ML20066J323
| ML20066J323 | |
| Person / Time | |
|---|---|
| Site: | University of Texas at Austin |
| Issue date: | 12/31/1990 |
| From: | TEXAS, UNIV. OF, AUSTIN, TX |
| To: | |
| Shared Package | |
| ML20066J316 | List: |
| References | |
| NUDOCS 9102260064 | |
| Download: ML20066J323 (63) | |
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l Technical Specifications Revision 1 Docket 50 602 The University of' Texas at Austin TRICn Reactor December 1990 9102260064 910212 PDR ADOCK0500g',g2 A
Rovisien 1 Technicci Spscifications Table of Contents 1.0 DEFINITIONS 5 1.1 Certified operators 5 1.1.1 Senior Reactor Operator 5 1.1.3 Reactor Operator 5 1.2 Channel 5 ,
1.2.1 Channel Test 5 1.2.2 Channel Check 5 1.2.3 Channel Calibration 5 1.3 Confinement 5 1.4 Experiment 6 1.4.1 Experiment, Moveable 6 1.4.2 Expariment, Secured 6 1.4.3 Experimental Facilities 6 1.5 Fuel Element, Standard 6 1.6 Fuel Element, Instrument 6 1.7 Mode; Manual, Auto, square Vave. Pulse 6 1.8 Steady State 6 1.9 operable 7 ~
1.10 Operating 7 1.11 Protective Action 7 1.11.1 Instrument Channel Level 7 1.11.2 Instrument System Level 7 1.11.3 Reactor Safety System Level 7 1.12 Reactivity, Excess 7 1.13 Reactivity Limit 7 1.14 Reactor Core, Standard 8 1.15 Reactor Core, Operational 8 1.16 Reactor Operating 8 1.17 Reactor Safety System 8 1.18 Reactor Secured 8 1.19 Reactor Shutdown 9 1.20 Reference Core Condition 9 1.21 Research Reactor 9 1.22 Rod, Control 9 1.22.1 Shim Rod 9 1.22.2 Regulating Rod 9 1.22.3 Standard Rod 9 1.22.4 Transient Rod 9 1.23 Safety Limit 10 1.24 Scram Time 10 1.25 Shall, Should and May 10 1.26 Shutdown Margin 10 1.27 Shutdown, Unscheduled 10.
1.28 Value,-Heasured 10 1.29 Value True 10 1.30 Surveillance Activities
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11 1 31 Surveillance Intervals 11 12/90 Page 2
R3visicn 1 Technicci $pacifications 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 12 2.1 SAFETY LIMIT 12 2.2 LIMITING SAFETY SYSTEM SETTINGS 12 2.2.1 Fuel Temperature 12 2.2.2 Power Level (Non Pulse) 12 2.2.3 Reactivity Insertion (Pulse) 12 3.0 LIMITING CONDITIONC FOR OPERATION 13 3.1 REACTOR CORE PARAMETERS 13 3.1.1 Excess Reactivity 13 3.1.2 Shutdown Margin 13 3.1.3 Transient Insertions 13 3.1.4 Fuel Elements 13 3.2 REACTOR CONTROL AND SAFETY SYSTEM 14 3.2.1 Control Assemblies 14 3.2.2 Reactor Control System 14 3.2.3 Reactor Safety System 15 3.2.4 Reactor Instrument System 15 3.3 OPERATIONAL SUPPORT SYSTEMS 16 3.3.1 Water Coolant Systems 16 3.3.2 Air Confinement Systems 16 3.3.3 Radiation Monitoring Systems 17 3.4 LIMITATIONS ON EXPERIMENTS 18 3.4.1 Reactivity 18 3.4.2 Materials 18 4.0 SURVEILLANCE REQUIREMENTS 20 4.1 REACTOR CORE PARAMETERS 20 4.1.1 Excess Reactivity 20 4.1.2 Shutdown Margin 20-4.1.3 Transient Insertion 20 4.1.4 Fuel Elements 20
- 4. ' RinCTOR CONTROL AND SAFETY SYSTEM 20 4.2.1 Control Assemblies 20 4.2d Reactor Control System 21 4.'. 3 Reactor Safety System 21 4.2.4 Reactor Instrument System 21 4.3 OPERATIONAL SUPPORT SYSTEMS 22 4.3.1 Water Coolant Systems 22 4.3.2 Air Confinement Systems 22 4.3.3 Radiation Monitoring Systems 23 4.4 LIMITATIONS ON EXPERIMENTS 23 4.4.1 Reactivity 23 4.4.2 Materials 23 12/90 Page 3
Rovisicn.1 Technical Spscifications 5.0 DESIGN FEATURES 24 5.1 SITE AND FACILITY DESCRIPTION 24 5.1.1 Location 24 5.1.2 Confinement 24 5.1.3 Safety Related Systems 24 5.2 REACTOR COOLANT SYSTEM 25 5.2.1 Natural convection 25 5.2.2 Siphon Protection 25
' 5.3 REACTOR CORE AND FUEL 25 5.3.1 Fuel Elements 25 5.3.2 Control Rods 25 5.3.3 Configuration 25 5.4 REACTOR FUEL ELEMENT STORACE 26 5.5 REACTOR POOL CAMMA IRRADIATOR 26 6.0 ADMINISTRATIVE 27 6.1 ORGANIZATION 27 6.1.1 Structure 27 6.1.2 Responsibility 28 6.1.3 Staffing 28.
6.1.4-Selection and Training of Personnel 29.
6.2 REVIEW. AND AUDIT 29 6.2.1 Composition and Qualifications 29-6.2.2 Charter and Rules 29' 6.2.3 Review Function 29 6.2.4 Audit Function 30
-6.3 OPERATING PROCEDURES 30 i 6.4 EXPERIMENT -REVIEW AND APPROVAL ' 31 6.5 REQUIRED ACTIONS 32 6.5.1 Case of Safety Limit violation '32 6.5.2 Event of a Reportable Occurrence 32
6.6 REPORTS
33
_ ,6.6.1 Operating Reports-- 33 6'.6.2 Special Reports 33
-6.7 RECORDS 36 6.7.1-Lifetime of the Facility 36 6.7.2 Five Years-or the Life.of the Component 36 6.7.3 One Licensing Cycle 36 APPENDIX A.1 Introduction 37 A.2 Objectives & Bases for Satity Limitsi 38 A.3 Objectives 6. Bases for Limiting Conditions for Operations 41 A 4 Objectives 6. Bases for Surveillance Requirements 51 A.5 Objectives.& Bases for Design Features 12/90 Page 4 4
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Revision 1 Technical Specifications 1.0 DEFINITIONS 1.1 Certified operators An individual authorized by the U.S. Nuclear Regulatory Commission to carry out the responsibilities associated with the position requiring the certification.
1.1.1 Senior Reactor Operator An individual who is licensed to direct the activities of reactor operators. Such an individual may be referred to as a class A operator.
1.1.2 Reactor Operator An individual who is licensed to manipulate the controls of a reactor.
Such an individual may be referred to as a class B operator.
1.2 Instrumentation Channel A channel is the combination of sensor, line, amplifier, and output device which are connected for the purpose of measuring the value of a parameter, 1.2.1 Channel Test Channel test is the introduction of a signal into the channel for verification that it is operable.
1.2.2 Channel check Channel check is a qualitative verification of acceptable performance by observation of channel behavior. This verification, where possible, shall include comparison of the channel with other independent channels or systems measuring the same variable.
1.2.3 Channel Calibration Channel calibration is an adjus tment of ti .nnel such that its output corresponos with acceptable accurac, - known values of the parameter which the channel measures. Calibra' on shall encompass the entire channel, including equipment actuation, alarm, or trip and shall be deemed to include a channel test.
1.3 Confinement Confinement means an enclosure on the overall facility which controls the movement of air into it and out through a controlled path.
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Revision 1 Technical Specifications 1.4 Experiment Any operation, component, or target (excluding devices such as detectors, foils, etc.), which is designed to investigate non routine reactor characteristics or which is intended for irradiation within the pool, on or in a beam tube or irradiation facility and which is not rigidly secured to a core or shield structure so as to be part of their design.
1.4.1 Experiment, Moveable A moveable experiment is one where it is intended that all or part of the experiment may be moved in or near the core or into and out of the reactor while the reactor is operatin6 1.4.2 Experiment, Secured A secured experiment is any experiment, experiment facility, or component of an experiment that is held in a stationary position relative to ens reactor by mechanical means. The restraining- force must be substantially greater than those to which the experiment might be subjected by hydraulic, pneumatic, buoyant, or other forces which are normal to the operating environment of the experiment, or by forces which can arise an a result of credible conditions.
1,4.3 Experimental Facilities Experimental facilities shall mean rotary specimen rack, pneumatic transfer tube, central thimble, beam tubes and irradiation facilities in the core or in the pool.
1.5 Fuel Element, Standard A fuel element is a single TRIGA element of standard type. Fuel is U ZrH clad in stainless steel clad. ilydrogen to zirconium _ ratio is nominal 1.6.
1.6 Fuel Element, Instrumented An instrumented fuel element is a special fuel element fabricated for temperature . measurement. The element shall have at least one thermocouple embedded in the fuel near the axial and radial midpoints.
1.7 Mode; Manual, Auto, pulse, Square Wave .
Each mode of operation shall mean operation of the reactor with the mode selection switches in the manual, auto, pulse or square wave position.
1.8 Steady state Sceady state mode operation shall mean any operation of the reactor with the mode selection switches in the manual, auto or square wave position.
The pulse mode switch will define pulse operation.
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R2Violen 1 Technical Spscifications .
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1.9 Operable [
t Operable means a component or system is capable of performing its !
intended function.'
i 1.10 Operating ,
Operating means a component or system is performing its intended function.-
i 1.11 Protective Action j Protective action is the initiation of a signal or the operation of i equipment- within the reactor safety system in response to a variable or t condition of_the reactor facility having reachod a specified limit.
1.11.1 Instrument Channel Level At the protective instrument channel level, protective action is -the generation and transmission of a trip signal indicating that a reactor- 7 variable has reached the specified limit. j P
1.11'.2 Instrument
- System Level At the protective instrument system level. protective action is the-
_ generation and transmission of the command signal for the safety ;
shutdown equipment to operate.
