ML20100L927
| ML20100L927 | |
| Person / Time | |
|---|---|
| Site: | University of Texas at Austin |
| Issue date: | 11/30/1984 |
| From: | TEXAS, UNIV. OF, AUSTIN, TX |
| To: | |
| Shared Package | |
| ML20100L920 | List: |
| References | |
| NUDOCS 8412120141 | |
| Download: ML20100L927 (51) | |
Text
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Technical Specifications 6.-
The University of Texas at Austin TRIGA Reactor 2
November 1984
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.Tachnical-Sp cifications-9/84 Table:of Contents 1.0' DEFINITIONS 5
-. 1.1 GENERAL 1 TERMS-5 1.1.l~
Research Reactor!
5 1.1.2
. Confinement
.5
.1.1.3 Operable-5 1.1.4
' Operating.
5-1.1'. 5
-Safety Limit.
5
-1.1.6
' Reactivity Limit 5
'1.1.7
. Excess Reactivity.
5
'l.1.8
. Shutdown Margin 6
1.1.9 Safety System-6 1.1.10 Protective Action 6
-1. 2 ' REACTOR COMPONENTS 6
1.2.1 Control Rod 6
1.2.2 Safety Rod 6
1.2.3 Shim Rod 7-1.2.41 Regulating Rod 7
1.2.5 Transient Rod 7
.l.2.6
~ Standard Fuel 1 Element 7
- 1.2.7 Standard Fuel Element 7
1.2.8 Instrumented Element 7
1.2.9
- Standard Core.
7 1.2.10'
-Operational Core 7
1.3 OPERATING CONDITIONS 8
1.3.1 Reactor' Secured 8
'l.3.2
' Reactor Shutdown 8
1.3.3 Unscheduled Shutdown 8
1.3.4.
Reactor-Operating 8
.1.3.5 Steady. State Mode 9
1.3.6i Pulse: Mode 9
' 1.4 REACTOR INSTRUMENTATION 9
- 1. 4. l'
. Channel 9
1.4.2
= Measured Value 9
'1.4.3
.True Value 9
1.5-REACTOR EXPERIMENTS 10 1.5.1 Experiment
-10 1.5.2 Moveable Experiment 10 1.5.3 Secured Experiment 10-1.5.4 Experimental Facilities 10 1.6' REACTOR OPERATORS 10 1.6.1 Certified Operators 10 1.6.2 Class'A? Reactor Operator 11
'1.6.3
. Class B Reactor Operator 11
- 1.7 SURVEILLANCE INTERVALS 11 1.7.2 Surveillance Intervals 11 1.7.2 Surveillance Activities 11 2.0 SAFETY. LIMITS AND LIMITING SYSTEM SETTINGS 12 2.1-FUEL ELEMENT TEMPERATURE SAFETY LIMIT 12-4 2.2 LIMITING SAFETY SYSTEM SETTINGS
'13 2.2.1 Fuel Element Temperature 13 2.2.2 Steady State Power 14 Page 2
)
e Technical Specifications 9/84 3.0 LIMITING CONDITIONS FOR OPERATION 15 3.1 REACTIVITY LIMITS 15 3.1.1 Shutdown Margin 15 3.1.2 Excess Reactivity 15 3.1.3 Transient Insertions 16 3.2 CONTROL AND SAFETY SYSTEM 17 3.2.1-Operable. Control Rods 17 3.2.2 Reactor Control System 17
-3.2.3 Reactor Safety System 19 3.2.4 Reactor Instrument System 20 3.3 ' OPERATIONAL SUPPORT SYSTEMS 21 3.3.1 Reactor Coolant Conditions 21
.3.3.2 Air Ventilation Conditions 22 3.3.3 Radiation Monitoring Conditions
'23 3.4 L.TMITATIONS ON EXPERIMENTS 24 3'.4.1 Reactivity 24 3.4.2 Irradiations 25 3.4.3 Materials 26 4.0 LIMITING CONDITIONS FOR OPERATION 28 4.1 REACTIVITY LIMITS 28 4.1.1 Shutdown Margin 28 4.1.2 Excess Reactivity 28 4.1.3 Transient Insertions 29 4.2 CONTROL AND SAFETY SYSTEM 29 4.2.1 Operable Control-Rods-31 4.2.2 Reactor Control.t' stem 30 4.2.3 Reactor Safety System 30 4.2.4 Reactor Instrument System 31
.4.3 OPERATIONAL SUPPORT SYSTEMS 32 4.3.1 Reactor Coolant Conditions
-32 4.3.2 Air Ventilation Conditions 32 4.3.3 Radiation Monitoring Conditions -
33 4.4 LIMITATIONS ON EXPERIMENTS 34 4.4.1 Reactivity 34 4.4.1 Irradiations 34 4.4.2 Materials 35 5.0 DESIGN FEATURES 36 5.1 QUALITY CONTROL 36 5.1.1 Safety Related Systems 36 5.1.2 Fuel Element Inspections 36 5.1.3 Control Rod Inspections 37 5.2 REACTOR CORE 38 5.2.1 Configuration 38 5.2.2 Standard Fuel Elements 38 5.2.3 Control Rods 39 5.3 FACILITY DESIGN-40 5.3.1 Reactor Shield, Pool and Coolant 40 5.3.2 Air Confinement 41 5.3.3 Radiation Monitoring 41 5.4 REACTOR FUEL ELEMENT STORAGE 42 ryy.n_3
m Technical Specifications 9/84 6.0'ADMINISTATIVE 43 6.1 ORGANIZATION-43 6.1.1
-Structure 43 6.1.2 Responsibility
-43 44 6.1.3 Staffing
.44 6.1.4 Selection and Training of~Pesonnel 6.2 ' REVIEW AND AUDIT 44 6.2.1 Composition and Qualifications 44 6.2.2.
