ML16063A264

Texas A&M Univ. - Supplement to License Amendment Request Dated October 14, 2015

ML16063A264
Person / Time
Site:	05000128
Issue date:	03/03/2016
From:	McDeavitt S M Texas A&M Univ
To:	Alexander Adams, Patrick Boyle Document Control Desk, Office of Nuclear Reactor Regulation
References
2016-0011
Download: ML16063A264 (14)

Text

NUCLEAR SCIENCE CENTER 1Nuclear Science Center1095NuclearScienceRoad,3575TAMUCollegeStation,TX778433575Tel. (979) 845-7551 Dr. Sean M. McDeavitt Director, TEES Nuclear Science Center Texas A&M University Texas A&M Engineering Experiment Station 1095 Nuclear Science Road, 3575 TAMU College Station, TX 77843-3575 March 3, 2016 2016-0011 Ref: 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555

SUBJECT:

SUPPLEMENT TO LICENSE AMENDMENT REQUEST DATED OCTOBER 14, 2015, FACILITY LICENSE R-83, DOCKET NUMBER 50-128. (ADAMS ACCESSION NO. ML15287A148) Attn: Mr. Alexander Adams, Jr., Chief, Research and Test Reactors Branch Office of Nuclear Reactor Regulation Mr. Patrick M. Boyle, Project Manager, Research and Test Reactors Branch Office of Nuclear Reactor Regulation The purpose of this letter is to provide supplemental information to clarify and enhance the October 14, 2015 license amendment request (LAR) and revised License and Technical Specification pages (ADAMS Accession No. ML15287A148), the subsequent Request for Additional Information (RAI) dated November 2, 2015 (ADAMS Accession No. ML15302A018), and the Texas A&M Engineering Experiment Station (TEES) response dated November 18, 2015 (ADAMS Accession No. ML15322A354). The October 14, 2015 license amendment request was submitted to change the licensing basis for the NSC Facility and amend the License and Technical Specifications to allow the receipt, possession, but not use of the AGN-201M SNM in the NSC Fuel Storage Vault. Information provided in the RAI response and this supplement does not change the conclusions reached relative to the significant hazards consideration and the environmental impact.

Movement of the AGN-201M will occur in two distinct phases: the first is to relocate the fuel and other special nuclear material (SNM) from the current AGN location to the NSC Fuel Storage Vault and the second is to remove all remaining AGN-201M components to the NSC site for long term storage while the project plan to construct a new reactor facility to house the reconstructed AGN-201 M reactor is implemented. The fuel and other SNM, together with associated byproduct material (e.g., fission and activation products in the fuel), will be received, possessed, but not used under the NSC Facility Operating License No. R-83. Byproduct material not contained in or on fuel-bearing components will continue to be possessed under the AGN-201M Facility Operating License R-23 during storage on the NSC site. This point is addressed further in the LAR for the AGN-201 M Facility Operating License No. R-23 submitted on November 11, 2015 (ADAMS Accession No. ML 1531 A027). TEES is seeking approval of the October 14, 2015 license amendment request by the end of March 2016. TEES believes this short time to review the License and Technical Specification Change Request is achievable as this request contains no increased risk or impact above the currently designed, analyzed, and approved NSC reactor license. TEES notes that the proposed receipt, possession, but not use, of the AGN-201 M fuel and other SNM at the TEES NSC facility does not constitute a concern to public health and safety. Prior to undertaking efforts to support the engineering, design and construction of a new building to house the reconstructed AGN-201 M, several important actions must be completed. One action to be resolved in the near term is bringing closure to the July 30, 2013 Confirmatory Action Letter No. EA-2013-154 (ADAMS Accession No. ML 13189A058). Secondly, the ongoing License Renewal efforts should be put on hold until the efforts associated with the new building can be merged with the License Renewal completion efforts. Third, the AGN-201 M License and the NSC Facility License each have a Safety Analysis Report (SAR) which is required to be updated to reflect the current configuration of each reactor. Once the AGN-201 M has been relocated to the NSC Facility site, both SARs shall be revised to reflect the changes, as required by 10 CFR 50.71(e). Should you have any questions regarding the information provided in this submittal, please contact me or Mr. Jerry Newhouse at (979) 845-7551 or via email at mcdeavitt@tamu.edu or newhouse@tamu.edu. Oath of Affirmation I declare under penalty of perjury that the foregoing is true and correct to the best of my knowledge. Sinc71y, /0--/71. / /. Sean M. McDeavitt, PhD. Director, TEES Nuclear Science Center

Attachment:

Supplemental Information

Enclosures:

1A Current License 1 B Proposed License Changes 2A Current Technical Specification 28: Proposed Technical Specification Changes 2 Nuclear Science Center 1095 Nuclear Science Road, 3575 TAMU College Station, TX 77843-3575 Tel. (979) 845-7551 3Nuclear Science Center1095NuclearScienceRoad,3575TAMUCollegeStation,TX778433575Tel. (979) 845-7551cc:

Mr. William Dean, Office Director United States Nuclear Reactor Commission Office of Nuclear Reactor Regulation

Mr. Michael Young, President Texas A&M University 1246 TAMU College Station, TX 77843-1246 Dr. M. Katherine Banks, Vice Chancellor and Dean Dwight Look College of Engineering 3126 TAMU College Station, TX 77843-3126 Dr. Dimitris Lagoudas, Deputy Director Texas A&M Engineering Experiment Station 3470 TAMU College Station, TX 77843-3577 Dr. Costas Georghiades, Associate Agency Director Texas A&M Engineering Experiment Station 3470 TAMU College Station, TX 77843-3577 Dr. Yassin Hassan, Department Head Nuclear Engineering Texas A&M University Nuclear Engineering Department 3133 TAMU College Station, TX 77843-3133