1.11.3 Reactor Safety System Level At the reactor safety system level, protective action is the operation of sufficient equipment to immediately shut down the reactor.- .;
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.1.12 Reactivity,-Excess' j Excess reactivity in that amount of. reactivity that would exist if all the control rods were moved to the maximum reactive condicion from the point where the reactor is exactly critical..
1 13 Reactivity Limits '
The reactivity limits'are those limits imposed on the reactor core excess reactivity. Quantities are referenced to a' reference core condition, s
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R9visien 1 Technical Spacifications 1.14 Reactor Core, Standard A standard core is an arrangement of standard TRIGA fuel in the reactor grid plate and may include installed experiments.
1.15 Reactor Core, Operational An operational core is a standard core for which the core parameters of excess reactivity, shutdown margin, fuel temperature, power calibration, and reactivity worths of control rods and experiments have been determined to satisfy the requirements set forth in the Technical Specifications.
1.16 Reactor Operating The reactor is operating whenever it is not secure /. or shutdown.
1.17 Reactor Safety Systems Reactor safety systems are those systems, including their associated input channels, which are designed to initiate automatic reactor protection or to provide information for initiation of manual protective action, 1.18 Reactor Secure The reactor is secure when:
1.18.1.Suberitical :
There is insufficient fissile _ material or modereivt present in the reactor, control rods or adjacent experiments, to attain criticality under optimum available conditions of moderation and reflection, or 1.18.2 The following conditions exist :
- a. The minimum ntunber of neutron absorbing control rods are fully inserted in shutdown position,- as required by technical specifications.
- b. The console key switch is in the off position and the key is removed from the lock,
- c. No work is in progress involving core fuel, core structure, installed control rods, or control rod drives unless they are physically decoupled from the control rods, i
- d. No experiments are being moved or serviced that have, on movement, a reactivity worth equal to or exceeding one dollar.
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Rsvision 1 Technical Specifications 1.19 Reactor Shutdown The reactor is shutdown if it is suberitical by at least one dollar in the reference core condition with the reactivity of all installed experiments included.
1.20 Reference Core Condition The condition of the core when it is at ambient temperature (cold) and the reactivity worth of xenon is negligible (<.30 dollars).
1.21 Research Reactor A research reactor is defined as a levice designed to support a self.
sustaining neutron chain reaction for research, development, educational, training, or experimental purposes, and which may have provisions for the production of radioisotopes.
1.22 Rod, Control A control rod is a device fabricated from neutron absorbing material or fuel which is used to establish neutron flux changes and to compensate for routine reactivity loses. A control rod may be coupled to its drive unit allowing it to perform a safety function when the coupling is dir3ngaged.
1.22.1 Shim Rod A shim rod is a control rod having an electric motor drive and scram capabilities.
1.22.2 Regulating Rod A regulating rod is a conteol rod used to maintain an intended- power level and may be varied manually or by a servo controller. The regulating rod shall have scram capability.
1.22.3 Standard Rod Tho regulating and shim rods are standard control rods.
1.22.4 Transient Rod A transient rod is a control rod used-to initiate a power pulse that is operated by a motor drive and/or air pressure. The transient rod shall have scram capability.
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Revisicn 1 Technical Specifications j 1.23 Safety 1.imits Safety limits ere limits on important process variables which are found to be necessary to protect reasonably the integrity of the principal barriers which guard against the uncontrolled release of radioactivity.
The principal barrier is the fuel element cladding.
1.24 Scram Time l Scram time is the elapsed time between reaching a limiting safety system set point and a specified control rod movement.
1.25 Shall, should and May i
T}e word shall is used to denote a requirement. The word should is used I to denote a recommendation, The word may is used to denote permission. l neither a requirement nor a recommendation, l 1.26 Shutdown Margin Shutdown margin shall mean the minimum shutdown reactivity necessary to provide confidence that the reactor can be made suberitical by means of the control and cafety systems starting from any permissible operating condition and with the most reactive rod in its most reactive position, and that the reactor will remain suberitical without further operator action.
1.27 Shutdown, Unscheduled An unscheduled shutdown is defined as any unplanned shutdown of the reactor caused by actuation of the reactor safety system, operator error, equipment malfunction, or a manual shutdown in respnse to conditions which could adversely affect safe operation, not including shutdowns which occur during testing or check out operations.
1.28 Value, Heasured The measured value is the value of a parameter as it appears on the output of a channel.
1.29 Value. True The true value is the actual value of a parameter.
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Revision 1 Technical Specifications 1.30 Surveillance Activities Surveillance activities (except those specifically required for safety when the reactor is shutdown), may be deferred during reactor shutdown.
however, they must be cortpleted prior to reactor startup unless reactor operation is necessary for performance of the activity. Surveillance activities scheduled to occur during an operating cycle which cannot be performed with the reactor operating may be deferred to the end of the cycle.
1.31 Surveillance intervals Maximum intervals are to provide operational flexibility and not to reduce frequency. Established frequencies shall be innintained over the long term. Allowable surveillance intervals shall not exceed the following:
1.31.1 .
5 years (interval not to exceed 6 years).
1.31.2 2 years (interval not to exceed 2 1/2 years).
1.31.3 Annual (interval not to exceed 15 months),
1.31.4 Semiannual (interval not to exceed 7 1/2 months).
1.31.5 Quarterly (interval not to exceed 4 months).
1.31.6 Monthly (interval not to exceed 6 weeks).
1.31.7 Weekly (interval not to exceed 10 days).
1.31.8 Daily (must be done during the calendar day).
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Revision 1 Tochnicel Specifications 2.0 SAFETY 1.IMITS AND 1.IMITING SAFETY SYSTEM $ETTINGS 2.1 Safety Limit Specification (s)
The maximum temperature in a standard TRICA fuel element shall not exceed 1150'C for fuel element clad temperatures less than 500'C and shall not exceed 950'C for fuel element clad temperatures greater than 500'C, Temperatures apply to any condition of operation.
2.2 Limitinc Safety System Settints 2.2.1 Fuel Temperature Specification (s)
The limiting safety system setting shall be 550'C as measured in an ,
instrumented fuel element. One instrumented element shall be located in the B or C ring of the reactor core configuration.
2.2.2 Power Level (Manual, Auto, Square Wave)
Specification (s)
The maximum operating power level for the operation of the reactor shall be 1100 kilowatts in the manual, auto and square wave modes.
2.2.3 Reactivity Insertion (Pulse) ,
Specification (s)
The maximum transient reactivity insertion for the pulse operation of the reactor shall be 2.2% ak/k in the pulse mode.
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R$visien 1 *tochnical Specifications 3.0 LIMITING CONDITIONS FOR OPERATION l 3.1 Reactor Core Parameters 3.1.1 Excess Reactivity Specification (s) I Maximum excess reactivity shall be 4.91 Ak/k.
3.1.2 Shutdown Margin Specification (s)
The reactor shall not-be operated unless the shutdown margin provided by~ control rods 1s greater than 0.21 Ak/k with:
- a. The reactor in the reference core condition.
- b. The most reactive control rod fully withdrawn.
- c. All moveatle experiments in their most reactive state.
3.1.3 Transient Insertions Specification (s) !
Total worth of the transient rod shall-be limited ~to 2.81 Ak/k, and the total withdrawal time for the rod shall not exceed 15 seconds, j 3.1.4 Fuel Elements Specification (s)
The reactor-shall'not be operated.with fuel element damage except for
, .the purpose of loce,ing and removing the elements. A fuel element shall be considered damaged and must'be removed'from the core-if:
- a. In measuring the- elongation, the- length exceeds the original length by 2.54 mm (1/10 inch).
b.-In measuring _the! transverse bend, the bond exceeds the original bend by 1.5875 mm (1/16 inch). ,
- c. A clad defect exists as indicated by release of fission products- I or visual observation _
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Rovisien 1 Technical Spscificctions 1
3.2 Reactor Control and Safety System l l
3.2.1 Control Assemblies Specification (s) 1 The reactor shall not be operated unless the control rods are f operable, and
- a. Control rods shall not be operable if damage 8 s apparent to the rod or drive assemblies.
- b. The scram time measured from the instant a simulated signal reaches the value of a limiting safety system setting to the instant that the slowest scrammable control rod reaches its fully inserted position shall not exceed 1 second.
- c. Maximum reactivity insertf yr. ' rate of a standard cor. trol rod shall be less than 0.2% Ak!k pt<r second.
3.2.2 Reactor Control System Specification (s)
The reactor shall not be operable unless the minimum safety interlocks are operable. The following control system safety interlocks shall be operable: ;
Interlocks Number Effective Mode Rod Drive Control Operable Function Manual
- Pulse ;
- a. Startup Withdrawal 4 prevent rod X Standard control rods withdrawal for Transient control rod less-than 2 -
counts per see
- b. Simultaneous Withdrawal 4 trevent rod X Standard control rods withdrawal for Transient control rod two or more rods
- c. Non pulse condition 1 prevent withdrawal X Transient control rod for drive not down except square wave
- d. Pulse Withdrawal 3 prevent withdrawal X Standard control rods of non pulse rods
- e. Transient Withdrawal 1 prevent rod X Transient control rod withdrawal for more than 1 kilowatt power
- Manual mode includes Auto and Square Wave modes 12/90 Page 14 e
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Revision 1 Technical Specifications 3.2.3 Reactor Safety Systen Specification (s)
The reactor shall not be operable unless the minimum safety channels are operable. The following control rod scram safety channels shall be operable, Number Effective Mode Safety Channel._, Operable Function Manual
- Pulse
- a. Fuel Temperature 2 Scram at 55$0'C X X
- c. liigh Voltage 2 Scram on loss X X
- d. Magnet Current 1 Scram on loss X X
- e. Manual Scram 1 Scram on demand X X Console Button
- f. Watchdo8 Trip 2 Scram on loss of Microprocessor scan rate timer reset X X
- Manual modo includes Auto and Square Wave modes 3.2,4 Recctor Instrument System Specification (s)
A minimum configuration of measuring channela shall be operable. The following minimum reactor parameter measuring channels shall be operable:
Number Effective Mode Measuring Channel Operable Manual
- Pulse
- a. Fuel Temperature 2 X X
- b. Power Level 2 X
- c. Pulse Power 1 X
- d. Pulse Energy 1 X
- Manual mode includes Auto and Square Wave modes 12/90 Page 15
Revision 1 Tochnical Sp*cifications 1
3.3 Qperational Suonort Systens 3.3.1 Water Coolant Systems Specification (s) ,
Corrective action shall be *,aken or the reactor shut down if any of the following reactor coolant conditions are observed:
- a. The bulk pool water temperature exceeds 48'C.