Charter and Rules 45 6.2.3.
Review Function 45 6.2.4 Audit Function 45
- 6.3 PROCEDURES 46
- 6. 4 - EXPERIMENT REVIEW AND APPROVAL 47
-6.5 REQUIRED ACTIONS 47 6.5.1 Action to be Taken in. Case of Sefety Limit Violation 47 6.5.2 Action to be Taken in the Event of a Reportable Occurrence 47
. 6.6 REPORTS 48 6.6.1 Operating Reports 48 6.6.2 Special Reports 49 6.7 RECORDS 50 L6.7.l' Records to be Retained for a Period-of at Least Five Years or the Life of the Component
-50 6.7.2 Records to be Retained for at Least One Training Cycle 51 6.7.3 Records to be Retained for the Lifetime of the Facility 51 i
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Technical Specifications 9/84 1.0 DEFINITIONS 1.l' GENERAL TERMS 1.1.1 Research Reactor A researchLreactor-is defined as a device designed to support a self-sustaining neutron chain reaction for research, development,-training, educational,.or experimental. purposes, and.which may have provisions for the production of radioisotopes.
1.1.2 Confinement Confinement is the enclosure on the overall facility which controls the movement of air into it and out through a controlled path.
1.1.3 Operable Operable means a system or component is capable of performing its intended function.
-1.1.4 Operating Operating means a system or component is performing its intended function.
1.1.5 Safety Limit Safety limits are 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.
1.1.6 Reactivity Limit-The reactivity limits are thase limits imposed on the reactor core excess reactivity.
Quantities are referenced specifically to a clean core (ambient) with the effect of xenon poisoning on core reactivity accounted for if greater than.33 dollars.
The reactivity worth of samarium in the core need not be included in excess reactivity limits.
The reference e
core condition will be known as the cold xenon free condition.
1.1.7 Excess Reactivity Excess reactivity is that amount of reactivity that would exist if all the control rods were moved to the maximum reactive condition from the reactor shutdown condition.
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Technical' Specifications 9/84-y 21.l'.8
. Shutdown' Margin ShutdownLmargin is the minimum reactivity necessary to
. provide' confidence:that the reactor;can be made subcriticalJby means ofLthe control and safety systems starting 1from any permissible operating; condition, that the most: reactive rodtis stuck in.its most reactive ~
. position, and that the reactor will remain subcritical without further operator. action.
^
~ 1 '. l. 9 Safety System Reactor; safety systems are those. systems, including _
their associated. input channels, which.are designed to-
-initiate automatic reactor protection or ta) provide.
information-for initiation of manual protective: action.
l'l.10 Protective-Action
. Protective-action is the initiation of a signal or the
' operation of equipment.within'the. reactor safety 1 system in~ response to a. variable or condition of the reactor facility having reached a' limit specified.in the. design basis.
a.
At_the' reactor safety system level, protective action is the operation:of' sufficient equipment to immediately shut down the' reactor.
b.
At'the' protective instrument system' level, protective action is thejgeneration and transmission of the command signal for the safety.
shutdowniequipment to' operate.
c.
At.the: protective instrument channel level, protective action iszthe. generation.and transmission of.a trip signal indicating that a reactor variable has reached the specified limit.
1.2 REACTOR COMPONENTS 1.2.1 Control Rod 1
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 disengaged.
1.2.2
. Safety Rod A safety rod is a control rod having an electric motor driv'e and scram capabilities.
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-Technical Specifications 9/84
'l.2.3-Shim Rod
.A' shim rod is'a~ control rod having an electric motor
~ drive.and. scram capabilities.