Dr. John Hardy Reactor Safety Board Chairman Texas A&M University 3255 TAMU College Station, TX 77843-3255

Dr. Latha Vasudevan Radiological Safety Officer Texas A&M University Environmental Health and Safety 1111 Research Parkway College Station, TX 77843-4472 Mayor, City of College Station P.O. Box Drawer 9960 College Station, TX 77840-3575

Governor's Budget and Policy Office P.O. Box 12428 Austin, TX, 78711-2428 Radiation Program Officer Bureau of Radiation Control Dept. of State Health Services Division for Regulatory Services 1100 West 49th St., MC 2828 Austin, TX 78756-3189

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 P.O. Box 118300 University of Florida Gainesville, FL 32611-8300 Mr. Jerry Newhouse, NSC Assistant Director Texas A&M Engineering Experiment Station 3575 TAMU College Station, TX 77843-3575 Mr. Scott Miller, NSC Manager of Reactor Operations Texas A&M Engineering Experiment Station 3575 TAMU College Station, TX 77843-3575 Mr. Jeremy Osborn AGN-201M Reactor Supervisor Texas A&M University Nuclear Engineering Department 3133 TAMU College Station, TX 77843-3133 4Nuclear Science Center1095NuclearScienceRoad,3575TAMUCollegeStation,TX778433575Tel. (979) 845-7551Supplemental Information to License Amendment Request dated October 14, 2015, Facility License R-83, Docket Number 50-128. (ADAMS Accession No. ML15287A148)

Relocation and storage of a nuclear reactor is a rare occurrence. To assist with preparations to relocate and store the AGN-201M reactor, Texas A&M University/Texas A&M Engineering Experiment Station (TAMU/TEES) has reviewed a similar possession approval requested and granted to the Oregon State University (OSU) facility for storage of its AGN-201 fuel in their TRIGA Reactor Fuel Storage Vault. The planned activity includes requesting the AGN-201M special nuclear material (SNM) be received, possessed, but not used in the NSC Fuel Storage Vault. This requires approval of the October 14, 2015 License Amendment. The duration of the storage of the fuel and special nuclear materials in the NSC Fuel Storage Vault will be no longer than 5 years, to allow for approval of the Construction Permit and completion of construction of a new building adjacent to the NSC site. Once the new facility is completed, and pending receipt of Commission approval, the AGN-201M reactor will be assembled in its new licensed location. TAMU AGN-201M fuel and other SNM contained in the TEES NSC Fuel Storage Vault will be relocated to the new AGN-201M reactor facility for installation. This will reconstitute the original reactor licensing basis.

The following information has been generated to supplement the Amendment Request of October 14, 2015. Information obtained from experts in this field and discussions with NRC Staff have led to the conclusion that enhancement is required to ensure the docket is complete and easily reviewable by the NRC staff. The SAR will be updated to reflect this information upon approval of the October 14, 2015, amendment request to address the receipt, possession, but not for use, of the AGN-201M fuel, special nuclear materials and components. The current AGN-201M Safety Analysis Report uses multiple terms when referring to the reactor fuel and the control rods. This will be addressed further in the next revision to the SAR and in coordination with the License and Technical Specifications.

The purpose of the October 14, 2015 License Amendment is to allow the TEES NSC facility to receive, possess, but not use the AGN-201M fuel, SNM, and components currently authorized under license R-23, Docket 50-59. The storage of all components will be in accordance with the current NSC license basis. Enclosures 1A and 1B are the current and proposed NSC License pages. Enclosures 2A and 2B are the current and proposed NSC Technical Specification pages that address receipt, possession, but not use, of the AGN-201M fuel, SNM, and components. The following sections contain additional clarification for issues associated with receipt, possession, but not use, of the AGN-201M fuel, SNM and components at the NSC facility.

Security Plan:

TEES has reviewed the NSC (TEES) Security Plan and finds that the proposed changes to allow TEES to receive, possess, but not use the AGN-201M fuel, SNM and components at the NSC facility does not constitute a change or decrease of the safeguards effectiveness of the NSC (TEES) Security Plan in accordance with 10 CFR 50.54 (p)(1,2), and does not require prior NRC review and approval. TEES will maintain all records of any proposed changes to the NSC Security Plan in accordance with 10 CFR 50.54 (p)(1,2). Accordingly, no changes to the NSC (TEES) Security Plan are required.

5Emergenc TEES hasallow TEEcomponenthe event no change Use of the TEES is p(ADAMS Adated Novinformationstorage vaconservati unnecessain the origdefense-inreactivity im

Figure 1. y Plan: s reviewed tES to receivnts does not of a radiologes to the currterm borateproviding theAccession November 2, 2n pertains toault and the vely calculaary for the saginal NSC fun-depth provmpact from tNominathe NSC (Te, possess,result in redgical emergrent NSC (Ted aluminume following o. ML15322A2015 (ADAMo Item 1 conuse of a borted for the tafe storage uel storage ision in the sthis materialal configuratiEES) Emerg but not usducing the caency, in accEES) Emergm is not discuinformation A354) to theMS Accessionncerning rearated aluminwo 5-gallonof the AGNvault designstorage druml is not crediion of the stogency Plan se the AGN-apability to pcordance witgency Plan aussed in the supplemene NRC Staffn No. ML15activity of thenum neutronSNM storag-201M fuel. n, borated ams in a manted in the reorage drumsand finds t-201M fuel, perform an eth 10 CFR 5are requiredSAR: ntal to the Nf Request fo5302A018). Me stored AGn absorber. Gge drums, thSimilar to thaluminum wners shown eactivity calcs to be used1095NucCthat the prospecial nucemergency p50.54 (q) (iv. November 1or AdditionaMore specifiGN-201M fueGiven the lohe use of bohe use of thill be utilizeschematicaculations shod for SNM stoNuclear SciencclearScienceRoad,3CollegeStation,TX7Tel. (979)posed chanclear materplanning funcv) (3). Accor8, 2015 resl Informationically, the foel in the NSow reactivity orated alumie cadmium d as an addally in Fig.1, own below.orage. ce Center3575TAMU778433575845-7551nges to ial and ction in rdingly, sponse n (RAI) ollowing SC fuel values inum is sheets ditional but the 6Nominal sthicknessecylinder fitinformationpossession TEES is presponse clocation. Aborated al storage co14.3" outsgasket. Thone at 310drum.

