations Logs and Records a. Inspection Scope (IP 69001)
The inspector reviewed selected aspects of the following to verify compliance with Technical Specification Sections 2, 3, and 6 and the applicable procedures:
- Scram Log
- Staffing for operations as recorded on the reactor log sheets
- NSCR Operations Log Books Numbers 220-2126 dated from January 4, 2012 to present
- Selected entries on the following facility forms:
NSC Form 531, entitled Morning Facility Checklist - Daily, latest revision dated June 26, 2003, from January 2011 to present NSC Form 532, entitled TRIGA Reactor Pre-startup Checklist, latest revision dated September 4, 2014, from November 2011 to present NSC Form 533, entitled Reactor Operations Facility Checklist -
Daily Surveillance, latest revision dated May 13, 2013, from November 2011 to present NSC Form 534, entitled Facility Security Shutdown Checklist -
Daily Surveillance, latest revision dated July 13, 2013, from November 2011 to present NSC Form 573, entitled Irradiation Cell Entry Log, latest revision dated August 2, 2001 NSC Form 574, entitled Irradiation Cell Operations Checklist, latest revision dated September 14, 2006 NSC Form 590, entitled Unscheduled Scram Recovery Checklist, latest revision dated October 5, 2004
- Selected TAMU NSC Daily Senior Reactor Operator Checklists for 2011 and 2012
- NSC SOP, Chapter II, Reactor Operations, Section II-A, General Organization and Responsibilities, Rev. 1, dated February 9, 2000
-3-
- NSC SOP, Chapter II, Reactor Operations, Section II-B, Operations Records, Rev. 3, dated February 9, 2000
- NSC SOP, Chapter II, Reactor Operations, Section II-C, Reactor Startup, Rev. 5, dated August 19, 2003
- NSC SOP, Chapter II, Reactor Operations, Section II-D, Steady State Mode Operation, Rev. 1, dated September 3, 1999
- NSC SOP, Chapter II, Reactor Operations, Section II-F, Reactor Shutdown, Rev. 0, dated December 15, 1993
- NSC SOP, Chapter II, Reactor Operations, Section II-G, Movement of Reactor Bridge, Rev. 1, dated March 17, 1997
- NSC SOP, Chapter II, Reactor Operations, Section II-M, Response to Alarms, Rev. 1, dated February 9, 2000
- NSC SOP, Chapter II, Reactor Operations, Section II-E, Pulsing Operations, Rev. 3, dated September 3, 1999 b. Observations and Findings Reactor operations were generally carried out following written procedures and Technical Specification requirements. Information on the operational status of the facility was recorded in log books and on checklists as required by procedure.
Use of maintenance and repair logs satisfied procedural requirements.
Operational problems and events noted in the appropriate logs were reported, reviewed, and resolved as required. The inspector verified that required items were logged and cross referenced with other logs and forms, as required, and that Technical Specification Sections 2 and 3 operational limits had not been exceeded.
The inspector conducted observations of the reactor staff performing irradiations of samples at a power level of 1 MW. Observation of operational activities, on November 4-7, also confirmed that reactor operations were carried out in accordance with written procedures and Technical Specification requirements.
In 2011 there were 18 unplanned scrams and in 2012 there were 17 unplanned scrams. This is down from 22 unplanned scrams in 2010.
c. Conclusions Operational activities were generally consistent with applicable Technical Specification and procedural requirements.
-4-3. Requalification Training a. Inspection Scope (IP 69001)
To verify that operator requalification activities and training were conducted as required in the licensees Senior Reactor Operator and Reactor Operator Requalification Program, Rev. 4, dated April 1997, and to verify that medical requirements were met, the inspector reviewed:
- Requalification Training Matrix dated October 2012 to September 2014
- Medical examination records
- Active license status of all current operators
- Written examinations given to operators for 2012
- Selected portions of NSC Reactor Operations Log Books for 2011 through the present
- Logs and records of reactivity manipulations for 2011 through the present
- Training lectures and records for selected individuals for the current and previous training cycles
- Radiation Safety Board Reactor Requalification Program Audits dated August 5, 2011 and November 27, 2012
2, dated March 2, 2001
- TAMU Senior Reactor Operator and Reactor Operator Requalification Program, Rev. 4, dated April 1997 b. Observations and Findings The facility had seven qualified, licensed Senior Reactor Operators and two Reactor Operators. The facility had 4 licenses that needed termination letters sent to the NRC.
A review of the logs and requalification records showed that annual operational examinations were being administered as required. Written examinations were administered within the time frame as required. In order to comply with the requirement for actively performing their operator functions for a minimum of four hours per calendar quarter, the licensee included time spent on the reactor console, supervisory functions, and maintenance, as appropriate. This was consistent with 10 CFR Part 55 requirements.