- b. The water depth is less than 6.5 meters measured from the pool bottom to the pool water surface,
- c. The water conductivity exceeds 5.0 pmho/cm for the average value during measurement periods of one month,
- d. The pressure difference during heat exchanger operation is less than 7 kPa (1 psig) measured between the chilled water outlet pressure and the pool water inlet pressure to the heat exchanger.
- e. Pool water data from periodic measurements shall exist for water pH and radioactivity. Radionetivity measurements will include total alpha beta activity and game ray spectrum analysis.
3.3.2 Air Confinement Systems Specification (s)
Corrective action shall 'be taken or the reactor shut devn if any of the following air confinement conditicas do not exist:
- a. Equipment shall be operable to isolate the reactor area by closure of room ventilation supply and exhaust dampers, and shutdown of system supply and exhaust fans.
- b. The reactor room ventilation system shall have an automatic signal to isolate the area if air particulate radioactivity exceeds preset valuea.
- c. An auxiliary air purge system to exhaust air from experiment systems shall have a high efficiency particulate filter.
- d. Room ventilation shall require two air changes por hour or exhaust of pool areas by the auxiliary air purge system.
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Revision 1 Technical Specificationo 3.3.3 Radiation Monitoring Systems Specification (s)
Radiation monitoring while the reactor is operating requires the following minimum conditions :
- a. A continuous air monitor (particulate) shall be operable with readout and audible alarm. The monitor chall sample reactor .s room air within 5 meters of the pool at the pool access level. (
Alarm set point shall be equal to or less than a t,casurement
. concentration of 2 x 10*' poi /cm3 with a two hour particulate accumulation.
The particulate continuous air monitor shall be operating when the reactor is operating. A set point of the monitor will initiate the isolation signal for the air ventilation system.
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The particulate air monitor may be out of service for a period ;
of 1 week provided the filter is evaluated daily, and a eignal from the argon 41 continuous air monitor is available to provide information for manual shutdown of the IIVAC.
- b. A continuous air monitor (argon 41) shall be operable with readout and audible alarm. The monitor shall sample exhaust I stack air from the auxiliary air purge system when the systers is operating. Alara set point shall be equal to or less than a measurement concentration of 2 x IO'S pCi/cm3 for a daily t release.
The argon 41 continuous air monitor shall be operatin5 when the auxiliary air purge system is operating. The average annual concentration limit for release at the stack shall be 2 x 10*6 pCi/cm3. _
n If the argon 41 monitor is not operable, operating the re.se tor with the auxiliary air purge system shall be limited to a period of ten days. ,
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- c. Area radiation monitors (gamroa) shall be ope.3ble with readout and audible alarm, one of which shall be located in the vicinity of the top of the reactor pool. Alarm set point shall be a measurement value equal to or less than 100 mr/hr.
One area radiatica monitor shall be operating at the pool level when the reactor is operating. Two additional area radiation monitors shall be operating at other reactor areas when the reactor is operating.
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I Rsvision 1 Tochnicc1 Spacificctions 3.4 Limitatient onJKp1I.imenLE 3.4.1 Reactivity Specification (s) l The reactor shall not be operater unles the following conditions Governing experiment reactivity exier:
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- a. A moveable experiment shall hav, a reactivity wot'th less than l 1.00 dollar. I
- b. The reactivity worth of any single secured experiment shall be l 1ess than 2.50 dollars.
- c. The total of absolute reactivity worths of reactor core l experiments sna11 not exceed 3,00 dollars, including the potential reactivity which might result from malfunction, flooding, voiding, or removal and insertion of the experiments. ,
3.4.1 Materials Specification (s)
The reactor shall not be operated unless the following conditions governing experiment materials exist:
- a. Experiments containing materials corrosive to reactor components, compounds highly reactive with water, potentially t explosive materials, and liquid fissionable . materials shall be doubly encapsulated. Cuidaneo for classification of anterials shall use the Handbook of Laboratory Safety Tables of Chemical Information published by CRC press,
- b. If a capsule fails and releases materini which could damage the reactor fuel or structure by corrosion or other. means, removal and physical inspection shall be performed to determine the consequences and need for-correceive action. The results of the inspection and any corrective action taken shall be reviewed by the Director, or his designated alternate, and determined to be satisfactory before operation of the reactor is resumed.
- c. Explosive materials in quantitles greater than 25 milligrams shall not be irradiated .in the reactor or experimental facilities. . Explosive materials .in quantities less than 25 milligrams may be irradiated provided the pressure produced upon
' detonation of the explosive has been calculated and/or experimentally demonstrated to be less than the design pressure of the container,
- d. Each fueled experiment shall be controlled such that the total Invencory of iodine isotopes 131 through 135 in the experiment is no greater than 750 millieuries and the maximum strontium inventory is no greater than 2.5 mil 11 curies.
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Revision 1 Tec'Anical Spscifications )
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- e. Experiaant m.ite rials , except fuel materials, which could off-gas, sublime, volatilfre, or produce aerosol s under (1) normal operating conditions of the experiment or ra retor. G) crediblo accident conditions in the reactor, (3) possible accident i conditions in the experiment shall M limited in activity such 1 that if 100% of the gaseous activity or radioactive aerosols produced escaped to the reactor room or the ottnosphere, the .
airborne concentration of radicactivity averaged over a year would not exceed the occupational limits for maximum permissible i concentration,
- f. In calculations pursuant to e. above, the following assumptions shall be used: (1) If the effluent from an experimental facility exhausts through a holdup tank which closes automatically n high radiation level, at least 10% of the i gaseous activity or aerosols produend will escape. (2) If the effluent from an experimental facility exhausts through a filter installation designed for greater than 991 efficiency . for 0.25 micron particles, at least 10% of these *:apora can escape. (3)
For materials whose boiling point is above 55'c and where vapors -
formed by boiling this rnaterial can escape only through an undisturbed column of water above the core, at least 10% of these vapors can escape. (4) Limits for maximum permissible concentrations are specified in the appropriate section of 10CFR20.
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l Revis tor.1 Technical Spec 1C1 cations 4.0 SURVEILLANCE REQUIREMENTS 4.1 Reatter core Parameters 4.1.1 Excess Reactivity Specification (s)
Excess reactivity shall be decernined annually or after significant control rod or reactor core changes.
4.1.2 Shutdown Marsin Specification (a)
Shutdown margin shall be determined annually or after significant control rcd or reactor care 2hanges.
4.1.3 Transient Insertion Specification (s)
Transient rod function shall be evaluated annually or after significant control rod or reactor core changes. The transient rod drive and associated air supply shall be inspected annually, and the drive cylinder shall he cleaned and lubricated annually.
A comparison of pulse data shall be made with previous measurements at annual intervals or each time the interval to the previous measurement exceeda the annual interval.
4.1.4 Fuel Elements a
Specification (s)
The reactor fuel elemen*s saall be examined for physical damage by a visual inspection, including e check of t.e dimensional measurements, made at biennial intervals.
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Ravicionl1 Tschnical'Spscifications i l
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4l?( Reactor Control and Safety System 4.2.1 Control Assemblies Specification (s) 3-Control rod worths shall be determined annually or- after significant control' rod or reactor core changes, and ,
- 3. a. - Esch control rod shall be inspected at biennial intervals ' by
= visual observation,
- b. The scer.m time of a scrammable control rod shall' be measured ' .'
annually or after maintenance to the control rod or drive; I
- c. The reactivity insertion rate of a standard control rod shall be
. measured ' annually; or af ter maintenance to the control rod or
. drive.-
4.2.2' Reactor Control System Specification (s) 1 The' minimum' safety interlocks shall be tested at semiannual intervals or af ter repair: or modification.
-4.2.3' Reactor Safety 9ystem
. Specification (s)
The . minimum safety. channels' .shall be calibrated annually = or - af ter repair.or modifications. A channel test shall be,done prior to.each
. days H operation, - af ter repair ' or modifications, or prior to each extended period'of operation.
[d 4;2.4 Reactor Instrument System V
s Specificction(s)
'. -J_
The . minimum configuration of -instrument channels shall be calibrated annually or = af ter repair or modification. Calibration of the ? powerL measuring channels shall' be by the ~ calorimetric ' method. - . A channel' check and channel test of the fuel temperature; instrument channe.ls and-power level instrument channels shall be made prior to each daysj g operation.or prior to each extended period of ooeration.
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- w. ,- - , , ~ , , , ,.....n, - . - , , - - , r- , ,,, , - , ,
4.3 Operatio~al Support Systems '
4.3.1 Water Coolant Systems
, specification (s)
.The following measurements shall monitor the reactor cociant conditions:-
- a. Tne ' pool- temperature channel ; shall '. have a channel calibration annually, channel check monthly _ and will - be monitored during reactor _ operation,
- b. The pool- water depth channel- shall- have a channel - calibration ' -l annually. channel check monthly and ' will be monitored ' during reactor operation; c.-The water conductivity channel shall have a channel calibration iannually and-pool water _ conductivity will be measured weekly. _
- d. The presst re difference channel shall have a channel test prior to-each days operation after repair or. modifications,-or-prior to each extended period of operation of rhe' heat exchanger and will be= monitored during operation,
- e. Measure-- pool water pH with low lon test papet or ' equivalent -
quarterly. Sample pool water radioactivity-quarterly for total alpha beta activity. Analyze -pool water sample by:Jgamma spectroscopy annually for isotope identification.
4.3.2 Air Confinement Systems Specification (s).
.The -following actions shall- demonstrate- the .- air. confinement conditions:-
--a'. Annual examination of door seals and-isolation dampers, b'. Monthly functional tests of air confinement isolation.
- c. Monthly check of-the auxiliary air purge system valve. alignments-for experimental areas,
- d. Daily _ check of ventilation system alignment for proper exhaust
-conditions prior to reactor operation.
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Tschnical Spscifications RSviolon 1 4 3.3 Radiation Monitoring Systems Specification (s)
The following conditions shall apply to radiation monitoring systems:
- a. Calibrate - particulate air monitor at semiannual intervals and check operability weekly,
- b. Calibrate argon 41 air monitor at biennial intervals and check operability monthly,
- c. Calibrate area radiation =onitors at semiannual inte rvals and check operability weekly prior to reactor operation.
