IR 05000128/2016201

Texas A&M University, Texas A&M Engineering Experiment Station NRC Routine Inspection Report 05000128/2016201

ML16358A728
Person / Time
Site:	05000128
Issue date:	01/04/2017
From:	Mendiola A J Research and Test Reactors Oversight Branch
To:	McDeavitt S Texas A&M Univ
Morlang G M
References
IR 2016201
Download: ML16358A728 (18)

Text

January 4, 2017

Dr. Sean McDeavitt, Director Texas A&M University System

Nuclear Science Center Texas A&M Engineering Experiment Station 1095 Nuclear Science Road, M/S 3575 College Station, TX 77843

SUBJECT: TEXAS A&M UNIVERSITY, TEXAS A&M ENGINEERING EXPERIMENT STATION-NRC ROUTINE INSPECTION REPORT NO. 50-128/2016-201

Dear Dr. Banks:

The U.S. Nuclear Regulatory Commission (NRC or the Commission) conducted an inspection, from December 12-15, 2016, at your Nuclear Science Center TRIGA Research Reactor Facility. The enclosed report documents the inspection results, which were discussed on December 15, 2016, with members of the Texas A&M Nuclear Science Center. The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations and with the conditions of your license. The inspector reviewed selected procedures and records, observed activities, and interviewed personnel.

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 el ectronically for public inspection in the NRC Public Document Room or from the Publicly Available Records component of NRC's 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. Should you have any questions concerning this inspection, please contact Mr. Gary Morlang at (301) 415-4092 or by electronic mail at Gary.Morlang@nrc.gov.

Sincerely,

/RA/

Anthony J. Mendiola, 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:

Inspection Report No. 50-128/2016-201 cc: See next page Texas A&M University Docket No. 50-128

cc: Mayor, City of College Station P.O. Box Drawer 9960 College Station, TX 77840-3575

Governor's Budget and Planning Office P.O. Box 13561 Austin, TX 78711

Dr. Dimitris C. Lagoudas, Deputy Director Texas A&M University System Texas A&M Engineering Experiment Station 241 Zachry Engineering Center

College Station, Texas 77843

Mr. Jerry Newhouse, Associate Director Texas A&M University System

Nuclear Science Center Texas A&M Engineering Experiment Station 1095 Nuclear Science Road, M/S 3575

College Station, Texas 77843 Radiation Program Officer Bureau of Radiation Control Department of State Health Services

Division for Regulatory Services 1100 West 49 th Street, MC2828 Austin, TX 78756-9347

Technical Advisor

Office of Permitting, Remediation and Registration Texas Commission on Environmental Quality P.O. Box 13087, MS 122 Austin, TX 78711-3087 Mr. Scott Miller, Manager Reactor Operations Texas A&M University Texas A&M Engineering Experiment Station 1095 Nuvlear Science Road, MS3575 College Station, Texas 77843

Test, Research and Training

Reactor Newsletter P.O. Box 118300 University of Florida Gainesville, FL 32611

ML16358A728; *concurred via e-mail NRC-002 OFFICE NRR/DPR/PROB/RI* NRR/DPR/PROB/LA* NRR/DPR/PROB/BC NAME GMorlang NParker (ELee w/comment for) AMendiola DATE 1/4/17 12/28/16 1/4/17

Enclosure U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION Docket No. 50-128

License No. R-83

Report No. 50-128/2016-201

Licensee: Texas A&M University

Facility: Texas A&M Engineering Experiment Station Nuclear Science Center Reactor Location: College Station, TX

Dates: December 12-15, 2016

Inspector: Gary Morlang

Approved by: Anthony J. Mendiola, Chief Research and Test Reactors Oversight Branch Division of Policy and Rulemaking Office of Nuclear Reactor Regulation EXECUTIVE SUMMARY Texas A&M University Texas A&M Engineering Experiment Station Nuclear Science Center Reactor Inspection Report No. 50-128/2016-201

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: 1) procedures, 2) experiments, 3) health physics, 4) effluents and environmental monitoring, 5) design changes, 6) committees, audits and reviews, and 7)

transportation. The licensee's programs were generally directed toward the protection of public

health and safety.

Procedures

• Written procedures were being maintained in accordance with Technical Specifications (TS).

Experiments

• The approval and control of experiments met TS and applicable regulatory requirements.

Health Physics

• Periodic surveys were completed and documented as required by procedure.

