ML062220278
| ML062220278 | |
| Person / Time | |
|---|---|
| Site: | 05000128 |
| Issue date: | 08/04/2006 |
| From: | Reece W Texas A&M Univ |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 2006-0069 | |
| Download: ML062220278 (5) | |
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TEXAS A&M UNIVERSITY 3575 TAMU COLLEGE STATION, TEXAS 77843-3575 NUCLEAR SCIENCE CENTER 979/845-7551 FAX 979/862-2667 August 4, 2006 2006-0069 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Subject:
Texas A&M University System Texas Engineering and Experiment Station Nuclear Science Center (TAMU NSC), Docket 50-128, License R-83 Corrections to Revised Tech Specs (RE: High-Enriched to Low Enriched Uranium Conversion for TAMU NSC)
The enclosed documents are corrections to the Proposed Technical Specifications for the Texas A&M University Conversion from HEU to LEU Fuel. Typographical errors were brought to our attention via telephone conversation with Alexander Adams, NRC Project Manager.
The enclosures include corrections to the following pages:
Table of Contents page 2 (Sections 1.37 - 5.4)
Page 9 (Sections 3.0 to 3.1.2)
If you have any questions me at 979-845-7551.
Sincerely, W. D. Reece Director, NSC xc: 2.1 1/central file A. Adams, NRC Project Manager RESEARCH AND DEVELOPMENT FOR MANKIND
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http://nsc.tamu edu
1.37 Shall, Should and M ay ....................................................................................................... 5 1.38 Shutdown M argin ....................................................................................................................... 6 1.39 Steady State M ode ............................................................. ;....................................................... 6 1.40 True V alue .................................................................................................................................. 6 1.41 U nscheduled Shutdown ..................................................................................................... 6 2.0 Safety Lim it and Limiting Safety System Setting ............................................................................... 7 2.1 Safety Limit Fuel Element Tem perature ................................................................................ 7 2.2 Limiting Safety System Setting ............................................................................................. 7 3.0 Lim iting Conditions for Operation ...................................................................................................... 9 3.1 Reactor Core Param eters ...................................................................................................... 9 3.1.1 Steady State Operation ........................................................................................... 9 3.1.2 Pulse M ode Operation .............................................................................................. 9 3.1.3 Shutdown M argin .................................................................................................. 10 3.1.4 Core Configuration Limitation ................................................................................... 11
- 3.1.5 Maximum Excess Reactivity.. .......... . ........................ ................... .1.1 3.2 Reactor Control and Safety System s .................................................................................... 12 3.2.1 Reactor Control Systems ....................................................................................... 12 3.2.2 Reactor Safety System s ......................................................................................... 12 3.2.3 Scram Time ................................................................................................................ 14 3.3 Confinem ent ............................................................................................................................. 14 3.3.1 Operations that Require Confinem ent .................................................................. 14 3.3.2 Equipment to Achieve Confinem ent .................................................................... 15 3.4 Ventilation System ................................................................................................................... 15 3.5 Radiation M onitoring Systems and Effluents ....................................................................... 16 3.5.1 Radiation M onitoring ........................................................................................... 16 3.5.2 Argon-41 Discharge Limit .................................................................................... 17 3.5.3 X enon and Iodine Monitoring ................................................................................ 17 3.6 Lim itations on Experim ents .................................................................................................. 18 3.6.1 Reactivity Limits .................................................................................................... 18 3.6.2 M aterial Limitations ............................................................................................. 18 3.6.3 Failures and M alfunctions .................................................................................... 20 3.6.4 Xenon Irradiation for Iodine Production .............................................................. 21 3.7 As Low As Reasonably Achievable (ALARA) Radioactive Effluents Released ................. 21 3.8 Primary Coolant Conditions ................................................................................................ 22 4.0 Surveillance Requirem ents ..................................................................................................................... 24 4.1 General ..................................................................................................................................... 24 4.2 Reactor Core Param eters .................................................................................................... 24 4.2.1 Steady State Operation .......................................... 24 4.2.2 Pulse M ode Operation ............................................................................................ 25 4.2.3 Shutdown M argin .................................................................................................. 25 4.2.4 Reactor Fuel Elements ........................................................................................... 25 4.3 Reactor Control And Safety System s .................................................................................. 27 4.3.1 Reactor Control System s ....................................................................................... 27 4.3.2 Reactor Safety Systems ......................................................................................... 27 4.3.3 Scram Time ................................................................................................................ 28 4.4 Equipment to Achieve Confinement: Ventilation System .................................................. 28 4.5 Radiation M onitoring Systems and Effluents ....................................................................... 29 4.6 Exp eriments .............................................................................................................................. 29 5.0 D esign Features ...................................................................................................................................... 31 5.1 Reactor Fuel ............................................................................................................................. 31 5.2 Reactor Core ............................................................................................................................ 32 5.3 Control Rods ............................................................................................................................ 32 5.4 Radiation M onitoring System .............................................................................................. 33
NSC Technical Specifications, Version 09/01/1999 3.0 Limiting Conditions for Operation 3.1 Reactor Core Parameters 3.1.1 Steady State Operation Applicability This specification applies to the energy generated in the reactor during steady state operation.
Objective The objective is to assure that the fuel temperature safety limit will not be exceeded during steady state operation.
Sipecifications The reactor power level shall not exceed 1.3 megawatts under any condition of operation.
The normal steady state operating power level of the reactor shall be 1.0 megawatts.
However, for purposes of testing and calibration, the reactor may be operated at higher power levels not to exceed 1.3 megawatts during the testing period.
Basis Thermal and hydraulic calculations indicate the TRIGA fuel may be safely operated up to power levels of at least 2.0 MW with natural convection cooling.