Section 2.1 of the requalification program requires that one or more lectures will be scheduled within a four month interval to cover a topic. The lecture sequence over all topics will take two years to complete and will then be repeated. Self-study or individual tutoring may substitute for each missed lecture, however, examinations given after each lecture must be taken or an alternate examination taken within a month after the lecture. Lectures on the Emergency Plan and Security Plan will be given annually.
-5-The inspector verified that all current operators were up to date on medical evaluations. The Unresolved Item 50-128/2011-201-1 will be closed.
c. Conclusions The Requalification Program was being completed as required and records were being maintained.
4. Surveillance and Limiting Conditions for Operation a. Inspection Scope (IP 69001)
To determine that surveillances and Limiting Conditions for Operations (LCOs)
verifications were being completed as required by Technical Specification Sections 3.0 and 4.0, the inspector reviewed:
- NSC Reactor Operations Log Books Numbers 220-226 (January 4, 2011 to present)
- Surveillance and calibration data and records for 2011 and 2012 documented on the following facility forms:
NSC Form 557, entitled Annual Reactor Maintenance and Surveillance, dated May 20, 2008, for 2011 and 2012 NSC Form 546, entitled Semiannual Fuel Element Temperature Measuring Channel Maintenance, dated July 15, 2008, for 2011 and 2012 NSC Form 547, entitled Semiannual Linear Power Measuring Channel Maintenance and Surveillance, dated February 16, 2000, for 2011 and 2012 NSC Form 539, entitled Weekly Ventilation and Scram Surveillance, dated June 30, 2009, for 2011 and 2012 NSC Form 541, entitled Quarterly Transient Rod Drive Maintenance, dated October 4, 1999, for 2011 to 2012 NSC Form 549, entitled Semiannual Reactor Pulse Power Surveillance, dated October 15, 1999, for 2011 and 2012 NSC Form 550, entitled Semiannual Transient Rod Drive Maintenance, dated October 4, 1999, for 2011 and 2012 NSC Form 551, entitled Semiannual Scram Circuit Surveillance, dated July 9, 2005, for 2011 and 2012 NSC Form 552, entitled Semi-Annual Evacuation Horn System Surveillance, dated October 4, 1999, for 2011 and 2012 NSC Form 565, entitled Annual Calorimetric, dated July 5, 2010, for 2011 and 2012
-6-b. Observations and Findings The inspector determined that selected daily, monthly, annual, other periodic checks, tests, verifications, and calibrations for Technical Specification required surveillances and LCOs were completed as stipulated. Surveillances, LCOs, and calibration reviews were completed on schedule and performed in accordance with licensee procedures. The recorded results were within the Technical Specification and procedurally prescribed parameters and in close agreement with the previous surveillance results. The records and logs reviewed were accurate.
c. Conclusions The program for Surveillance and LCO confirmations was implemented in accordance with Technical Specifications Sections 3.0 and 4.0 requirements.
5. Emergency Preparedness a. Inspection Scope (IP 69001)
To verify compliance with Technical Specification Section 6.2 and the licensees Emergency Plan for the TEES, Texas A&M University System NSCR Facility, Revision 2, dated December 14, 1999, the inspector reviewed selected aspects of:
- Annual training records for the College Station Fire Department dated August 15-17, 2012 and November 5-7, 2013, and the College Station Medical Center dated June 25, 2013
- Offsite support and annual reconfirmation of letters of agreement between NSC and the College Station Medical Center and the annual agreement letter between NSC and the College Station Fire Department (dated June 18 and 27, 2013)
- Emergency drills and exercises for 2011 and 2012
- Emergency response facilities, supplies, equipment and instrumentation Radiation Safety Board Meeting Minutes for May 26, 2011 Radiation Safety Board Meeting Minutes for November 27, 2012 Radiation Safety Board Meeting Minutes for September 19, 2013
- NSC Form 583, entitled Emergency Directors Checklist, dated August 6, 1992 b. Observations and Findings The licensee staff and the Radiation Safety Board audited and reviewed the Emergency Plan and Implementing procedures at least annually.
-7-Through records review, and interviews with licensee, the inspector determined that emergency responders were trained in the proper actions to take in case of an emergency. Agreements with outside response organizations had been updated annually. Based on a review of training records, it is evident that the College Station Fire Department continues to support the facility. Fire station personnel from all shifts participated in training during the inspection and personnel from the College Station Medical Center participated in training on June 25, 2013. The inspector observed one of the training sessions during the inspection.
Emergency facilities, instrumentation, and equipment were being maintained and inventoried as required by Emergency Plan Sections 10.4 and 10.5. To ensure appropriate emergency response personnel are notified in the event of an emergency, the emergency notification roster was updated and verified quarterly as required by Emergency Plan Section 8.5.
c. Conclusions The emergency preparedness program was conducted in accordance with the E-Plan.