• Postings and signs met regulatory requirements.

• Personnel dosimetry was being worn as required and recorded doses were within the U.S. Nuclear Regulatory Commission's (NRC) regulatory limits.

• Radiation survey and monitoring equipment was being maintained and calibrated as required.

• The Radiation Protection and As Low As Reasonably Achievable (ALARA) programs satisfied regulatory requirements.

• Radiation protection training was acceptable.

Effluents and Environmental Monitoring

• Effluent monitoring satisfied license and regulatory requirements and releases were within the specified regulatory and TS limits.

- 2 - Design Changes

• Based on the records reviewed, the inspector determined that the licensee's design change program was being implemented as required.

Committees, Audits and Review

• The Reactor Safety Board (RSB) completed the review, oversight, and audit functions required by TS Section 6.2.

Transportation

• Radioactive material was being shipped in accordance with the applicable regulations.

• The training of the staff members responsible for shipping the radioactive material met U.S. Department of Transportation (DOT) requirements.

REPORT DETAILS Summary of Plant Status

The Texas A&M University (the licensee) TRIGA research reactor, licensed to operate at a maximum steady-state thermal power of one megawatt, continued to be operated in support of operator training, surveillance, research, and utilization involving neutron activation analysis. During the inspection the reactor was operated each day at full power to conduct sample irradiations.

1. Procedures a. Inspection Scope (Inspection Procedure (IP) 69001)

The inspector reviewed the following to ensure that the requirements of TS Section 6.3, "Operating Procedures," were being met concerning written procedures:

• TS for the Texas A&M TRIGA reactor, dated March 1983

• Standard Operating Procedure (SOP)Section I, Procedure B, "Purpose and Scope of the Review Mechanism," Rev. 0, dated February 1, 1985

• SOP Section I, Procedure C, "Administration," Rev. 0, dated August 25, 1994 * SOP Section I, Procedure F, "Review and Approval," Rev. 2, dated March 11, 2015 * SOP Section III, Procedure G, "Reactor Pulse Power Surveillance," Rev. 1, dated February 9, 2000

• SOP Section III, Procedure I, "Scram Circuit Surveillance," Rev. 2, dated February 9, 2000

• RSB Meeting Minutes for 2015 and 2016

• Nuclear Science Center Reactor (NSCR) Operations Log Books Numbers 230-240, dated September 18, 2014 to present b. Observations and Findings Oversight and review of procedure implementation was provided by licensee management and the RSB. All procedures were current. Procedure changes are done by a Procedure Change Notice (PCN). The PCN lists the procedure steps affected, the current wording, the new wording and the reason for change. All changes were approved by the RSB. All licensed reactor operators and senior reactor operators were required to review and sign all PCN's.

c. Conclusion Procedure administrative review, revision, adherence to, and implementation satisfied TS requirements.

- 2 - 2. Experiments a. Inspection Scope (IP 69001)

The inspector reviewed selected aspects of the following in order to verify that experiments were being conducted consistent with TS Sections 3.6 and 6.4:

• NSCR Operations Log Books 230-240, dated September 18, 2014 to present * Experiment authorization review forms, most recent Number EA-28, dated June 7, 2003

• SOP Section IV, Procedure A, "Experiment Review and Approval," latest revision dated January 25, 2002

• SOP Section IV, Procedure B, "Sample Handling Procedures," latest revision dated July 14, 1988

• SOP Section IV, Procedure C, "Pneumatic System Operation," latest revision dated February 8, 1991

• SOP Section IV, Procedure D, "Beam Port Experiments," latest revision dated September 3, 1999

• SOP Section IV, Procedure E, "Irradiation Cell Experiments," latest revision dated March 2, 2001

• SOP Section IV, Procedure F, "Neutron Radiography Beam Port #4," latest revision dated March 22, 1990

• SOP Section IV, Procedure G, "In-Pool Irradiations," latest revision dated May 2, 1984

• SOP Section IV, Procedure H, "Thermal Column Film Irradiations," latest revision dated February 14, 1996

• Various Request for Service forms completed for in-pool and irradiation cell irradiations and experiments

• Annual Report for the Texas A&M University Nuclear Science Center for 2014, dated August 2015

• Annual Report for the Texas A&M University Nuclear Science Center for 2015, dated March 2016

• Modification Authorizations 1-60 b. Observations and Findings The inspector reviewed the various experiments that had been approved for the reactor facility. All had been approved and signed as required. No new experiments had been initiated, reviewed, or approved for 2014, and there was only one modification authorization approved in 2015.