4.4 Ljmitations on Experiments 4.4.1 Reactivity Specification (s)
The reactivity of an experiment shall be measured before an experiment is considered functional.
4.4.2 Materials Specification (s)
Any surveillance conditions or special requirements shall be specified as a part of the experiment approval.
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Y
'Technicci Spscificctions -- :I Revisicn'l-l- ,
- 5.0 DESIGN FEATURES 5.1 Site and Facility Descriotion i
5.1.1 Location Specification (s)
- a. The site location is in the northeast corner of The University of Texas at Austin Balcones Research Center.
- b. The TRICA reactor -is installed in. a designated room of a building constructed as a Nuclear Engineering Teaching La% ratory.
- c. The' reactor core is assembled in an above ground shield and pool structure with horizontal and vertical access to the core, -i
- d. License areas of the facility ~ for reactor operation shall ;;
consist of the room enclosing the reactor shield and - pool structure, = and the adj acent~ area for reactor control. (room 1.104, corridor 3.200; and rooms 3.202, 3,204, and 3.208) 5.1.2 Confinement Specification (s)
- a. The reactor room snall be designed to restrict leakage and will _
have a minimum enclosed air volume of 4120 cubic meters. 1
- b. Ventilation system should provide two air changes per hour and q shall isolate air in the reactor area upon detection of a limit signal related-to the radiation level,
- c. An air purge system Lshould exhaust experiment air cavities and q 1
shall be filtered by _ high efficiency particulate. absorption filters.
1
- d. All exhaust. air from the reactor area enclosure shall be ejected vertically upward at a.. point above the facility roof level.
5.1.3 Safety Related Systems' ;
1 Specifications )
Any modifications - to the air confinement or ventilation system, the ,
reactor shield,-the pool =or its penetrations, the pool coolant system, the core and its associated support structure, the rod drive mechanisms or the' reactor safety system shall be made and-tested in accordance' with the specifications tt which the systems were originally designedt and fabricated, t.1 ternate specifications may be approved- by the Nuclear Reactor Committee. A system _ shall not be-considered operable until after it is tested successfully.
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Revision 1 Technicc1 Spscifications 5.2 Reactor Coolant System 5,2.1 Natural Convection Specification (s)
The reactor core shall be cooled by natural convection flow of water.
5.2.2 Siphon Protection Specification (s)
Pool water level shall L protected by holes for siphon breaks in pool water system pipe ling.s.
5.3 Reactor Core and Fuel 5.3.1 Fuel Elements Specification (s)
The standard TRIGA fuel element at fabrication shall have the following characteristics:
Uranium 235,
- c. Cladding: 304 stainless steel, nominal .020 inches thick.
5,3.2 Control Rods
' Specification (s)
The shim, regulating, and transient control rods shall -have- ecram capability, and
- a. Include stainless steel or aluminum clad and may be followed by air or aluminum, or for a standard. rod may be followed by fuel with stainless steel clad,
- b. Contain borated graphite, B C4 powder, or boron and its compounds in solid form as a poison,
- c. The transient rod shall have a mechanical limit. An adjustable limit will allow a variation of reactivity insertions,
- d. Two shim rods, one regulating rod and the transient rod are the minimum control rods.
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" . Technical.Spscifications Rsvisionil 25 5 3.3 Configuration Specification (s)
The reactor. shall be an arrangement of core single grid positions i occupied by fuel elements, control rods,- and- graphite elements.
. Single eltment positions may.be occupied by-voids, water or experiment facilities, Special multielement positions or single element j
positions may be occupied by-approved experiments, 5.4 Reactor Fuel Element Storage
~
Specification (s) a'.- All . fuel elements shall: be stored . in a geometrical array where the effective multiplication is less than 0.8 for all conditions .
1 of moderation.
b, 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. l 5.5 Reactor Pool Irradiator Specification (s)~ ._
The.Irradiator assembly will be an experiment facility.
- a. A 10,000 Curie -gamma irradiator may be located in the reactor pool. .The irradiator isotope will be cobalt.60, b.J Location n of the - assembly will be; at a ldepth of at least 4.5 '
Laeters and at a distance of at -least 0.5 meters from the reactor
~
, core structure.-
- c. Poo1~ water sample . requirements will monitor pool foy so'urce leakage. At a pool water activity of- 2,5x10'gater pCi/cm t the gamma irradiator components _xwill be tested to' locate and remove-any leaking source. ,
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Revision 1 Tschnicc1 Spscifications 6.0 ADMINISTRATIVE CORTROLS 6.1 orcanization 6.1.1 Structure The facility shall be under the control of the Director or a supervisory Senior Reactor Operator. The management for operation of the facility shall consist of the organizational structure established as follows:
President of The University of Texas at Austin Executive Vice President and Provost
................. 1evel 1 Radiation Dean College of Nuclear Safet" Engineering Reactor Committee Committee Radiation Safety Officer I
Chairman Department of Hechanical Engineering i
Director Nuclear Engineering Teaching Laborat ory
................. 1evel 2 Reactor Supervisor
' Health Physicist '''''''''''' l'V81 3 Reactor Operators, Technicians, Others
................. 1evel 4 Responsibility ---
Communication ---
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Revision 1' Technical Specifications 6.1.2 Responsibility The Director- shall be responsible to the Dean of the college of Engineerin6 and the chairman of the Department of Mechanical Engineering for safe operation and maintenance of the reactor and its associated equipment. The Director or a supervisory Senior Reactor Operator shall review and approve all experiments and experimental procedures prior to their use in the reactor. Individuals of the management organization shall be responsible for the policies and operation of the facility, and shall be responsible for safeguarding the public and facility personnel from undue radiation exposures and for adhering to the operating license and technical specifications.
6.1.3 Staffing The minimum staffing when the reactor is not shutdown shall be:
- a. A reactor operator in the control room,
- b. A' second person in the facility area that can perform prescribed written instructions. 11nexpected absence for two hours shall require immediate action to obtain an alternate
- person.
- c. A senior reactor operator readily available. The available operator should be within thirty minutes of the facility and reachable by telephone.
Events requiring the direction of a senior reactor operator shall be:
- a. All fuel element or control rod relocations within the reactor core region.
) b. Relocation of any experiment with a reactivity worth of greater than one dollar.
- c. Recovery from an unscheduled shutdown or significant power.
reduction,
- d. Initial startup and approach to power.
A list of reactor facility personnel by name and telephone number shall be available to the operator in the control room. The list shall include:
- c. Management personnel,
- b. Radiation safety personnel,
- c. Other operations personnel.
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Revision 1 Technical Specifications 6.1.4 Selection and Training of Personnel The selection, training and requalification of operators shall meet or exceed the requirements of American National Standard for Selection ant. Training of Personnel for Research Reactors ANSI /ANS -
15.4. Qualification and requalification of licensed operators shall be subj ec t to an approved NRC (Nuclear Regulatory Commission) program.
6.2 Review and Audit 6.2.1 Composition and Qualifications A Nuclear Reactor Committee shall consist of at least three (3) merbers appointed by the Dean of the College of Engineering that are knowledgeable in fields which relate to nuclear safety. The university radiological safety officer shall be a member or an ex-officio member. The committee will perform the functions of review and audit or designate a knowledgeable person for audit functions.
6.2.2 Charter and Rules The operations of the Nuclear Reactor Committee shall be in accordance with an established charter, including provisions for:
- a. Meeting frequency (at least once each six months).
- b. Quorums (not less than one half the membership where the operating staff does not represent a majority),
- c. Dissemination, review, and approval of minutes,
- d. Use of subgroups.
6.2.3 Review Function The review function shall include facility operations related to reactor and radiological safety. The following items shall be reviewed:
- a. Determinations that proposed changes in equipment, systems, tests, experiments, or procedures do not involve an unreviewed safety question.
- b. All new procedures and major revisions thereto, and proposed changes in reactor facility equipment or systems having safety significance.
- c. All new experiments or classes of experiments that could affect reactivity or result in the release of radioactivity.
- d. Changes in technical specifications or license.
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Revision 1 Technical Specifications
- e. Violations of technical specifications or license,
- f. Operating abnormalities or violations of procedures having safety significance,
- g. Other reportable occurrences,
- h. Audit reports.
6.2.4 Audit Function The audit function shall be a selected exarnination of operating records, logs, or other documents. An audit will be by a person not directly responsible for the records and raay include discussions with cognizant personnel or observation of operations. The following items shall be audited and a report made within 3 months to the Director and Nuclear Reactor Comrnittee:
- a. Conformance of facility operations with license and technical specifications at least once each calendar year.
- b. Results of actions to correct deficiencies that may occur in reactor facility equipment, structures, systems, or methods of operation that affect safety at least once per calendar year.
- c. Function of the retraining and requalification program for reactor operators at least once every other calendar year,
- d. The reactor facility emergency plan and physient security plan, and implementing procedures at least once every other year.
6.3 Operating Procedures Written operating proaedures shall be prepared, reviewed and approved by the Director or a supervisory Senior Reactor Operator and the Nuclear Reactor Committee prior to initiation of the following activities:
a Startup, operation, and shutdown of the reactor,
- b. Fuel loading, unloading and movement in the reactor,
- c. Routine meintenance of major components of systems that could have an effect on reactor safety,
- d. Surveillance calibrations and tests required by the technical specifications or those that could have an effect on reactor safety,
- e. Administrative controls for operation, maintenance, and the conduct of experiments or irradiations that could have an offect on reactor safety.
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T E Revision 1 Technicci--Spscifications
- f. Personnel radiation protection, consistent with applicable- I regulations .or- guidelines, and- shall include a -management commitment _and programs to maintain exposures _ and . releases as ,
low as reasonably achievable,
- g. - Implementation of required plans such as the-emergency plan or physical security plan.
Substantive changes to the- above procedures shall be made e f fective after approval by the Director or a supervisory Senior Reactor Operator -
and the Nuclear Reactor Committee. Minor modifications to the original procedures which do not change the original intent may be made by a senior reactor operator but the modifications must be approved by the Director or a supervisory Senior . Reactor Operator. Temporary deviations from the procedures may-be'made by a senior reactor operator in order._to [
deal- with.- special- or unusual circumatances- or conditions. Such deviations shall be documented and reported to the Director or a supervisory Senior Reactor Operator. _.