Figure 2.

specificationes ranging ftted to the inn upon appn, but not usproviding theconcerning cAs noted abuminum liniontainers (boide diametehe fuel plate0 g). Note tDesign s for the ifrom approxnside wall ofproval of thse, of the AGe following icalculation obove, TEES ng that will olted-ring druer, 10.4" outs will be sehat the coredrawing of tnserts incluximately 1/8f the drum (he October GN-201M fuenformation sof reactivity will not takbe placed ums) have thtside height,parated intoe thermal futhe 5-gallon ude aluminu8" to 3/8", T(Fig. 1). The14, 2015 ael special nusupplementaof the storedke credit foinside the 5he following, with 20 gao 2 roughly euse containindrums to beum containinTop and boe NSC SAR amendmentuclear materal to the Nod AGN-201Mr the prese5-gallon sto nominal spauge wall thequal stacksng 0.4 g 235e used for SN1095NucCng 16% (oottom absor will be updt request toials and comovember 18M fuel in theence of the rage containpecifications hickness, ans for packag5U will be plNM storage.Nuclear SciencclearScienceRoad,3CollegeStation,TX7Tel. (979)r greater) Brber plates, dated to refleo address rmponents. , 2015 RAIe NSC fuel sneutron-absners. The 5(refer to Fignd a 3/8" diaging (one at laced in the. ce Center3575TAMU778433575845-7551B4C at and a ect this receipt, Item 1 storage sorbing 5-gallon gure 2): ameter 312 g, 310 g 7Nuclear Science Center1095NuclearScienceRoad,3575TAMUCollegeStation,TX778433575Tel. (979) 845-7551Description of storage drums and proposed storage layout A nominal quantity of 312 grams of fissile AGN-201M fuel has been modeled in one of these drums under the following conditions: in air and reflected by 12" of concrete, and reflected by 12" of water and by 12" of concrete. The results are presented in the following table. An additional calculation for 9 fuel plates (as described in the SAR and discussed in the November 18, 2015 response to RAI item 1) in a single right cylindrical stack, reflected by 12" of water and 12" of concrete was also performed with a resulting keff = 0.8945. This result approximates the outcome of stacking two drums containing all of the AGN-201M fuel plates without an air gap. The reactivity calculations performed represent very conservative bounding estimates, as demonstrated by an estimate of the reactivity of the nine fuel plates in the AGN-201M reactor with all control rods inserted. The resulting reactivity value (keff = 1.0760) is very conservative relative to the excess reactivity margin described in the Safety Evaluation Report (keff = 1.005), and is the result of simplifying assumptions used for the SCALE/KENO-VI calculations. This includes using a fuel concentration averaged over the external volume of the stacked fuel plates without modeling the voids for control rod drive mechanisms and the glory hole penetration.

Scenario # configuration keff +/- 1 312 g fuel in can, 12" air 0.5339 0.0018 2 312 g fuel in can, with 12" water +12" concrete 0.6665 0.0024 3 9 fuel plates, single stack, 12" water + 12" concrete (represents stacked drums) 0.8945* 0.0023 TEST 665 g fuel (all control rods inserted) in Al core tank, with graphite reflector, lead shield, Fe reactor tank, and water-filled Fe outer shield tank 1.0760 0.0019

• The Hazard Summary Report for the AGN-201 reactor predicts a 5% to 10% reduction in reactivity from a nominal 2" air gap between the upper and lower core halves. (ANL-6510, page 9). Given the stacked drums have the potential to exceed the reactivity limit of keff = 0.8 specified in Technical Specification 5.6, item 1, the two drums will be placed in opposite corners of the NSC fuel storage vault with and secured to the lower TRIGA fuel storage tubes (empty) using cable, chain, or similar methods, and locked.

Horizontal spacing of the two drums has been further evaluated using the solid angle assessment method presented in TID-7016, Rev 2, Nuclear Safety Guide. Using a conservative keff of 0.7 and the nominal drum dimensions, the allowed solid angle must be <2 steradians and is met with the drums even at very close distances (e.g., with an air gap < 1 foot). A revised proposed minimum center-to-center separation distance of 10 feet is sufficient to consider the storage drums uncoupled for nuclear safety considerations and allows flexibility for drum inspections.

Figure 3 illustrates the proposed positions of SNM-bearing components in the NSC fuel storage vault, with the exception of the 239PuBe source. To maintain personnel exposures ALARA, this source will be stored in a neutron-attenuating shield and placed in a location within the fuel storage vault, as approved by site Radiation Safety Officer.

8Figure 3.