3.1.2 Pulse Mode Operation Applicability This specification applies to the peak temperature generated in the fuel as the result of a pulse insertion of reactivity.
Objective The objective is to assure that respective pulsing will not induce damage tot he reactor fuel.
Specification a) The reactivity to be inserted for pulse operation shall not exceed that amount which will produce a peak fuel temperature of 1526*F (830°C). In the pulse mode the pulse rod shall be limited by mechanical means or the rod extension physically shortened so that the reactivity insertion will not inadvertently exceed the maximum value.
b) Until the LEU fuel core has been calibrated, maximum pulse shall be limited to
$2.00.
Basis TRIGA fuel is fabricated with a nominal hydrogen to zirconium ratio of 1.6 for LEU fuel.
This yields delta phase zirconium hydride which has a high creep 9
1.37 Shall, Should and May................................................................................. 5 1.38 Shutdown Margin ...................................................................................... 6 1.39 Steady State Mode...................................................................................... 6 1.40 True Value .............................................................................................. 6 1.41 Unscheduled Shutdown................................................................................ 6 2.0 Safety Limit and Liniting Safety System Setting.............................................................. 7 2.1 Safety Lin-it Fuel Element Temperature.............................................................. 7 2.2 Limiting Safety System Setting ....................................................................... 7 3.0 Limiting Conditions for Operation.............................................................................. 9 3.1 Reactor Core Parameters .............................................................................. 9 3.1.1 Steady State Operation ...................................................................... 9 3.1.2 Pulse Mode Operation....................................................................... 9 3.1.3 Shutdown Margin........................................................................... 10 3.1.4 Core Configuration Limitation ............................................................ 11
--- 3.1.5 Maximum Excess Reactivity..-7...... .................... 7.......
3.2 Reactor Control and Safety Systems ................................................................ 12 3.2.1 Reactor Control Systems................................................................... 12 3.2.2 Reactor Safety Systems .................................................................... 12 3.2.3 Scram Time ................................................................................. 14 3.3 Confinement........................................................................................... 14 3.3.1 Operations that Require Confinement .................................................... 14 3.3.2 Equipment to Achieve Confinement...................................................... 15 3.4 Ventilation System.................................................................................... 15 3.5 Radiation Monitoring Systems and Effluents....................................................... 16 3.5.1 Radiation Monitoring ...................................................................... 16 3.5.2 Argon-41 Discharge Limit................................................................. 17 3.5.3 Xenon and Iodine Monitoring.............................................................. 17 3.6 Limitations on Experiments .......................................................................... 18 3.6.1 ReactivityLimits............................................................................ 18 3.6.2 Material Limitations........................................................................ 18 3.6.3 Failures and Malfunctions.................................................................. 20 3.6.4 Xenon Irradiation for Iodine Production ................................................. 21 3.7 As Low As Reasonably Achievable (ALARA) Radioactive Effluents Released ................ 21 3.8 Primary Coolant Conditions ......................................................................... 22 4.0 Surveillance Requirements..................................................................................... 24 4.1 General ................................................................................................. 24 4.2 Reactor Core Parameters............................................................................. 24 4.2.1 Steady State Operation ..................................................................... 24 4.2.2 Pulse Mode Operation...................................................................... 25 4.2.3 Shutdown Margin........................................................................... 25 4.2.4 Reactor Fuel Elements ..................................................................... 25 4.3 Reactor Control And Safety Systems ............................................................... 27 4.3.1 Reactor Control Systems................................................................... 27 4.3.2 Reactor Safety Systems .................................................................... 27 4.3.3 Scram Time ................................................................................. 28 4.4 Equipment to Achieve Confinement: Ventilation System ........................................ 28 4.5 Radiation Monitoring Systems and Effluents....................................................... 29 4.6 Experiments ........................................................................................... 29 5.0 Design Features ................................................................................................. 31 5.1 Reactor Fuel........................................................................................... 31 5.2 Reactor Core .......................................................................................... 32 5.3 Control Rods .......................................................................................... 32 5.4 Radiation Monitoring System........................................................................ 33
NSC Technical Specifications, Version 09/01/1999 3.0 Limiting Conditions for Operation 3.1 Reactor Core Parameters 3.1.1 Steady State Operation Applicability This specification applies to the energy generated in the reactor during steady state operation.
Obiective The objective is to assure that the fuel temperature safety limit will not be exceeded during steady state operation.
Specifications The reactor power level shall not exceed 1.3 megawatts under any condition of operation.
The normal steady state operating power level of the reactor shall be 1.0 megawatts.
However, for purposes of testing and calibration, the reactor may be operated at higher power levels not to exceed 1.3 megawatts during the testing period.
Basis Thermal and hydraulic calculations indicate the TRIGA fuel may be safely operated up to power levels of at least 2.0 MW with natural convection cooling.
3.1.2 Pulse Mode Operation Applicability This specification applies to the peak temperature generated in the fuel as the result of a pulse insertion of reactivity.
Obiective The objective is to assure that respective pulsing will not induce damage tot he reactor fuel.
Specification a) The reactivity to be inserted for pulse operation shall not exceed that amount which will produce a peak fuel temperature of 1526TF (8301C). In the pulse mode the pulse rod shall be limited by mechanical means or the rod extension physically shortened so that the reactivity insertion will not inadvertently exceed the maximum value.
b) Until the LEU fuel core has been calibrated, maximum pulse shall be limited to
$2.00.
Basis TRIGA fuel is fabricated with a nominal hydrogen to zirconium ratio of 1.6 for LEU fuel.
This yields delta phase zirconium hydride which has a high creep 9