-6.4 Exneriment Review and Anoroval ,
All- new experiments or classes _of experiments shall. be approved by the Director -or a Supervisory Senior Reactor Operator and the Nuclear L Reactor Operations Committee, q a, - Approved experiments shall be carried out in accordance with established and approved procedures.
- b. Substantive changes to previously approved experiments shall require the same review as a new experiment. i
' c. Minor changes to an experiment that do not significantly-alter the experiment may be made by a supervisory senior reactor.
operator, i
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-Revision-1 Technical Specification's j 6.5 Reauired Actions 6.5.1- Action to be Taken in Case of a. Safety Limit Violetion.
In the - event of a safety limit violation, the following action shall ~
be taken:
- a. The reactor shall be shut down and reactor operation shall not' '
- be - resumed until a report of1 the : violation is prepared and
-authorization _ to restart by the Nuclear Regulatory Commission (NRC) is issued.
b.-The safety limit - violation shall- be promptly L reported to : the -
Director of the facility or a designated alternate..
- c. The- safety limit- violation shall be. subsequently reported to the NRC.
- d. A safety limit violation report shall be prepared and submitted
,>~
/,x - to the Nuclear Reactor Committee. The report shall = describe: =i 1
(1) Applicable circumstances leading to the violation
- including. when known the cause and contributing factors,- (2)
Effect of. the .. violation on reactor- facility components,-
systems,- or L structures' and on the health and safety c of . the
>public, (3)-Corrective actions taken to prevent. recurrence.
6.5.2 Action to be Taken in the Event of an Occurrence that: is _;
Reportable.
i In the event of a repottshia occurrence, the following action shall L be taken:
k :a. Reactor conditions shall br. returned to normal or the reactor shutdown.
If it is a esassaty to : shut- down the- reactor - to - 3 correct the' occurrence, operamrw shall not be resumed unless authorized by the-Director or his>6usignated alternate,
- b. Occurrence shall be reported to the. Director : or his . designated-
. alternate and to the Naelear Regulatory Commission -as required.
- c. Occurrence shall - be- reviewed by the' Nuclear Reactor Committee at the next regularly scheduled meeting.
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- Revisicn 1 Tschnical Spscifications 1
6.6 Reports All written reports shall be sent within the prescribed interval to the NRC, Washington D.C. 20555, Attn: Document Control Desk, with a copy to the Regional Administrator, Region IV.
6.6.1 Operatin5 Reports Routine annual reports covering the activities of the reactor facility during the previous calendar year shall be submitted within three months following the end of each prescribed year. Each annual ,
operating report shall include the following information:
- a. A narrative summary of reactor operating experience including
- the energy produced by the reactor or the hours the reactor was critical, or both,
- b. The unscheduled shutdowns including, where applicable, corrective action taken to preclude recurrence,
- c. Tabulation of major preventive and corrective maintenance operations having safety significance. .
- d. Tabulation of major changes in the reactor facility and procedures, and tabulation of new tests or experiments, or both, that are significantly different from those performed previously, including conclusions that no unreviewed safety questions were involved.
- e. A summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective control of the university as determined at or before the point of such release or discharge. The summary shall include to the extent practicable an estimate of individual radionuclides preser.t in - the - effluent. If the estimated average release after dilution or diffusien is less than 25% of the concentration allowed or recommended, a statement to this effect is sufficient.
- f. A summary of exposures received by facility personnel and visitors where such exposures are Breater than 25% of that allowed or recommended,
- g. A summarized result of environmental surveys performed outside the facility.
s.
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Revicion 1 Technical Spscifications 6,6,2 Special Reports 6.6.2.1 A written report within 30 days to the NRC of:
- a. Permanent changes in the facility organization involving Director or Supervisor,
- b. Significant changes in transient or accident analysis as described in the Safety Analysis Report, 6,6.2.2 A report to NRC Operation Center and Region IV by telephone not later than the following working day and confirmed in writing by telegraph or s'.milar conveyance to be followed by a written report within 14 days that describes the circums tances of the event of any of the followin&:
- a. Violation of fuel element temperature safety limit, b, Release of radioactivity above allowable limits,
- c. Other reportable occurrences.
Other events that will be considered reportable events are listed in this coction. (Note: Where components or systems are provided in addition to those required by the technical specifications, the failure of components or systems is not considered reportable provided that the minimum number of components or systems specified or required perform their intended reactor safety function,)
- a. Operation with actual safety-system settings for required systems less conservative than the limiting safety system settings specified in the technical specifications, b, Operation in violation of limiting conditions for operation established in technical specifications unless prompt remedial action is taken,
- c. A reactor safety system component malfunction which renders or could render the reactor safety system incapable of performing its intended safety function unless the malfunction or condition is discovered during maintenance tests or periods of reactor shutdowns,
- d. An unanticipated or uncontrolled change in reactivity greater than one dollar. Reactor trips resulting from a known cause are excluded, a
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Ravision 1 Tschnical Specifications
- e. Abnormal and significant degradation in reactor fuel, or cladding, or both, coolant boundary, or confinement boundary (excluding minor leaks) where -applicable which could result- in exceeding prescribed radiation exposure limits of personnel or environment, or both,
- f. An observed inadequacy in the implementation of administrative or procedural controls such that the inadequacy causes or could have caused the existence or development of an unsafe condition with regard to reactor operations, 6.6.2.3 A written report within 90 days after the completion of startup tests or 9 months after initial criticality, which ever is earlier, of the startup test program, to the NRC of:
Characteristics of the reactor such as critical mass, excess reactivity, power calibration, control rod calibrations, shutdown margin and experiment facility worths, describing the measured values of the operating conditions including:
- a. Total control reactivity worth and reactivity of the rod of highest reactivity worth,
- b. Minimum shutdown margin of the reactor both at ambient and operating temperatures, c . An evaluation of facility performance to date in comparison with design conditions and measured operating characteristics, and a reassessment of the safety analysis when measurements indicate that there may be substantial variance from prior analysis submitted with the license application, l
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- 'L Revisioni l; Technical Specifications ;
l 6.7 Records The -records may be in the_ form of logs, data sheets, or other suitable-forms. The required information may be contained in single or multiple records, or a combination thereof.
6.7.1 Records to be Retained for the Lifetime of the Reactor .
Facility: I
.(Note: Applicable annual reports, if they contain all of the required information, may be used as records in this section.)
- a. Gaseous and liquid radioactive effluents released to the environs,
- b. Offsite environmental monitoring surveys required by technical specifications.
- c. Events that impact or effect decommissioning of the facility
- d. Radiation exposure for all personnel monitored.
- e. Updated drawings of the reactor facility.
6.7.2 Records to be Retained for a Period of at Least Five ' Years or 3 for the Life of the Component Involved Whichever is Shorter:
- a. Normal reactor facility operation (supporting documents such as checklists,_ log sheets, etc. shall be maintained for a period '
of at least one year).
- b. Principal maintenance operations,
- c. Reportable occurrences,
- d. Surveillance activities required by technical specifications,
- e. Reactor facility radiation and contamination surveys where required by applicable regulations,
- f. Experiments performed with the reactor. "
- g. Puel inventories, receipts, and shipments.
- h. Approved changes in operating procedures.
- 1. Records of meeting and audit reports of the review and audit group.
6.7.3 Records to be Retained for at Least One Licensing Cycle:
Retraining _ and requalifications of licensed operations personnel.
Records of the most recent complete cycle shall be maintained at all times the individual is employed.
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Rsvisien l' Tschnical Specifications:
L .
p i APPENDIX o
,A.1.0 DOCKET 50 602 INFORMATION ;
l The' Technical Specifications - of this document depend on the analysis and
. conclusions _ of_ _ ; the Safety Analysis Report.
Descriptive information.
important to. each specification is presented in- the form of 'the' applicability, . objective and. bases. This information defines- the
- condit!ons effective for each technical specification, except administrative conditions, for.the Docket 50 602 facility.
A.1.1-Aeolicability-The L applicability - defines - the conditions, parameters, or - equipment to
. which the specification applies. -i
, ,h LA.1.2 Objective !
The objective defines the-_ goals _of the specification in terms of limits,
' frequency,ior other' controllable item.
J A.1.3 Bases The bases presents information important to the specification, including such- '_ things - as1; justification, logica1 constraints' and' development u imethodology. .. j
. 3.-
1
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.]ht '
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_ Rsvisien.1.' Technicci-Specifications *
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A.2.0 SAFETY LIMITS 6 LIMITING SAFETY SYSTEM SETTINGS APPLICABILITY,. 0BJECTIVES AND BASES Y
A.2.1 Safety Limit-
' Applicability-This specification applies to the temperature of the reactor fuel in. a-
' standard TRICA-fuel element, s
- Obj ective The objective.is to define the maximum temperature that can be permitted with confidence that no damage to the fuel element cladding will result.
Bases iThe important parameter. for a TRIGA reactor- is the- fuel' element '
temperature. This parameter is we11 ' suited as a single specification s since.-it can be: measured directly. -A loss =in the integrity of;the fuel-element - cladding _ could arise from a L build up of- excessive; pressure y between the ' fuel-moderator = and :- the cladding -if the fuel - = temperature : ;
exceeds the safety limit, - The pressure is caused by. the ? presence: of; air; fission product . gases, -and hydrogen from the dissociation of' the -
hydrogen and zirconium in the fuel moderator.- Hydrogen pressure is - the most :significant- component. The- magnitude of this ' pressure. is:
determined by ' the ' fuel moderator temperature and the ratio: of hydrogen - 1 to zirconium.:in'the-alloy.
The safe ty .. limit for the r standard TRIGA - fuel is ' based .on calculations t
1 and_ experimental evidence. . The results -indicate that theistress in the claddingH due _ to hydrogen pressure from the dissociation of : zirconium-hydride :will.' remain below the -ultimate-_ stress provided that. the temperature . of the , fu,1 does - noti exceed.- 1150*C and the fuel cladding 3 does not' exceed 500'C. For conditions that = might - _cause the - clad
~
z
. temperatures to exceed - 500'C the! safety limit of : the fuel should be - set ,
at 950'C.. >
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~' '*4
" Revision 1 Technical Spscificctions Al2.2 Limitine safety System settine h A.2.2.1 Fuel Temperature ;
Applicability _
4 4
This specification applies to the protective action for the reactor ;
fuel element temperature.