6. Maintenance Logs and Records a. Inspection Scope (IP 69001)
To determine that maintenance was being completed as required by the Technical Specifications and applicable procedures, the inspector reviewed:
- NSC Reactor Operations Log Books Numbers 220-226, dated from January 4, 2011 to present
- Surveillance and calibration data and records for 2011 and 2012 documented on the following facility forms:
NSC Form 547, entitled Semiannual Linear Power Measuring Channel Maintenance and Surveillance, dated February 16, 2000, for 2011 and 2012 NSC Form 539, entitled Weekly Ventilation and Scram Surveillance, dated June 30, 2009, for 2011 and 2012 NSC Form 541, entitled Quarterly Transient Rod Drive Maintenance, dated October 4, 1999, for 2011 and 2012 NSC Form 549, entitled Semiannual Reactor Pulse Power Surveillance, dated October 15, 1999, for 2011 and 2012 NSC Form 550, entitled Semiannual Transient Rod Drive Maintenance, dated October 4, 1999, for 2011 and 2012 NSC Form 551, entitled Semiannual Scram Circuit Surveillance, dated July 9, 2005, for 2011 and 2012 NSC Form 552, entitled Semi-Annual Evacuation Horn System Surveillance, dated October 4, 1999, for 2011 and 2012
-8-NSC Form 565, entitled Annual Calorimetric, dated July 5, 2010, for 2011 and 2012
- Texas A&M University NSC 2012 Annual Report, dated April, 2013 b. Observations and Findings In 2011 there were 18 unplanned scrams and in 2012 there were 17 unplanned scrams. This is a decrease from 22 unplanned scrams in 2010. There were 11 unplanned scrams to date in 2013. A review of the reactor console and maintenance logs showed that maintenance items were being documented. This review also demonstrated that maintenance was being conducted consistent with the Technical Specifications and applicable procedures.
c. Conclusions Maintenance was completed and documented as required.
7. Fuel Handling Logs and Records a. Inspection Scope (IP 69001)
To verify adherence to Technical Specifications Sections 3.1.4, 3.3.1.b, 5.1, 5.2, and 5.5, the inspector reviewed:
NSC Core Loading Map in the Control Room
- Fuel handling equipment and instrumentation
- NSC Reactor Operations Log Book Number 220-226, dated from January 4, 2011 to present
- Fuel bundle movement records for July 2012 and July 2013 NSC Form 576, entitled LEU Fuel Log Vol. I, dated July 18, 2008 NSC Form 578, entitled LEU Fuel Log Vol. II-A In Service Element Data, dated July 23, 2006 NSC Form 575, entitled LEU Fuel Log Vol. II-B Fuel Element Elongation Data Sheets by Bundle, dated July 23, 2006 b. Observations and Findings The inspectors reviewed selected records for the July 2012 and June 2013 core offload and reload for fuel inspection and control rod maintenance and inspection. The inspector also verified that fuel locations were consistent with records. Records showed that Technical Specification required surveillances for refueling and fuel movement were completed to ensure controlled operations for the reactor core. All fuel movements were recorded in the reactor log and in the individual fuel element log sheets. Good correlation was noted between the fuel logs and console logs.
-9-The inspector observed that the data recorded for fuel was acceptable and was cross referenced in the operations logs. Log entries verified that fuel movements were completed under the direct supervision of an SRO as required. Through records review and interviews with licensee personnel, the inspector determined that fuel movements were conducted in accordance with Technical Specifications to authorized locations.
c. Conclusions The fuel handling activities and documentation were conducted in accordance with the facility Technical Specifications and procedures.
8. Exit Interview The inspectors presented the inspection results to licensee management at the conclusion of the inspection on November 7, 2013. The inspector described the areas inspected and discussed in detail the inspection observations. No dissenting comments were received from the licensee. The licensee acknowledged the findings presented and did not identify as proprietary any of the material provided to or reviewed by the inspector during the inspection.
PARTIAL LIST OF PERSONS CONTACTED Licensee Personnel R. Skoda Director, Nuclear Science Center J. Newhouse Associate Director A. Booth NSCR Radiation Protection Office D. Menchaca Environmental Health and Safety Radiation Protection Office INSPECTION PROCEDURES USED IP 69001: Class II Non-Power Reactors ITEMS OPENED, CLOSED, AND DISCUSSED Opened None Closed 50-128/2011-201-1 URI Failure to conduct operator medical evaluations within the required time frame.
LIST OF ACRONYMS USED 10 CFR Title 10 of the Code of Federal Regulations IP Inspection Procedure LCO Limiting Condition for Operation MW Megawatt NSC Nuclear Science Center NSCR Nuclear Science Center Reactor NRC U. S. Nuclear Regulatory Commission Rev. Revision SOP Standard Operating Procedure TAMU Texas A&M University TEES Texas Engineering Experiment Station URI Unresolved Item