1.2.4 Regulating Rod A regulating rod is a low, worth rod used primarily to maintain _an intended power level and may be varied manually-or by a servo-controller.
The regulating. rod may have scram capability.
1.2.5-Transient Rod
- JL transient rod is a control rod that is capable of providing rapid reactivity insertion to produce a power
. pulse. The transient ~ rod shall have scram capability.
1.2.6 Standard Control Rod The safety, shim and-regulating rods are standa'rd control-rods.
1.2.7 Standard Fuel Element A fuel element is a single TRIGA fuel' rod of standard type.
Fuel is U-ZrH clad'in stainless steel clad.
1.2.8 Instrumented Element An instrumented element is a special fuel element fabricated for temperature measurement.
The element shallihave at least one thermocouple embedded ~in the fuel near the horizontal center' plane.
.l.2.9 Standard Core A standard core is an arrangement of standard TRIGA fuel in the reactor grid plate and may include installed' experiments.
1.2.10 Operational Core 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.
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- o Technical Specifications 9/84 1.3 OPERATING; CONDITIONS 1.3.1 Reactor Secured-The reactor is secured when:
a.
It contains insufficient fissile material or moderator present in the reactor, control rods or adjacent experiments, to attain criticality under optimum available conditions of moderation and reflection, or b.
1.
The minimum number'of neutron absorbing control rods are fully inserted or other safety devices are in shutdown position, as required by technical specifications, and 2.
The console key switch is in the off position and the key is removed from the lock, and 3.
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, and 4.
No experiments in or near the reactor are being moved or serviced that have, on movement, a reactivity worth exceeding the maximum allowed-for a single experiment or one dollar which ever is smaller.
1.3.2 Reactor Shutdown The reactor is shutdown when the reactor at ambient temperature and xenon free condition, including the reactivity worth of all experiments, is subcritical.by at least one dollar.
1.3.3 Unscheduled Shutdown An unscheduled shutdown is defined as any unplanned shutdown of the reactor caused by actuation.of the reactor safety systela, operator error, equipment malfunction, or a manual shutdown in response to conditions which could affect safe operation, not to
' include shutdowns which occur during testing or check-out operations.
1.3.4 Reactor Operating The reactor is operating whenever it is not secured or shutdown.
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TschnicalLSpecifications 9/84 11.3.5 Steady State Mode Steady state mode operation shall mean operation of the reactor with the mode selector switch in the
- steady-state position.
II.326-
. Pulse Mode
- Pulse mode operation shall mean:any operation of the reactor with the-mode selector switch in the pulse:
position.
1.4 REACTOR INSTRUMENTATION 1.4.1 Channel i
.A channel :Ls the combination.of sensors,. lines, amplifiers, and output devices which are connected-for the purpose of measuring the value of a parameter.
a.
Channel test is the introduction of a signal into l
the channel for verification that it operates.
1 b.
Channel check is a qualitative verification of acceptable performance by observation of channel
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behavior.. This verification where possible,.shall include comparison of the channel with other:
independent systems measuring-the same variable._
L c.
Channel calibration is an adjustment of the channel-such that-its output corresponds'with acceptable accuracy to known values of the parameter which~the channel measures.
Calibration shall ' encompass the entire channel, including equipment actuation, alarm, or trip and shall be deemed to include a channel test.
1.4.2 Measured Value
- The measured value is the value of a parameter as it appears on'the output of a channel.
1.4.3 True Value The true value is the actual value of a parameter.
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Technical'Spscifications 9/84 1.5 REACTOR EXPERIMENTS
'1.5.1
. Experiment Any operation, equipment, or target (excluding devices such as detectors,--foilc, etc.), which is designed to investigate.non-routine reactor characteristics or
.which_ is _ intended for irradiation within the pool, cn1 or in a' beam port or irradiation facility and which is not' rigidly secured to a core or: shield structure-so as to be part of their design.
-1.5.2 Moveable Experiment A moveable experiment.is one where it is intended that the entire experiment may be moved in or near the core or into and out of the reactor while the reactor is operating.
l1.5.3 Secured Experiment A secured experiment is any experiment, experiment facility,.or component of an experiment that is held in
-a stationary position relative to the. 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 ari'se as a result of credible conditions.
~1.5.4
_ Experimental Facilities Experimental facilities.shall mean rotary specimen rack, pneumatic transfer tube, central thimble,fbeam tubes and irradiation facilities in the core or.in the pool.
The cobalt-60 facility will be considered an experiment facility.
1.6 REACTOR OPERATORS
- 1. 6.'l Certified Operators Jul individual authorized by the chartering or licensing organization to carry out the responsibilities associated with the position requiring the certification.