Obj ective The objectise is to prevent the fuel element temperature safety _ limit-1 from being reached. l Bases For non pulse operation of the reactor, the 1Laiting safety system setting is _ a temperature- which, if exceeded, shall cause a reactor scram _ to be initiated- preventing the safety limit from being exc.)eded. _ A setting of 550'C- provides a safety margin at the point of measurement of'at least 400'C for standard TRIGA fuel- elements in any _' condition _ of operation. A part of the safety margin is used to account- for the difference between the true and measured temperatures resulting -- from-_ the - actual location of the - thermocouple.
If the thermocouple element-is located in the-hottest position in the core, .
the difference between .- the true and measured temperatures will be only. a_ few degrees since the thermocouple - junction is near the center and- the mid-plane of the fuel element. For pulse operation of the.
reactor, the_ same; limiting safety _ system setting will apply.
However, the temperature channel will have no effect on limiting the peak powers generated .because of its relatively long timel constant -
(seconds) as compared _with the width of the pulse (milliseconds). .In this mode, however,.the temperature trip will act to limit the energy _
release af ter - the pulse if ' the transient rod should not reinsert and.
the fuel temperature continues-to increase, -
i
.+
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Revision 1; Technical Spscifications A.2.2.2 Power Level (Manual, Auto, Square Vave)
Applicability This specification applies to the protective action for the reactor during non pulse operation.
Objective The objective is to prevent the fuel element temperature safety limit from being reached.
Bases Thermal and hydraulic calculations indicate that standard TRICA fuel elements may be safely operated at power levels in excess of 1500 kilowatts with natural convection cooling. Conservative estimates indicate that a departure from nucleate boiling ratio of approximately two will occur at about 1900 kilowatts. A limiting setting for the power level measurement at 1.1 megawatts assures sufficient margin for safety to allow for calibration errors. The power- calibration goal is a measurement accuracy of 5% although an error of 10% may be representative of some measurements.
A.2.2.3 Reactivity Insertion (Pulse)
Applicability This specification applies to the reactivity insertion for the reactor during pulse operation.
Objective The objective is to prevent the iuel element temperature safety limit from being reached.
Bases Calculations indicate that standard -TRIGA fuel elements may be safely operated at transient conditions in excess of 2.2% Ak/k with ambient cooling conditions. Conservative estimates indicate that a substantial safety margin exists for the rise. of peak fuel temperature with reactivity insertions as large as 2.8% Ak/k.
\
D 12/90 Page 40
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1
- Revision-1 Technienl-Spscifications
- j x
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A'3~.0 LIMITING CONDITIONS-FOR OPERATION _ .
APPLICABILITY, OBJECTIVES &' BASES 1
A.3'.1 Reactor Core Parameters >
A.3.1~.1' Excess Reactivity Applicability ,
'This specification applies to the; reactivity condition.of the reactor core in terms of the available excess . above the - cold xenon free, ;'
critical condition.
dbj ective -
The objective is to prevent the fuel element temperature safety, limit !
' from being reached by. limiting the potential reactivity available. in
'the reactor.for any condition of operation. i
' Bases Maximum excess ' core reactivity -is c sufficient - to provide the _ core [
rated power, xenon compensation and - - reactivity _ ~ for shutdown.
Analysis of - the = reactor core _ demonstrates that no single component represents sufficient potential reactivity to
- reach the- fuel element
, temperature safety limit during any condition of operation.
, m.
A'.3.1.2 Shutdown Margin e Applicability = [
This specification applies - to the 1reactivityL margin by which the.
reactor core . will be - considered shutdown when the reactor is not- !
operating.
Objective .
s The objective is to assure that the reactor:can be shut down safely by a margin that is sufficient to Leompensate for the failure of a control rod or'the movement of an experiment.
Bases-The value of the shutdown margin assures that the reactor can be shut-
-down from -- any' operating condition. These conditions' t include - the ,
assumption that the' highest worth' control rod remains fully - withdrawn :- -;
and all moveable experiments are in the most reactive condition.
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Revision 1 Technical Specifications A.3.1.3 Transient Insertions Applicability This specification applies to the total potential worth of the transient rod and the allowable reactivity insertion for reactor pulse operation.
Objective The objective is to limit the reactivity available for pulse insertion to a value that will not cause the fuel temperature safety limit to be exceeded.
Bases Calculations demonstrate that the total insertion of all the transient rod worth will not exceed the fuel temperature safety limit. For a 2.8% Ak/k pulse a safety margin would exist between the fuel element safety limit and the rise of peak fuel temperature above an assumed ambient pool temperature of 50'C, A preset timer insures that the transient rod will not remain in the pulse position for an extended time after the pulse. Experiments with pulsed operation of TRICA reactors by the manufacturer indicate that insertions up to 3.5% Ak/k have not exceeded the fuel temperature safety limit.
A 3.1,4 Fuel Elements Applicability This specification applies to the measurement parameters for the fuel elements.
Obj ective The objective is to verify the physical condition of the fuel element cladding.
Bases The elongation limit has been specified to assure that the cladding material will not be subjected to stresses that could cause a loss of integrity in the fuel containment and to assure adequate coolant flow. The limit of transverse bend has bean shown to result in no
~
difficulty in disassembling the reactor core. Analysis of the removal of heat from touching fuel elements shows that there will be i no hot spots resulting in damage to the fuel caused by this touching.
L Experience with TRIGA reactors has shown that fuel element bowing that could result in touching has occurred without deleterious effects.
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1 l
- :* Revisien 1 Technical Spscifications A.3.2 Reactor Control and Safety System A.3.2.1 Control Assemblies Applicability This specification applies to the function of the control rods.
Objective The objective is to determine that the control rods are operable by specification of apparent physical conditions, the scram times for scrammable control rods and the reactivity insertion rates for standard control rods.
Bases The apparent condition of the control rod assemblies will provida assurance that the rods will continue to perform reliably and as designed. The specification for rod scram time assures that the reactor will' shut down promptly when a scram signal is initiated. 3 The specification for rod reactivity insertion rates assures that the ;
reactor will start up at a controllable rate when rods are withdrawn.
Analysis has indicated that for the ran6e of transients anticipated for a TRICA reactor the specified scram time and insertion rate is
- adequate to assure the safety of the reactor.
A,3.2.2 Reactor Control System Applicability These specifications apply to logic of the reactor control system.
Obj ective The objective is to determine the minimum control system interlocks operable for operation of the reactor.
Bases Interlocks are specified to pr. event function of the control rod drives unless certain specific conditions exist. ~
Program logic of the digital procest. ors implement the interlock functions.
Two basic interlocks control all rod movements in the manual mod The interlock to prevent startup of the reactor at power levels le..s than 2 neutron cps, which corresponds to approximately 4 milliwatts, assures that sufficient neutrons are available for controlled reactor startup. Simultaneous withdrawal of more than one control rod is prevented by an interlock to limit the maximum positive reactivity insertion rate available for steady state operation.
l 12/90 Page 43 l
Revision 1 Technical Specificetions Two basic interlocks control rod movements for the pulse mode. The interlock to prevent withdrawal of the motor driven rods in the pulse mode is designed to prevent chsnging the critical state of the reactor prior to the pulse. A power level interlock controls potential fuel temperature changes by settin6 a limit of less than 1 kilowatt for initiation of any pulse.
Interlocks applicable to the transient rod determine the proper rod operation during manual mode and pulse mode operation. The non pulse condition interlock determines the allowable position of the rod drive for actuation of the FIRE switch. Actuation of the switch applies the air impulse for removal of the transient rod from the reactor core.
,. Auto mode is a special condition of the manual mode with automatic control of the regulating rod. Square wave mode is also a special case of the manual mode with automatic control except that pulse
, logic applies to the initiation of the auto mode condition.
A.3.2.3 Reactor Safety System Applicability These specifications apply to operation of the reactor safety system.
Objective The obj ective is to determine the minimum safety system scrams operable for the operation of the reactor.
Bases Safety system scram functions consist of three types. These scram types are the limiting safety system settings, operable- system conditions, and the manual or program logic scrams. The scrams cause control rod insertion and reactor shutdown.
Scrams for limiting safety system settings consist of signal trip levels that nonitor fuel temperature and power level. The trip levels are conservative by a significant margin relative to the-fuel element temperature safety limit.
Operation without adequate control and safety system power supplies is prevented by scrams on neutron detector high voltage a..d control rod magnet current.
Manual action of the scram switch, key switch, or computer actuation of watchdog timers will initiate a protective action of the reactor safety system. Either of two watchdog circuits provide updating timers to terminate operation in the event that key digital processing routines fail, such as a display system. Each watchdog circuit with four resettable timers contains one trip relay and monitors one microcomputer.
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i Revision 1 Technicc1 Specifications A 3.2.4 Reactor Instrument System l Applicability-These specifications apply to measurements vt reactor operating parameters.
l Objective The objective is to determine the minimum instrument systern channels to be operable for continued operation cf the reactor.
Bases The minimum measuring channels are suf ficione to provide signals for automatic safety system operation. Signals from the measuring system provide information to the control and safety system for a protective action. Instruments provide redundancy by measurements of thu so,me parameters and diversification by measurements of difftrent.
pararac ters . Two redundant temperature thermocouple sensors monitor the fuel temperature limiting safety system setting. Two redundant percent power channels monitor the . power level limiting safety system.: A digital vide range channel may also function as a safety channel-but only by diversification as a supplemental channel to an analog linear power channel. Pulse parameters c. peak power and energy release are- measurements of a single -detector chamber. Tnere are, however, two separate peak and energy monitoring circuits.
i-i 12/90 Page 45
/ LRbviolon1 Technical Spacifications
- t. 3.3 Qpfrational Sunriott System ,
A.5.3.1 Water Coolant Systerns .
Applicability This_ specification applies to the operating conditiont for the reactor pool and coolant water systems.
Obj ective
, The objective is to assure th=c sdequato conditions are maintained to provid.: shielding of the reat %r raf'ntion, protection against corros, ion of the reactor compovents, cooling of the reactor fuel, and prevout leakaSe from the primary coolant.