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10Enclosure 1A TEXAS ENGINEERING EXPERIMENT STATION/TEXAS A&M UNIVERSITY SYSTEM DOCKET NO. 50-128 FACILITY OPERATING LICENSE License No. R-83 A. This license applies to the Texas Engineering Experiment Station/Texas A&M University System Nuclear Science Center [herein "the facility"] TRIGA-type nuclear research reactor owned by the Texas Engineering Experiment Station/Texas A&M University System [herein "the licensee"], located on the campus of Texas A&M University at College Station, Texas, and described in the licensee's application for license renewal, dated February 27, 2003, as supplemented. B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses the Texas Engineering Experiment Station/Texas A&M University System as follows: 1. Pursuant to subsection 104c of the Act and 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," to possess, use, and operate the facility as a utilization facility at the designated location in accordance with the procedures and limitations described in the application and set forth in this license. 2. Pursuant to the Act and 10 CFR Part 70, the following activities are included: a. to receive, possess, and use, but not separate, in connection with the operation of the facility, up to 15 kilograms of contained uranium-235 enriched to less than 20 percent in the form of TRIGA-type reactor fuel; b. to receive, possess, and use, but not separate, in connection with the operation of the facility, up to 40 grams total of special nuclear material, of any enrichment, in the form of detectors, fission plates, foils, and solutions; and, c. to receive, possess, and use, but not separate, in connection with the operation of the facility, such special nuclear material as may be produced by the operation of the facility. 3. Pursuant to the Act and 10 CFR Part 30, the following activities are included: a. to receive, possess, and use, in connection with the operation of the facility, a sealed antimony-beryllium neutron startup source, b. to receive, possess, and use, in connection with the operation of the facility, a sealed 2.5-curie americium-beryllium neutron source; and, c. to receive, possess, and use, in connection with operation of the facility, such byproduct material as may be produced by operation of the reactor, which can not be separated except for byproduct material produced in reactor experiments.4. Pursuant to the Act and 10 CFR Part 40, "Domestic Licensing of Source Material," to receive, possess, and use in connection with operation of the facility, not more than 6.8 kilograms of source material.

11Enclosure 1B PROPOSED LICENSE CHANGE FOR THE NSC FACILITY TEXAS ENGINEERING EXPERIMENT STATION/TEXAS A&M UNIVERSITY SYSTEM DOCKET NO. 50-128 FACILITY OPERATING LICENSE License No. R-83 As Amended Through Amendment No. XX A. This license applies to the Texas Engineering Experiment Station/Texas A&M University System Nuclear Science Center [herein "the facility"] TRIGA-type nuclear research reactor owned by the Texas Engineering Experiment Station/Texas A&M University System [herein "the licensee"], located on the campus of Texas A&M University at College Station, Texas, and described in the licensee's application for license renewal, dated February 27, 2003, as supplemented. B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses the Texas Engineering Experiment Station/Texas A&M University System as follows: 1. Pursuant to subsection 104c of the Act and 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," to possess, use, and operate the facility as a utilization facility at the designated location in accordance with the procedures and limitations described in the application and set forth in this license. 2. Pursuant to the Act and 10 CFR Part 70, the following activities are included: a. to receive, possess, and use, but not separate, in connection with the operation of the facility, up to 15 kilograms of contained uranium-235 enriched to less than 20 percent in the form of TRIGA-type reactor fuel; b. to receive, possess, and use, but not separate, in connection with the operation of the facility, up to 40 grams total of special nuclear material, of any enrichment, in the form of detectors, fission plates, foils, and solutions; and, c. to receive, possess, and use, but not separate, in connection with the operation of the facility, such special nuclear material as may be produced by the operation of the facility. d. To receive, possess, but not use up to 0.7 Kilograms of contained Uranium-235 as AGN-201M <20% enriched 235U reactor fuel, and actinides and activation products for up to 5 years from the date of issuance of license amendment xx. e. To receive, possess, but not use up to 0.020 kilograms of 239Pu as a 239PuBe sealed neutron start-up source in connection with storage of the AGN-201M reactor for up to 5 years from the date of issuance of license amendment xx. _______________ Date-2016 123. Pursuant to the Act and 10 CFR Part 30, the following activities are included: a. to receive, possess, and use, in connection with the operation of the facility, a sealed antimony-beryllium neutron startup source, b. to receive, possess, and use, in connection with the operation of the facility, a sealed 2.5-curie americium-beryllium neutron source; and,

c. to receive, possess, and use, in connection with operation of the facility, such byproduct material as may be produced by operation of the reactor, which cannot be separated except for byproduct material produced in reactor experiments.

d. to receive, possess, but not use, byproduct materials including contaminated or activated AGN-201M reactor components for up to 5 years from the date of issuance of amendment xx. __________ Date-2016 13Enclosure 2A CURRENT TECHNICAL SPECIFICATION FOR THE TEES NSC FACILITY The current NSC reactor Technical Specification affected is Section 5.6 titled, "Fuel Storage" which follows. The proposed new Technical Specification has a vertical line indicating the changes made to the existing Technical Specification: 5.6 Fuel Storage Applicability This specification applies to the storage of reactor fuel at times when it is not in the reactor core. Objective The objective is to ensure that fuel that is being stored will not become critical and will not reach an unsafe temperature. Specification 1. All fuel elements and fueled devices shall be stored in a geometrical array for which the k-effective is less than 0.8 for all conditions of moderation and reflection.

2. Irradiated fuel elements and fueled devices shall be stored in an array, which will permit sufficient natural convection cooling by water or air such that the fuel element or fueled device temperature will not exceed design values. Basis The limits imposed by Specifications 5.6.1 and 5.6.2 are conservative and ensure safe storage.