The inspector observed an irradiation experiment using the pneumatic transfer system which was approved and authorized by the NSCR Director and the Chairman of the RSB in accordance with TS Section 6.4(a) and SOP Section IV, Procedure A. The irradiation experiment had been reviewed and approved by the health physicist (HP) and senior reactor operator on duty as required, and was conducted under the cognizance of the reactor supervisor as noted in the

- 3 - NSCR operations log. The licensee estimated the reactivity worth of the experiment and recorded it on the appropriate sheet. The results of the experiments were documented on the NSCR operations log book sheets and on the irradiation request forms.

c. Conclusion The approval, conduct, and control of experiments met TS and applicable procedure requirements.

3. Health Physics a. Inspection Scope (IP 69001)

The inspector reviewed selected aspects of the following to verify compliance with Title 10 of the Code of Federal Regulations (10 CFR) Parts 19 and 20 and TS Sections 3.5, 4.5, 5.4, and 6.6:

• Personnel dosimetry records for 2015 and 2016 through the present

• RSB meeting minutes from 2015 through the present

• RSB completed audits and reviews from 2015 through the present

• NSCR Form 844, "Radiation Work Permit (RWP)," Rev. 0, dated April 30, 2010, for 2015 and 2016

• Annual Report for the Texas A&M University Nuclear Science Center for 2014, dated August 2015

• Annual Report for the Texas A&M University Nuclear Science Center for 2015, dated March 2016

• SOP Section VII, Procedure A-1, "Radiation Protection Program," Rev. 3, dated December 4, 1997

• SOP Section VII, Procedure A-2, "Record Retention," Rev. 3, dated December 4, 1997

• SOP Section VII, Procedure A-3, "Reporting Requirements," Rev. 4, dated September 14, 2007

• SOP Section VII, Procedure A-4, "Health Physics Administration," Rev. 4, dated December 19, 1997

• SOP Section VII, Procedure A-6, "ALARA," Rev. 0, dated December 12, 2002

• SOP Section VII, Procedure B-4, "Daily Facility Air Monitoring Check," Rev. 5, dated September 14, 2007

• SOP Section VII, Procedure B-6, "Monthly Facility Air Monitoring Test," Rev. 4, dated September 14, 2007

• SOP Section VII, Procedure B-7, "Area Radiation Monitor," Rev. 3, dated September 14, 2007

• SOP Section VII, Procedure B-8, "Stack Particulate Monitor," Rev. 4, dated December 14, 2004

• SOP Section VII, Procedure B-13, "Portable Survey Instrument Calibration and Operability Check," Rev. 4, dated September 3, 1999

- 4 - * SOP Section VII, Procedure C-11, "Site Survey," Rev. 2, dated September 3, 1999 * SOP Section VII, Procedure C-12, "Facility Radiation Survey," Rev. 4, dated December 14, 2004

• SOP Section VII, Procedure C-14, "Facility Contamination Surveys," Rev. 4, dated December 14, 2004

• SOP Section VII, Procedure D-1, "Health Physics Training," Rev. 1, dated October 3, 1990

• SOP Section VII, Procedure E-1, "Personnel Dosimetry," Rev. 0, April 13, 1995 * SOP Section VII, Procedure F-1, "Facility Air Monitor Configurations," Rev. 0, dated May 10, 2000 b. Observations and Findings The inspector reviewed selected monthly and other contamination and radiation

surveys from 2015 through the present. The surveys had been completed by HP staff members as required, and were documented as required by procedures.

During tours of the facility, the inspector observed that caution signs, postings, and controls in the controlled areas were acceptable for the hazards involving radiation, high radiation, and contaminated areas and were posted as required by 10 CFR Part 20, Subpart J. Through observations of and interviews with licensee staff, the inspector confirmed that personnel complied with the signs, postings, and controls. The facility's radioactive material storage areas were noted to be properly posted.

Copies of current notices to workers were posted in various areas in the facility, including the bulletin board in the hallway by each entrance to the facility, in the hallway of the Upper Research Level in the Reactor Building, and in the Lower Research Level of the Reactor Building. Radiological signs were typically posted at the entrances to controlled areas. Other postings also characterized the industrial hygiene hazards that were present in the areas as well. Caution signs, postings, and controls for radiation areas were as required in 10 CFR Part 20.