Bases The specifications for conditions of the pool water coolant system provide controls that art to control the radiation exposures and radioactive releases associated with the reactor fission product inventory,
- a. The bulk water temperature constraint assures that sufficient core cooling exists under all anticipated operating conditions and protects the resin of the water purification system from deterioration,
- b. A pool water depth of 6.5 meters is sufficient to provide more than 5.25 meters of water above -the reactor core so that radiation levels above the reactor poci are at reasonable levels.
- c. Avewge measurements of pool coolant water conductivity of 5.0 pmho/cm assure that vatu purity -is maintained to control the effects of corrosion and activation of coolant water impurities.
- d. A pressure difference ne the heat exchanger chilled water outlet and the pool water inlet of'? kPa will be sufficient to prevent loss of pool water from the primary reactor coolart system to the secondary chilling water system in the event of a leak in the heat exchanger, i
- e. Periodic sampling of pool water pH and radioac tJ.'ri ty arm ;
supplemental c:easurements that assist evaluation of the overait i I
'- conditions of the reactor pool. Protection of aluminun components requires a pH range of 5 to 8.5. Heasurements cf I radioactivity in the pool water provide information to evaluat-working hazards for -personnel, leakage indications for i radioactive sources in the pool, and monitoring for activation l of unknown components in the water.
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Technical Specifications Revision 1 A.3.3.2 Air Confinement Systems Applicability This specification applies to tha air ventilation conditions in the reactor area during reactor operation.
Obj ective The objective is to control the release of air in the reactor area or experimental facilities.
Bases .
The specifications for exhaust ventilation and isolation of the reactor bay provide control for radioactive releases for both routine and non routine operating conditions,
- a. Air confinement of the reactor bay includes a provision for isolation of the air flow of the_ ventilation system. Dampers in the room supply ai'r ducts and room return air ducts limit the leakage rate and total release of radioactive airborne materials to a fraction of the available volume, b,- A signal from a particulate air monitor in the vicinity of the I reactor pool initiates the automatic isolation of the supply air dampers and return air dampers, The isolation process takes less - than one minute and includes the shutdown of supply fan and exhaust fan. An equivalent to one maximum permissible concentration is the set point. i
- c. Air from experiment areas within the_ neutron flux regions of the core will ventilate separately from room air by way of a filter- bank that includes a high efficiency particulate filter.
Space is available to install a charcoal filter for special experiment conditions.
- d. Control of concentrations of argon-41 in reactor room air depends on ventilation of the room air at a rate of two air changes per hour or operation of the auxiliary purge air system. Operation and isolation of the purge system is by manual control of damper and fan switches.
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Rovtston 1 Technical Sp:cificcticns A.3.3.3 Radiation Monitoring Systems Applicability This specif . cation applies to the radiation monitoring conditions in the reactor area during reactor operation.
Objective The objective is to monitor the radiation and radioactivity conditions in the reactor area to control exposures or releases.
Bases The radiation monitors provide information to operating personnel of impending or existing hazards from radiation so that there will be sufficient time to take the necessary steps to control the exposure of personnel and release of radioactivity or evacuate the facility.
Alarm setpoints do not include measurement uncertainty. These setpoints are measured values and not true values
- a. Air particulate radioactivity accumulates on the filter of a continuous monitor that records the radiatico levels. An alert and alarm set point including remote readouts at the reactor control console infora the operator of the monitor status and activity levels. An alarm limit at two thousand picocurie / milliliter detects particulate activity concentrations at the occupational values of 10CFR20. The alarm set point exceeds occupational values for any single fission product nuclide , the ranges 84 105 and 129 149.
Seventy percent of the peet sulate isotopes are also detectable at the reference concentb Aons within two hours. The gaseous argon 41 monitor can provide fission product gas monitoring during repair of the particulate monitor.
- b. Air gaseous radioactivity of argon 41 concentrations require monitoring of the levels for effluent release and cocupational ;
exposure. The alarm setpoint detects a release concentration that will not exceed ten times oither the occupation value at the stack or. the reference conc ntration at the ground, Calculations of a stack release concentration of 1,2 pC1/cm3 indicate that the equivalent ground level concentration is equivalent to 1x10 e pC1/cm3 A license limit for the average annual concentration is necessary to fix the amount of allowable release. Periods of inoperable argon 41 monitoring equipment of up to 10 days limit the amount of release without measurement to a fraction of the total annual release.
- c. Several area radiation monitors (six) are part of the permanent installation. Some locations are experiment areas in which shield configuratima determine the levels of radiation during reactor operation. At the pool access area radiation levels substantial enough to be a high radiation level may occur.
Alarm levels at 100 mr/hr will monitor radiation areas if the limit of 2 or 5 mr/hr is not reasonable.
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i
R3vislen 1 Technical Spocifications A.3.4 Limitations on Experiments A.3.4.1 Reactivity Applicability This specification applies to the reactivity of experiments located in the rear. tor core.
Objective The objective is to control the amount of reactivity associated with experiments to values that will not endanger the reactor safety limit.
Bases
- a. The worth of sir.st e moveable experiment is limited so that sudden removal movement of the experiment will not cause prompt criticality. Worth of a single unsecured experiment will not ceuse a reactivity insertion that would exceed the core temperature safety limit,
- b. The maximum worth of a single experiment is limited so that the fuel element temperature safety limit will not be exceeded by removal of the experiments. Since experiments of such worth must be secured in place, removal from the reactor operating at full power would result in a relatively slow power increase such that the reactor protective systems would act to prevent exceasive power levels from being attained,
- c. The maxiui , worth of all experiments is limited so that removal of the total worth of all experiments will not exceed the fuel element temperature safety limit.
A.3.4.2 Materials Applicability These specifications apply to experiments installed , in the reactor and its experimental facilities.
Objective The objective is to : prevent the release of radioactive material in i the event of an experiment failure, either by failure of the experiment or subsequent damage to the reactor components.
- iases
- a. Double encapsulation requirements lessen the leakage hazards of some types of experiment materials,
- b. Operation of the reactor with the reactor fuel or structure damaged is prohibited to avoid release of fission products.
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l Rsvision 1 Technical Sp:cificctions
- c. Encapsulation requirernent s for explosive materials set a reference condition for the amount of material allowable for any reactor experiment. Damage from the explosive reaction depends on the available ener6y release and resultant gas creation. Approximate conditions for 25 milligrams of explosive inaterial are the release of 25 calories (104 joules) of energy and 25 milliliters of gas. If a 1 milliliter volume is avatlable for the reaction of an explosive material (density 1.654 ga/cm3), the energy will represent an instantaneous pressure of 1032 atmospheres and the gas release adds another 25 atmosphores. Stress calculations for a thin vall, cylindrical m aule specify the requirements for the wall thickness arr' aameter of the encapsulation. The relationship determines the stress liteit as one fourth the product of the ptescure tirnes the capsule diameter to wall thickness ratio.
An aluminum capsule with a 1 milliliter volume requires a ratio that does not exceed 5.2. At a volume of 5 rn111111ters capsule dienensions with a diarneter of 2.6 cm requires a wall thickness of 1 mm. These limiting values are within the constraints of aluminum tubular construction corsponents for experirnent facilities and experiments,
- d. Fission product inventory limits of 750 at111 curie iodine and 2.5 millicurie strontium fix the potential accident release concentrations. These two isotopes represent the radioactive exposure risk to individuals for fissipn product nuclidas with short (iodine) and long (strontium) half lives. If the isotope iodine.131 represents the total inventory release of 750 at111 curies, the facility annual average release. including building wake dilution of the total inventory, will be equivalent to the reference level esneent. ration of 2.:10 *10 pCi/cm). In the case of strontium 90 the release in less than 1/5 the reference level concentration of 5x10 12 pC1/cm3 Proper shutdown of tne ventilation system by manual or automatic operation subs.tantially reduces the effective total release. Any release of the total experiment inventory within the facility, however, in the form of iodine 131 or strontiurn-90 will exceed the occupational values within the facility for the oral ingestion or air inhalation of the radionuclides. As an extreme caso the evacuation times to maintain the average annual concentration are 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> for iodine 131 and 1 month for strontium 90.
- e. Accidental release of radioactive inaterials that cause airborne concentrations must meet 10CFR20 average annual limits.
Concentration limits apply to occupational values that cause exposure within the facility and reference level concentrations that may exist as a release from the facility. Calculations assume a complete release of the material but also must define release rates and frequencies that are conservative or reasonable estimates of accident conditions.
- f. This specification provides guidance for the calculation of conditions in part (e).
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l Revisicn 1 Technicc1 Sp3cificcticns A.4.0 SURVEII.1ANCE REQUIREMENTS OBJECTIVES & BASES A,4.1 Egggtor Core Parameterg A 4.1.1 Excess Reactivity Applicability This specification applies to the measurement of reactor excess reactivity.
Obj ective The objective is to periodically determine the changes in core excess reactivity available for power generation.
Bases Annual determination of excess reactivity ar.d measurements after reactor core or control rod changes are sufficient to monitor significanc changes in the core excess reactivity.
A.4.1.2 Shutdown Margin Applicability This specific.ation applies to the measurement of reactor shutdown margin.
Objective The objective is _ to periodically determine the core shutdown reactivity available for reactor shutdown.
Bases Annual determination of shutdown margin and measurements after reactor core or control rod changes are sufficient to monitor significant changes in the core shutdown margin.
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Revisien 1 Technical Spscificctions A.4.1.3 Transient Insertion Applicability This specification applies to surveillance of the transient rod mechanism and to observation of the reactor transient response.
Objective The objective is to assure the function of the transient rod drive and to compare the reactor pulse insertion parameters.
Bases Annual inspections of the pulse rod drive system should be sufficient to detect and correct changes in the system that could impair operability. Coniparison of pulse parameter data should detect characteristic changes of reactor core transients.
A.4.1.4 Fuel Elements Applicability This specification applies to the inspection requirements for the fuel elements.
Objective The objective is to inspect the physical condition off the fuel element cladding.
Bases The frequency of inspection and measurement schedule is based on the parameters most likely to affect the fuel cladding of a pulsing reactor operated at moderate pulsing levels and utilizing fuel elements whose characteristics are well known.
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Revisicn 1 Technicci-Sp3cificctions A.4.2 Reactor Control and Safety System A.4.2.1 Control Assemblies Applicability 4
This specification applies to- the surveillance of the control rods.
Objective The objective is to inspect the physical condition of the reactor control rods - and establish the operable condition of the rod - by periodic measurement of the scram times and insertion rates.