14Enclosure 2B Proposed Technical Specification Change TEES recommends the following replacement Technical Specification change containing wording to support this LAR is as follows:

5.6 Fuel Storage Applicability This specification applies to the storage of reactor fuel at times when it is not in the reactor core. This includes the combined 235U fissile mass of no more than 0.7 kilograms, actinides and activation products, and the 239PuBe neutron start-up source with a 239Pu fissile mass of no more than 20 grams, from the TAMU AGN-201M reactor.

Objective The objective is to ensure that fuel that is being stored will not become critical and will not reach an unsafe temperature.

Specification 1. All fuel elements and fueled devices shall be stored in a geometrical array for which the k-effective is less than 0.8 for all conditions of moderation and reflection. 2. Irradiated fuel elements and fueled devices shall be stored in an array, which will permit sufficient natural convection cooling by water or air such that the fuel element or fueled device temperature will not exceed design values.

3. Possession of the AGN-201M fuel, and actinides and activation products and neutron start-up source is restricted to receipt, possession, but not use in the operation of the NSC reactor. Specification 2, above, is not applicable to these materials. Basis The limits imposed by Specifications 5.6.1, 5.6.2, and 5.6.3 are conservative and ensure safe storage. __________ Date-2016 __________ Date-2016 __________ Date-2016 NUCLEAR SCIENCE CENTER 1Nuclear Science Center1095NuclearScienceRoad,3575TAMUCollegeStation,TX778433575Tel. (979) 845-7551 Dr. Sean M. McDeavitt Director, TEES Nuclear Science Center Texas A&M University Texas A&M Engineering Experiment Station 1095 Nuclear Science Road, 3575 TAMU College Station, TX 77843-3575 March 3, 2016 2016-0011 Ref: 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555

SUBJECT:

SUPPLEMENT TO LICENSE AMENDMENT REQUEST DATED OCTOBER 14, 2015, FACILITY LICENSE R-83, DOCKET NUMBER 50-128. (ADAMS ACCESSION NO. ML15287A148) Attn: Mr. Alexander Adams, Jr., Chief, Research and Test Reactors Branch Office of Nuclear Reactor Regulation Mr. Patrick M. Boyle, Project Manager, Research and Test Reactors Branch Office of Nuclear Reactor Regulation The purpose of this letter is to provide supplemental information to clarify and enhance the October 14, 2015 license amendment request (LAR) and revised License and Technical Specification pages (ADAMS Accession No. ML15287A148), the subsequent Request for Additional Information (RAI) dated November 2, 2015 (ADAMS Accession No. ML15302A018), and the Texas A&M Engineering Experiment Station (TEES) response dated November 18, 2015 (ADAMS Accession No. ML15322A354). The October 14, 2015 license amendment request was submitted to change the licensing basis for the NSC Facility and amend the License and Technical Specifications to allow the receipt, possession, but not use of the AGN-201M SNM in the NSC Fuel Storage Vault. Information provided in the RAI response and this supplement does not change the conclusions reached relative to the significant hazards consideration and the environmental impact.

Movement of the AGN-201M will occur in two distinct phases: the first is to relocate the fuel and other special nuclear material (SNM) from the current AGN location to the NSC Fuel Storage Vault and the second is to remove all remaining AGN-201M components to the NSC site for long term storage while the project plan to construct a new reactor facility to house the reconstructed AGN-201 M reactor is implemented. The fuel and other SNM, together with associated byproduct material (e.g., fission and activation products in the fuel), will be received, possessed, but not used under the NSC Facility Operating License No. R-83. Byproduct material not contained in or on fuel-bearing components will continue to be possessed under the AGN-201M Facility Operating License R-23 during storage on the NSC site. This point is addressed further in the LAR for the AGN-201 M Facility Operating License No. R-23 submitted on November 11, 2015 (ADAMS Accession No. ML 1531 A027). TEES is seeking approval of the October 14, 2015 license amendment request by the end of March 2016. TEES believes this short time to review the License and Technical Specification Change Request is achievable as this request contains no increased risk or impact above the currently designed, analyzed, and approved NSC reactor license. TEES notes that the proposed receipt, possession, but not use, of the AGN-201 M fuel and other SNM at the TEES NSC facility does not constitute a concern to public health and safety. Prior to undertaking efforts to support the engineering, design and construction of a new building to house the reconstructed AGN-201 M, several important actions must be completed. One action to be resolved in the near term is bringing closure to the July 30, 2013 Confirmatory Action Letter No. EA-2013-154 (ADAMS Accession No. ML 13189A058). Secondly, the ongoing License Renewal efforts should be put on hold until the efforts associated with the new building can be merged with the License Renewal completion efforts. Third, the AGN-201 M License and the NSC Facility License each have a Safety Analysis Report (SAR) which is required to be updated to reflect the current configuration of each reactor. Once the AGN-201 M has been relocated to the NSC Facility site, both SARs shall be revised to reflect the changes, as required by 10 CFR 50.71(e). Should you have any questions regarding the information provided in this submittal, please contact me or Mr. Jerry Newhouse at (979) 845-7551 or via email at mcdeavitt@tamu.edu or newhouse@tamu.edu. Oath of Affirmation I declare under penalty of perjury that the foregoing is true and correct to the best of my knowledge. Sinc71y, /0--/71. / /. Sean M. McDeavitt, PhD. Director, TEES Nuclear Science Center

Attachment:

Supplemental Information

Enclosures:

1A Current License 1 B Proposed License Changes 2A Current Technical Specification 28: Proposed Technical Specification Changes 2 Nuclear Science Center 1095 Nuclear Science Road, 3575 TAMU College Station, TX 77843-3575 Tel. (979) 845-7551 3Nuclear Science Center1095NuclearScienceRoad,3575TAMUCollegeStation,TX778433575Tel. (979) 845-7551cc:

Mr. William Dean, Office Director United States Nuclear Reactor Commission Office of Nuclear Reactor Regulation

Mr. Michael Young, President Texas A&M University 1246 TAMU College Station, TX 77843-1246 Dr. M. Katherine Banks, Vice Chancellor and Dean Dwight Look College of Engineering 3126 TAMU College Station, TX 77843-3126 Dr. Dimitris Lagoudas, Deputy Director Texas A&M Engineering Experiment Station 3470 TAMU College Station, TX 77843-3577 Dr. Costas Georghiades, Associate Agency Director Texas A&M Engineering Experiment Station 3470 TAMU College Station, TX 77843-3577 Dr. Yassin Hassan, Department Head Nuclear Engineering Texas A&M University Nuclear Engineering Department 3133 TAMU College Station, TX 77843-3133

Dr. John Hardy Reactor Safety Board Chairman Texas A&M University 3255 TAMU College Station, TX 77843-3255

Dr. Latha Vasudevan Radiological Safety Officer Texas A&M University Environmental Health and Safety 1111 Research Parkway College Station, TX 77843-4472 Mayor, City of College Station P.O. Box Drawer 9960 College Station, TX 77840-3575

Governor's Budget and Policy Office P.O. Box 12428 Austin, TX, 78711-2428 Radiation Program Officer Bureau of Radiation Control Dept. of State Health Services Division for Regulatory Services 1100 West 49th St., MC 2828 Austin, TX 78756-3189

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 P.O. Box 118300 University of Florida Gainesville, FL 32611-8300 Mr. Jerry Newhouse, NSC Assistant Director Texas A&M Engineering Experiment Station 3575 TAMU College Station, TX 77843-3575 Mr. Scott Miller, NSC Manager of Reactor Operations Texas A&M Engineering Experiment Station 3575 TAMU College Station, TX 77843-3575 Mr. Jeremy Osborn AGN-201M Reactor Supervisor Texas A&M University Nuclear Engineering Department 3133 TAMU College Station, TX 77843-3133 4Nuclear Science Center1095NuclearScienceRoad,3575TAMUCollegeStation,TX778433575Tel. (979) 845-7551Supplemental Information to License Amendment Request dated October 14, 2015, Facility License R-83, Docket Number 50-128. (ADAMS Accession No. ML15287A148)

Relocation and storage of a nuclear reactor is a rare occurrence. To assist with preparations to relocate and store the AGN-201M reactor, Texas A&M University/Texas A&M Engineering Experiment Station (TAMU/TEES) has reviewed a similar possession approval requested and granted to the Oregon State University (OSU) facility for storage of its AGN-201 fuel in their TRIGA Reactor Fuel Storage Vault. The planned activity includes requesting the AGN-201M special nuclear material (SNM) be received, possessed, but not used in the NSC Fuel Storage Vault. This requires approval of the October 14, 2015 License Amendment. The duration of the storage of the fuel and special nuclear materials in the NSC Fuel Storage Vault will be no longer than 5 years, to allow for approval of the Construction Permit and completion of construction of a new building adjacent to the NSC site. Once the new facility is completed, and pending receipt of Commission approval, the AGN-201M reactor will be assembled in its new licensed location. TAMU AGN-201M fuel and other SNM contained in the TEES NSC Fuel Storage Vault will be relocated to the new AGN-201M reactor facility for installation. This will reconstitute the original reactor licensing basis.

The following information has been generated to supplement the Amendment Request of October 14, 2015. Information obtained from experts in this field and discussions with NRC Staff have led to the conclusion that enhancement is required to ensure the docket is complete and easily reviewable by the NRC staff. The SAR will be updated to reflect this information upon approval of the October 14, 2015, amendment request to address the receipt, possession, but not for use, of the AGN-201M fuel, special nuclear materials and components. The current AGN-201M Safety Analysis Report uses multiple terms when referring to the reactor fuel and the control rods. This will be addressed further in the next revision to the SAR and in coordination with the License and Technical Specifications.

The purpose of the October 14, 2015 License Amendment is to allow the TEES NSC facility to receive, possess, but not use the AGN-201M fuel, SNM, and components currently authorized under license R-23, Docket 50-59. The storage of all components will be in accordance with the current NSC license basis. Enclosures 1A and 1B are the current and proposed NSC License pages. Enclosures 2A and 2B are the current and proposed NSC Technical Specification pages that address receipt, possession, but not use, of the AGN-201M fuel, SNM, and components. The following sections contain additional clarification for issues associated with receipt, possession, but not use, of the AGN-201M fuel, SNM and components at the NSC facility.

Security Plan:

TEES has reviewed the NSC (TEES) Security Plan and finds that the proposed changes to allow TEES to receive, possess, but not use the AGN-201M fuel, SNM and components at the NSC facility does not constitute a change or decrease of the safeguards effectiveness of the NSC (TEES) Security Plan in accordance with 10 CFR 50.54 (p)(1,2), and does not require prior NRC review and approval. TEES will maintain all records of any proposed changes to the NSC Security Plan in accordance with 10 CFR 50.54 (p)(1,2). Accordingly, no changes to the NSC (TEES) Security Plan are required.