The inspector determined that the licensee used optically-stimulated luminescent (OSL) dosimeters for whole body monitoring of beta and gamma radiation exposure with an additional component to measure fast/thermal neutron radiation. The licensee used thermoluminescent dosimeter (TLD) finger rings for extremity monitoring. The inspector confirmed that dosimetry was being issued to staff and visitors as required by Nuclear Science Center (NSC) SOP Section VII, Procedure E, "Personnel Dosimetry." The dosimetry was supplied and processed by a National Voluntary Laboratory Accreditation Program accredited

vendor.

An examination of the OSL and TLD results indicating exposures to radiation at the facility for the past 2 years showed that the highest occupational doses, as

- 5 - well as doses to the public, were within 10 CFR Part 20 limitations. The records showed that the highest annual whole body exposure received by a single individual for 2015 was 620 millirem (mr) deep dose equivalent (DDE) and the highest annual whole body exposure received by a single individual for 2016 was

810 mr DDE.

Through direct observation the inspector determined that dosimetry was acceptably used by facility personnel. Also, exit frisking practices were in accordance with facility radiation protection requirements.

The calibration and periodic checks of the portable survey meters and radiation monitoring instruments were performed by the licensee's staff, Texas A&M calibration facilities, or certified contractors. The inspector confirmed that the licensee's calibration procedures and frequencies satisfied TS Section 4.3 and 10 CFR 20.1501(b) requirements.

The inspector reviewed selected NSC instrument calibrations done during 2015 and to date in 2016, and confirmed that the calibration of the portable survey meters in use had been completed as required. All instruments checked had current calibrations appropriate for the types and energies of radiation they were used to detect and/or measure. Calibrations of the permanently installed radiation area monitors and the facility air monitors were completed in accordance with requirements specified in TS Section 4.5 and the applicable procedures.

The licensee's Radiation Protection and ALARA programs were established in SOP Section VII, Procedure A-1, "Radiation Protection Program;" SOP Section VII, Procedure A-6, "ALARA;" and through various related HP procedures. The programs had been reviewed and approved as required. The Radiation Protection and ALARA programs contained instructions concerning organization, training, monitoring, personnel responsibilities, audits, record keeping, and reports. The ALARA program provided objectives for keeping doses as low as reasonably achievable, which were consistent with the guidance in 10 CFR Part 20.

The licensee reviewed the programs at least annually, as required by 10 CFR 20.1101(c). Review and oversight was provided by the Radiation Safety Officer with the assistance of the RSB. It was also noted that the HP procedures were reviewed annually, as required by procedure.

The inspector reviewed selected RWPs that had been written, used, and closed out during 2015-2016. It was noted that the controls specified in the RWPs were acceptable and applicable for the type of work being done. The RWPs had been initiated, reviewed, and approved as required.

- 6 - c. Conclusion The inspector determined that the Radiation Protection and ALARA programs, as implemented by the licensee, satisfied regulatory requirements because:

1. surveys were completed and documented acceptably to permit evaluation of the radiation hazards present 2. postings met regulatory requirements 3. personnel dosimetry was being worn as required and recorded doses were within the NRC's regulatory limits 4. radiation survey and monitoring equipment was being maintained and calibrated as required, and 5. the Radiation Protection program satisfied regulatory requirements.

4. Effluents and Environmental Monitoring a. Inspection Scope (IP 69001)

The inspector reviewed the following to verify compliance with the requirements of 10 CFR Part 20 and TS Sections 3.5, 3.7, 4.5, 5.4, and 6.6:

• Effluent monitoring program results for 2015 and 2016

• Various gamma spectrum analyses for 2015 and 2016

• Counting and analysis records associated with airborne releases

• Annual Report for the Texas A&M University Nuclear Science Center for 2014 and 2015, including the effluent monitoring program results for that period * SOP Section VII, Procedure B-8, "Stack Particulate Monitor," Rev. 4, dated December 14, 2004

• SOP Section VII, Procedure B-9, "Stack Gas (Ar-41) Monitor," Rev. 4, dated December 14, 2004

• SOP Section VII, Procedure B-9A, "Stack Gas (Xe-125) Monitor," Rev. 1, dated December 14, 2004

• SOP Section VII, Procedure B-10, "Reactor Building Particulate Monitor," Rev. 6, dated December 14, 2004

• SOP Section VII, Procedure B-11, "Reactor Building Gas Monitor," Rev.