Basea Annual' determination of control rod worths or measurements after significant core changes provide information about changes in reactor total reactivity and individual rod worths. The frequency of inspection for the control rods will-provide periodic verification'of-the condition of'the control rod assemblies. Verification will be by measurement of fueled sections and visual observation- of absorber sections plus examination of linkages and drives. The specification intervals -for scram -time and insertion rate assure operable performance of -the rods. Deviations that are significant from acceptable standards will be promptly corrected, i
A.4.2.2 Reactor Control System Applicability This specification applies to the tests of the logic of the reactor control system.:
objective The objective is. to specify intervals for test, check or calibration of the minimum control system interlocks.
Bases The periodic test of the interlock logic at semiannual intervals provides adequate information that the function of the ' control system i interlocks are functional. Changes to the interlock logic consist of revisions. to the microcomputer algorithms (hardware,- sof'evare . or-firmware) and repair of - input or output circuits including devices that are sensors for the interlocks. Calibrations or checks of the control system logic are not considered applicable functions.
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Rovisicn 1 Technicol Spocificctions A.4.2.3 Reactor Safety System Applicability This specification applies to tests of the function of the reactor safety system.
Objective The objective is to specify intervals for test, check or calibration of the minimum safety system scrams.
Bases The periodic calibration at annual intervals provides adequate l information that the setpoints of the safety system scrams are functional. Tests of the safety system prior to each planned operation assure that each stended scram function is operable.
A.4.2.4_ Reactor-Instrument System Applicability These specifications apply to calibrations, checks, and tests of reactor measurement channels.
Objective The objective is to specify intervals for test, check or calibration of the minirnum instrument channels, Bases-Annual calibration of instrument channels are scheduled tu allow adj ustments for changes in reactor and instrumentation parameters.
Checks and tests prior to each system operation verify the function of key channels and systems.
12/90 page 54 m- m mi i umw s tiru ti m
Rovision 1 Technicc1 Spscifications A.4.3 Doerational Support Systema A.4.3.1 Water Coolant Systems Applicability This specification applies to surveillance conditions for the reactor pool and coolant water systems.
objective The objective is to insintain the reactor coolant conditions within acceptable specifications.
Bases Conditions for the reactor coolant are monitored by visual observation of measurements or automatic action of sensors. Periodic checks and tests of measurement devices for the reactor coolant system parameters assure that the coolant system will perform its intended function. Measurement frequencies of pool parameters relate to the time periods appropriate to detection of abnormal conditions.
Pool temperature, depth, and heat exchanger pressure differences have i an immediate effect on system operation. Water conductivity, pil as a supplemental indicator, and pool radioactive concentrations are conditions that develop at rates detectable at monthly to annual intervals.
A.4.3.2 Air Confinement Systems Applicability This specificat4on applies to surveillance conditions for the air ventilation in the reactor area, objective The objective is to demonstrate the function of confinement and release of air from the reactor bay.
Bases Periodic tests and checks of air confinement conditions verify appropriate ventilation functions. Monitoring frequencies verify performance of the confinement system exhaust daily by an alignment check that includes observation of negative pressures. Testa of the isolation feature at monthly intervals assure the acceptable operation of the system.
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Revision 1 Tochnical Sp:cificetions A.4.3.3 Radiation Monitoring S) : ems Applicability This specification applies to the surveillance conditions of the radiation monitoring channels.
Objective The objective is to assure the radiation monitors are functional.
Bases Periodic calibrations and frequent checks are specified to maintain reliable performance of the radiation monitoring instruments.
Calibration and check frequencies follow the general recommendations of guidance documents.
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Revision 1 Technical Sp cifications A.4.4 Limitations on Exneriments .
A.4.4.1 Reactivity
[ Applicability This specification applies to surveillance of the reactivity of experiments.
(
Objective ;
The objective is assure the reactivity of an experiment does not {
exceed the allowable specification. ,
i Bases ,
The measured' reactivity or determination that the reactivity 'is not ,
significant will provide data that configuration of the experiment or ;
experiments is allowable.
A.4.4.1 Materials b
Applicability This specification. applies to the surveillance requirements for materials inserted into the reactor. ,
Objective (
The objective is to prevent' the introduction of materials that could. ;
damage the reactor or its components.
Bases' A careful evaluation of all experiments is performed to classify the ,
experiment as an approved experim..nt. [
4 i-12/90 Page 57 e+ p ws g & ar y y y y p y- r w et'
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[ Revisien 1 Tochnicc1 Sp2cifications
' I
.A.$.0 DESIGN FEATURES
~ OBJECTIVES & BASES l
'A.$.1 jite and Facility Descriotions ;
A.$.1.1 Location .
Applicability This specification applies to the TRIGA reactor site location and ,
specific facility design features. ,
objective -
The objective is to sp -4 fy those features related to the Safety -
Analysis evaluation.-
Bases. .
- a. The TRICA facility- s a .e locateo in-an area controlled-by The University of Texas at Austin. ,
- b. The room enclosing the reactor. has. been designed with characteristics related~to the safe operation of the facility. ,
- c. The shield and pool structure have been- desi5 ned for radiation i
levels of less than 1 ares /hr at locations. that' are not access ports to the reactor structure.
~
- d. The- restricted access to specific - facility areas assure that proper controls are established for the safety of the public and for the security of special nuclear materials. ._.
t
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Rsviolen 1 Technicc1 Sp3cificaticns !
A.5.1.2 Confinement Applicability This specification applies to the boundary for control of air in the area of the reactor.
Objective The objective is to assure that provisions are made to control or restrict the amount of release of radioactivity into the environment.
Bases
- a. Calculations of the concentrations of released radionuclides within the reactor area depend on the available enclosed air volume to limit the concentrations to acceptable levels,
- b. Control of tF reactor area air exchange is by fan motors and isolation dat ers for the supply and exhaust air which are controlled by a logic signal from a radiation sensor to provide j automatic air confinement.
- c. Emergency air ventilation is filtered to control the release of particulates and a pressure difference relative to the external ambient pressure is intended to prevent leakage of air without filtratier.,
- d. Exhaust air during reactor operation is released at an elevated level for dispersion and is designed to provide a relative pressure difference to the external ambient pressure.
A.5.1.3 Safety Related Systems i i
Applicability This specification applies to the requirements of any system related to reactor aafety, Obj ec tive I
The objective is to assure the proper function of any system related to reactor safety.
Bases This specification relates to changes in reactor systems which could affect the safety of the reactor operation. Changes or substitutions to these systems that meet or exceed the original design specifications are assumed to meet the presently - accepted operating criteria. Questions that may include an unreviewed safety question are referred to the reactor operation committee.
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n j Revision 1 Technical Spacifications )
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l 1
A.S.2 Rs. actor Cooiant system i
- - Applicability This specification applies to the - reactor coolant system composed of deionized water.- i l
Objoctive The objective is to assure that adequate water . is available for cooling and shielding during reactor operation.
Bases a.. This specification is based on thermal and hydraulic calculations which show that a standard 85 element TRIGA core can operate in a safe manner at power levels up to 1,900 kW with natural convection flow of. the coolant water ' and a departure. from- nucleate boiling ratio of 2.0.
]
- b. . Siphon breaks set the subsequent pool water level for loss of ;
coolant without an associated, water return caused by inadvertent
- , pumping or accidental siphon of water from the pool.
A.5.3 Reactor Core ~and Fuel A.5.3.1 Fuel Elements Applicability .
This specification applies to the . fuel elements used in the reactor. ;
core.-
Objective 3 The objective is to assure that the fuel elements are of such a-
, design and fabricated in such a manner as to permit their.use-with a ,
high degree of reliability with respect to their physical and nuclear >
characteristics.
Bases I
The des _ign basis of the standard ~ TRIGA core demonstrates that 1.' 5 megawatt- . steady or 36 megawatt sec- pulse--operation presents a conservative limitation with respect to safety 1.imits for_the maximum _ .
temperature generated . in the fuel. The fuel temperatures are j not - -!
l expected to exceed 550*C during any condition of normal. operation. .
t
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Revisien 1 Technical Spwificctions 1
i A.5.3.2 Control Rods Applicability This specification applies to the control rods used in the reactor core. l l
Objective The objective is to assure that the control rods are of such a design as to permit their use with a high degree of reliability with respect ;
to their physical and nuclear characteristics, Bases The poison requirements for the control rods are satisfied by using neutron absorbing borated graphite, B6C powder, or boron and its compounds. These materials must be contained in a suitable clad material, such as aluminum or stainless steel, to insure mechanical stability during movement and to isolate the poison from the pool water environment. Scram capabilities are provided for rapid insertion of the control rods which is the primary safety feature of the reactor.- The transient control rod is desi 6ned for a reactor pulse.
. A minimum configuration of control rods consist of two shim rods, a regulating rod and the transient rod.
The configuration of rods is necessary for the -reactor to be operable. If the appropriate adjustmentr. to the core reactivity are made the removal of one or more of the control rods will f acilitate the necessary inspection and repair activities. Definitions for shutdown and suberitical require the reactor core to meet the suberitical constraint if any rod is out of the core and the reactor is to be shutdown.
A.5.3.3 Confi6uration Applicability This specification applies to the configuration of fuel elements, control rods, experiments and other reactor grid plate components.
Objective The objective is to assure that provisions are made to restrict the arrangement of fuel elements and experiments to provide assurance that excessive power densities will not b< produced.
Bases Standard TRICA cores have been in use for years and their characteristics are well documented, 12/90 Page 61
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Rovicion 1 Tochnicc1 Sp2cificctions A.5.4 Reactor Puel Element Storagg Applicability This specification applies to the storage of reactor fuel at times when it is not in the reactor core.
Obj ective The objectivo is to assure that fuel storage will not achieve criticality and will not exceed design temperatures.
Bases The limits imposed by these specifications are considered sufficient to provide conservative fuel storage and ascure safe storage.
A $.$ Camma Pool Irradiator Applicability This specification applies to the gamma irradiator experiment facility in the reactor pool.
Obj ective The objective is to assure that the use of the irradiator does not cause any threat to the reactor or safety question.
Bases Location of the irradiator is at a distance from the reactor sufficient to avoid interference with reactor operation. Depth of the pool water for adequate shielding of the irradistor is also a constraint of the location 12/90 Page 62
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l A.6.0 NOTES This section is blank l
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