5Emergenc TEES hasallow TEEcomponenthe event no change Use of the TEES is p(ADAMS Adated Novinformationstorage vaconservati unnecessain the origdefense-inreactivity im

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specificationes ranging ftted to the inn upon appn, but not usproviding theconcerning cAs noted abuminum liniontainers (boide diametehe fuel plate0 g). Note tDesign s for the ifrom approxnside wall ofproval of thse, of the AGe following icalculation obove, TEES ng that will olted-ring druer, 10.4" outs will be sehat the coredrawing of tnserts incluximately 1/8f the drum (he October GN-201M fuenformation sof reactivity will not takbe placed ums) have thtside height,parated intoe thermal futhe 5-gallon ude aluminu8" to 3/8", T(Fig. 1). The14, 2015 ael special nusupplementaof the storedke credit foinside the 5he following, with 20 gao 2 roughly euse containindrums to beum containinTop and boe NSC SAR amendmentuclear materal to the Nod AGN-201Mr the prese5-gallon sto nominal spauge wall thequal stacksng 0.4 g 235e used for SN1095NucCng 16% (oottom absor will be updt request toials and comovember 18M fuel in theence of the rage containpecifications hickness, ans for packag5U will be plNM storage.Nuclear SciencclearScienceRoad,3CollegeStation,TX7Tel. (979)r greater) Brber plates, dated to refleo address rmponents. , 2015 RAIe NSC fuel sneutron-absners. The 5(refer to Fignd a 3/8" diaging (one at laced in the. ce Center3575TAMU778433575845-7551B4C at and a ect this receipt, Item 1 storage sorbing 5-gallon gure 2): ameter 312 g, 310 g 7Nuclear Science Center1095NuclearScienceRoad,3575TAMUCollegeStation,TX778433575Tel. (979) 845-7551Description of storage drums and proposed storage layout A nominal quantity of 312 grams of fissile AGN-201M fuel has been modeled in one of these drums under the following conditions: in air and reflected by 12" of concrete, and reflected by 12" of water and by 12" of concrete. The results are presented in the following table. An additional calculation for 9 fuel plates (as described in the SAR and discussed in the November 18, 2015 response to RAI item 1) in a single right cylindrical stack, reflected by 12" of water and 12" of concrete was also performed with a resulting keff = 0.8945. This result approximates the outcome of stacking two drums containing all of the AGN-201M fuel plates without an air gap. The reactivity calculations performed represent very conservative bounding estimates, as demonstrated by an estimate of the reactivity of the nine fuel plates in the AGN-201M reactor with all control rods inserted. The resulting reactivity value (keff = 1.0760) is very conservative relative to the excess reactivity margin described in the Safety Evaluation Report (keff = 1.005), and is the result of simplifying assumptions used for the SCALE/KENO-VI calculations. This includes using a fuel concentration averaged over the external volume of the stacked fuel plates without modeling the voids for control rod drive mechanisms and the glory hole penetration.

Scenario # configuration keff +/- 1 312 g fuel in can, 12" air 0.5339 0.0018 2 312 g fuel in can, with 12" water +12" concrete 0.6665 0.0024 3 9 fuel plates, single stack, 12" water + 12" concrete (represents stacked drums) 0.8945* 0.0023 TEST 665 g fuel (all control rods inserted) in Al core tank, with graphite reflector, lead shield, Fe reactor tank, and water-filled Fe outer shield tank 1.0760 0.0019

• The Hazard Summary Report for the AGN-201 reactor predicts a 5% to 10% reduction in reactivity from a nominal 2" air gap between the upper and lower core halves. (ANL-6510, page 9). Given the stacked drums have the potential to exceed the reactivity limit of keff = 0.8 specified in Technical Specification 5.6, item 1, the two drums will be placed in opposite corners of the NSC fuel storage vault with and secured to the lower TRIGA fuel storage tubes (empty) using cable, chain, or similar methods, and locked.

Horizontal spacing of the two drums has been further evaluated using the solid angle assessment method presented in TID-7016, Rev 2, Nuclear Safety Guide. Using a conservative keff of 0.7 and the nominal drum dimensions, the allowed solid angle must be <2 steradians and is met with the drums even at very close distances (e.g., with an air gap < 1 foot). A revised proposed minimum center-to-center separation distance of 10 feet is sufficient to consider the storage drums uncoupled for nuclear safety considerations and allows flexibility for drum inspections.

Figure 3 illustrates the proposed positions of SNM-bearing components in the NSC fuel storage vault, with the exception of the 239PuBe source. To maintain personnel exposures ALARA, this source will be stored in a neutron-attenuating shield and placed in a location within the fuel storage vault, as approved by site Radiation Safety Officer.

8Figure 3.

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10Enclosure 1A TEXAS ENGINEERING EXPERIMENT STATION/TEXAS A&M UNIVERSITY SYSTEM DOCKET NO. 50-128 FACILITY OPERATING LICENSE License No. R-83 A. This license applies to the Texas Engineering Experiment Station/Texas A&M University System Nuclear Science Center [herein "the facility"] TRIGA-type nuclear research reactor owned by the Texas Engineering Experiment Station/Texas A&M University System [herein "the licensee"], located on the campus of Texas A&M University at College Station, Texas, and described in the licensee's application for license renewal, dated February 27, 2003, as supplemented. B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses the Texas Engineering Experiment Station/Texas A&M University System as follows: 1. Pursuant to subsection 104c of the Act and 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," to possess, use, and operate the facility as a utilization facility at the designated location in accordance with the procedures and limitations described in the application and set forth in this license. 2. Pursuant to the Act and 10 CFR Part 70, the following activities are included: a. to receive, possess, and use, but not separate, in connection with the operation of the facility, up to 15 kilograms of contained uranium-235 enriched to less than 20 percent in the form of TRIGA-type reactor fuel; b. to receive, possess, and use, but not separate, in connection with the operation of the facility, up to 40 grams total of special nuclear material, of any enrichment, in the form of detectors, fission plates, foils, and solutions; and, c. to receive, possess, and use, but not separate, in connection with the operation of the facility, such special nuclear material as may be produced by the operation of the facility. 3. Pursuant to the Act and 10 CFR Part 30, the following activities are included: a. to receive, possess, and use, in connection with the operation of the facility, a sealed antimony-beryllium neutron startup source, b. to receive, possess, and use, in connection with the operation of the facility, a sealed 2.5-curie americium-beryllium neutron source; and, c. to receive, possess, and use, in connection with operation of the facility, such byproduct material as may be produced by operation of the reactor, which can not be separated except for byproduct material produced in reactor experiments.4. Pursuant to the Act and 10 CFR Part 40, "Domestic Licensing of Source Material," to receive, possess, and use in connection with operation of the facility, not more than 6.8 kilograms of source material.