5, dated December 14, 2004

• SOP Section VII, Procedure B-12, "Fission Product Monitor," Rev. 4, dated September 14, 2007

• SOP Section VII, Procedure B-13, "Portable Survey Instrument Calibration," Rev. 4, dated September 3, 1999

• SOP Section VII, Procedure B-16, "Calibration of Gas Flow Proportional Counter," Rev. 4, dated December 19, 1997

• SOP Section VII, Procedure B-18, "Environmental Surveillance Program," Rev. 2, dated September 14, 2007

• SOP Section VII, Procedure C-8, "Radioactive Liquid Waste System," Rev. 3, dated May 10, 2000

- 7 - * SOP Section VII, Procedure C-9, "Radioactive Liquid Waste Disposal," Rev. 4, dated May June 11, 2011

• HP Form 819b, "Radioactive Liquid Waste Sewer Disposal Record," latest form revision dated September 8, 2008 b. Observation and Findings On-site and off-site gamma radiation monitoring was completed using the reactor facility stack effluent monitor and area monitors, and various environmental

monitoring TLDs.

The Texas Department of Health Services provided environmental results of the continuous radiation monitors in the unrestricted areas surrounding the Nuclear Science Center. Data indicated that there were no measurable doses above

regulatory limits.

The inspector determined that gaseous releases continued to be monitored as required, were calculated according to established protocol, and were acceptably documented in the annual reports. The airborne concentrations of the gaseous releases were well within the annual dose constraints of 10 CFR 20.1101(d),

Appendix B concentrations, and TS limits. COMPLY code calculations indicated an effective dose equivalent to the public of 0.1 mr/year for 2014 and 4.1x10-4 mr/year for 2015.

The Radiological Safety Officer reviewed and approved the liquid effluent releases after analysis, this was done to verify that the releases met regulatory requirements for discharge. The inspector reviewed radioactive liquid effluent sewer release data which indicated that the total activity released was below regulatory limits. The 2014 annual dose calculated from liquid effluent was 1.38 mr and 0.96 mr for 2015. The principles of ALARA were acceptably implemented to minimize radioactive releases. Monitoring equipment was acceptably maintained and calibrated.

c. Conclusion Effluent monitoring satisfied TS and regulatory requirements and releases were within the specified regulatory limits. The environmental monitoring program was acceptable.

5. Design Change Functions a. Inspection Scope (IP 69001)

To determine whether modifications to the facility, if any, were consistent with 10 CFR 50.59, the inspector reviewed:

- 8 - * RSB meeting minutes from 2015 through the present (RSB meeting numbers 173-182)

• Annual Report for the Texas A&M University Nuclear Science Center for 2014, dated August 2015

• Annual Report for the Texas A&M University Nuclear Science Center for 2015, dated March 2016

• SOP,Section I, Procedure H, "Reactor Safety Board," dated August 19, 2003 * Modification authorizations numbered 1-60 b. Observations and Findings The inspector determined that design changes at the NSCR facility required a facility staff review followed by an RSB review and subsequent approval. No design changes had been processed during the past 2 years. From the inspector's review, it was determined that 10 CFR 50.59 reviews and approvals were focused on safety and met licensee program requirements. No safety significant issues were noted during the review and the modifications completed by the licensee did not involve a change to the TS. The latest modification done at the facility was the replacement of the demineralizer system.

c. Conclusion The licensee's design change program was being implemented as required.

8. Committees, Audits, and Review a. Inspection Scope (IP 69001)

To verify that the licensee had established and conducted reviews and audits as required in TS 6.2, the inspector reviewed:

• Completed audits and reviews from 2015 thru 2016 to date

• RSB meeting minutes from 2015 through the present (RSB meeting numbers 173-182)

• NSC HP Review and ALARA Audit, dated September 25, 2016,

• Annual Report for the Texas A&M University Nuclear Science Center for 2014, dated August 2015

• Annual Report for the Texas A&M University Nuclear Science Center for 2015, dated March 2016

• SOP,Section I, Procedure H, "Reactor Safety Board," dated August 19, 2003 * RSB Charter dated July 2015