11Enclosure 1B PROPOSED LICENSE CHANGE FOR THE NSC FACILITY TEXAS ENGINEERING EXPERIMENT STATION/TEXAS A&M UNIVERSITY SYSTEM DOCKET NO. 50-128 FACILITY OPERATING LICENSE License No. R-83 As Amended Through Amendment No. XX A. This license applies to the Texas Engineering Experiment Station/Texas A&M University System Nuclear Science Center [herein "the facility"] TRIGA-type nuclear research reactor owned by the Texas Engineering Experiment Station/Texas A&M University System [herein "the licensee"], located on the campus of Texas A&M University at College Station, Texas, and described in the licensee's application for license renewal, dated February 27, 2003, as supplemented. B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses the Texas Engineering Experiment Station/Texas A&M University System as follows: 1. Pursuant to subsection 104c of the Act and 10 CFR Part 50, "Domestic Licensing of Production and Utilization Facilities," to possess, use, and operate the facility as a utilization facility at the designated location in accordance with the procedures and limitations described in the application and set forth in this license. 2. Pursuant to the Act and 10 CFR Part 70, the following activities are included: a. to receive, possess, and use, but not separate, in connection with the operation of the facility, up to 15 kilograms of contained uranium-235 enriched to less than 20 percent in the form of TRIGA-type reactor fuel; b. to receive, possess, and use, but not separate, in connection with the operation of the facility, up to 40 grams total of special nuclear material, of any enrichment, in the form of detectors, fission plates, foils, and solutions; and, c. to receive, possess, and use, but not separate, in connection with the operation of the facility, such special nuclear material as may be produced by the operation of the facility. d. To receive, possess, but not use up to 0.7 Kilograms of contained Uranium-235 as AGN-201M <20% enriched 235U reactor fuel, and actinides and activation products for up to 5 years from the date of issuance of license amendment xx. e. To receive, possess, but not use up to 0.020 kilograms of 239Pu as a 239PuBe sealed neutron start-up source in connection with storage of the AGN-201M reactor for up to 5 years from the date of issuance of license amendment xx. _______________ Date-2016 123. Pursuant to the Act and 10 CFR Part 30, the following activities are included: a. to receive, possess, and use, in connection with the operation of the facility, a sealed antimony-beryllium neutron startup source, b. to receive, possess, and use, in connection with the operation of the facility, a sealed 2.5-curie americium-beryllium neutron source; and,

c. to receive, possess, and use, in connection with operation of the facility, such byproduct material as may be produced by operation of the reactor, which cannot be separated except for byproduct material produced in reactor experiments.

d. to receive, possess, but not use, byproduct materials including contaminated or activated AGN-201M reactor components for up to 5 years from the date of issuance of amendment xx. __________ Date-2016 13Enclosure 2A CURRENT TECHNICAL SPECIFICATION FOR THE TEES NSC FACILITY The current NSC reactor Technical Specification affected is Section 5.6 titled, "Fuel Storage" which follows. The proposed new Technical Specification has a vertical line indicating the changes made to the existing Technical Specification: 5.6 Fuel Storage Applicability This specification applies to the storage of reactor fuel at times when it is not in the reactor core. Objective The objective is to ensure that fuel that is being stored will not become critical and will not reach an unsafe temperature. Specification 1. All fuel elements and fueled devices shall be stored in a geometrical array for which the k-effective is less than 0.8 for all conditions of moderation and reflection.

2. Irradiated fuel elements and fueled devices shall be stored in an array, which will permit sufficient natural convection cooling by water or air such that the fuel element or fueled device temperature will not exceed design values. Basis The limits imposed by Specifications 5.6.1 and 5.6.2 are conservative and ensure safe storage.

14Enclosure 2B Proposed Technical Specification Change TEES recommends the following replacement Technical Specification change containing wording to support this LAR is as follows:

5.6 Fuel Storage Applicability This specification applies to the storage of reactor fuel at times when it is not in the reactor core. This includes the combined 235U fissile mass of no more than 0.7 kilograms, actinides and activation products, and the 239PuBe neutron start-up source with a 239Pu fissile mass of no more than 20 grams, from the TAMU AGN-201M reactor.

Objective The objective is to ensure that fuel that is being stored will not become critical and will not reach an unsafe temperature.

Specification 1. All fuel elements and fueled devices shall be stored in a geometrical array for which the k-effective is less than 0.8 for all conditions of moderation and reflection. 2. Irradiated fuel elements and fueled devices shall be stored in an array, which will permit sufficient natural convection cooling by water or air such that the fuel element or fueled device temperature will not exceed design values.

3. Possession of the AGN-201M fuel, and actinides and activation products and neutron start-up source is restricted to receipt, possession, but not use in the operation of the NSC reactor. Specification 2, above, is not applicable to these materials. Basis The limits imposed by Specifications 5.6.1, 5.6.2, and 5.6.3 are conservative and ensure safe storage. __________ Date-2016 __________ Date-2016 __________ Date-2016