- 9 - b. Observations and Findings The inspector reviewed minutes of the last ten RSB meetings. The minutes showed that the committee met the once per calendar year as required by TS 6.2.2.a and that a quorum was present for each meeting. During 2015 RSB meetings were held on a monthly basis. The topics considered during the meetings were appropriate and as stipulated in TS Section 6.2.3. TS Section 6.2.4 requires that the RSB or a subcommittee thereof shall audit reactor operations and the radiation protection programs at least quarterly, but at intervals not to exceed 4 months. Audits shall include, but are not limited to, the

following:

Facility operations, including radiation protection, for conformance to the TS, applicable license conditions, and SOPs at least once per calendar year (interval between audits not to exceed 15 months)

The retraining and requalification program for the operating staff at least

once per calendar year (interval bet ween audits not to exceed 15 months)

The facility security plan and records at least once per calendar year (interval between audits not to exceed 15 months)

The reactor facility emergency plan and implementing procedures at least

once per calendar year (interval bet ween audits not to exceed 15 months)

The inspector reviewed the documentation and results of the audits that had been conducted by the RSB from 2015 through the present. The licensee had identified, and the inspector confirmed, that an audit of the facility operations including the radiation protection program, the facility emergency plan and the security plan had been conducted per TS requirements.

c. Conclusion The RSB acceptably completed review and oversight functions required by TS Section 6.2.

7. Transportation a. Inspection Scope (IP 86740)

The inspector interviewed licensee personnel and reviewed the following records to verify compliance with regulatory and procedural requirements for shipping licensed radioactive material:

• Licenses of shipment recipients

• Training records of those qualified to ship radioactive material

- 10 - * Selected records of various types of radioactive material shipments documented on various forms, including NSC Form 514, 852, and 854

• SOP Section VII, Procedure C-1, "HP Maintenance and Surveillance," Rev. 3, dated September 3, 1999

• SOP Section VII, Procedure C-2, "Radioactive Materials Control," Rev. 3, dated December 14, 2004

• SOP Section VII, Procedure C-3, "Radioactive Materials Released From the NSC License," Rev. 2, dated December 12, 1997

• SOP Section VII, Procedure C-5, "Radioactive Material Received," Rev. 3, dated December 19, 1997

• SOP Section VII, Procedure C-10, "Radioactive Material Handling," Rev. 2, dated December 19, 1997

• SOP Section VII, Procedure C-7, "Radioactive Solid Waste Sorting," Rev. 4, dated December 14, 2004 b. Observations and Findings Through records review and discussions with licensee personnel, the inspector determined that the licensee had shipped various types of radioactive material since the previous inspection in this area. A review of the records of selected shipments indicated that the radioisotope types and quantities were calculated and dose rates measured as required. All radioactive material shipment records reviewed by the inspector had been completed in accordance with the applicable DOT and NRC regulations.

The inspector verified that the licensee maintained copies of shipment recipients' licenses to possess radioactive material as required and that the licenses were verified to be current prior to initiating a shipment. The licensee maintained files of the Certificate of Compliance for shipping containers provided by outside companies. The training of the staff members responsible for shipping the material was also reviewed. The inspector verified that the shippers' training met DOT requirements. The training program appeared to be extensive and conducted properly.

It is of note that the licensee had made 437 shipments in 2015 and 279 shipments to date for 2016.

c. Conclusion Radioactive material was being shipped in accordance with the applicable regulations. The training of the staff members responsible for shipping the radioactive material met DOT requirements.

8. Exit Interview The inspector presented the inspection results to Texas A&M NSC staff at the conclusion of the inspection on December 15, 2016. The inspector described the areas

- 11 - inspected and discussed in detail the inspection observations. 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

S. McDeavitt Director, Nuclear Science Center J. Newhouse Associate Director A. Booth Radiation Safety Officer

INSPECTION PROCEDURES USED IP 69001 Class II Non-Power Reactors IP 86740 Transportation

ITEMS OPENED, CLOSED, AND DISCUSSED Opened None Closed None LIST OF ACRONYMS USED 10 CFR Title 10 of the Code of Federal Regulations ALARA As Low As Reasonably Achievable DDE Deep Dose Equivalent DOT Department of Transportation HP Health Physics IP Inspection Procedure mr Millirem NSC Nuclear Science Center NSCR Nuclear Science Center Reactor NRC U.S. Nuclear Regulatory Commission OSL Optically-Stimulated Luminscent PCN Procedure Change Notice RSB Reactor Safety Board RWP Radiation Work Permit SOP Standard Operating Procedure TLD Thermoluminescent Dosimeter TS Technical Specifications