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g Tschnical' Specifications 9/84
-1.6.2 Class-A Reactor Operator An individual who=is certified to direct the activities of Class!B reactor operators.
Such an individual is also a-reactor operator and is commonly referred.to as a Senior Reactor Operator.
.l.6.3.
Class B Reactor Operator An individual who is certified to manipulate'the controls of a. reactor.-
Such an individual is commonly referred to as a Reactor Operator.
1.7. SURVEILLANCE INTERVALS 1.7.2 Surveillance Intervals Maximum intervals are to provide operational flexibility and not to reduce frequency.
Established frequencies shall.tue maintained over the long term.
Allowable surveillance intervals shall not exceed the following:
- a. 5 years (interval not to exceed 6 years)
- b. 2 years (interval not to exceed 2-1/2 years)
- c. Annual (interval not to exceed 15 months)
- d. Semiannual (interval not to exceed 7-1/2 months)
- e. Quarterly-(interval not to exceed 4 months)
- f. Monthly (interval not to exceed 6 weeks)
- g. Weekly (interval not to exceed 10 days)
- d. Daily (must be done during the calendar day) 1;7.2 Surveillance Activities Surveillance activities, (except those specifically required for safety when the reactor 11s shutdown).may be deferred during reactor shutdown, however.they must be completed prior to reactor startup.
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.
In general, two types'of surveillance activities are specified, operability checks and calibrations.
Operability checks are generally specified as monthly to quarterly.
Calibrations are generally specified as annually to biennially.
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Technical Specifications 9/84 t.
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7 2.0' SAFETY LIMITS AND LIMITING SYSTEM SETTINGS 2.1 FUEL ELEMENT TEMPERATURE SAFETY LIMIT
~ Applicability L-This specification. applies 1to the temperature of the reactor l-fuel in a standard TRIGA: fuel element.
' Objective 1
The.objectiveLis to define the maximum temperature that can be-permitted with confidence that.no damage to the fuel element-cladding will result..
Specification (s)-
The maximum temperature in a standard TRIGA fuel element shall not exceed ll50?C for fuel-element clad temperatures.
less than 500 C and shall not exceed 950 C for fuel element i
0 cladLtemperatures greater than 500 C.
Temperatures apply-to
.any condition of' operation.
Basis The important parameter for a TRIGA' reactor is the fuel element temperature.. This parameter is well suited as a l
-single' specification since it'can be measured directly.
A l/ -
' loss-in the integrity of the fuel element cladding could L
arise from'a. build-up_of excessive pressure between the L
fuel-moderator and the cladding if the fuel temperature-exceeds the-' safety limit.
The pressure;is~causedLby 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 to l
zirconium in the alloy.
l-The safety limit for the standard TRIGA fuel is based on E.
calculations and experimental evidence.
The results iindicate that the stress in the cladding.due to' hydrogen
' pressure from the dissociation of zirconium hydride will.
remain below the ultimate stress provided that the
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temperature of the fuel ~does not exceed 11500C and the fuel 0
cladding-does not exceed 500 C.
For conditions that'might
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.cause the clad temperatures to exceed'5000C the safety limit of the fuel should be set at 950 C.
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1 Technical Specifications 9/84 1
2.2 : LIMITING' SAFETY SYSTEM SETTINGS 2.2.1 Fuel Temperature Applicability.
This' specification applies to the protective action for the reactor-fuel element temperature.
-Objective
-The_ objective is to prevent the fuel element temperature safety limit from being reached.
Specification (s)
The limiting safety system' setting shall.be 550?C as L
measured in an instrumented fuel-element.
The instrumented element shall-be located in the B ring of the' reactor core
- configuration..
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Basis l
-The limiting safety system setting is a temperature which, L
11f exceeded,'shall cause a. reactor _ scram to be initiated L
preventing-the safety. limit from.being exceeded.
A setting of.5500C provides a safety margin at the' point of measurement of at least 40000 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 h
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.
i In the pulse mode of operation, the same limiting safety system setting will apply.
However,-the temperature channel will have no effect on limiting the-peak powers generated l
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- because of its relatively long time constant (seconds) as compared with the width of the pulse (milli' seconds).
In this mode, however,'the temperature trip will act to limit the energy release after the pulse if the transient rod should not reinsert and the fuel temperature continues to increase.-
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- .0 Tschnical Spacificationo 9/84 2.2.2 Steady State Power Applicability-This specification applies to the protective action for power. generated in the reactor during continuous operation.
Objective The objective is to prevent the fuel element temperature safety limit from being' reached.
Specification (s)
The normal steady state operating power level of_the reactor shall be 1000 kilowatts,.provided that
- a. The reactor power level shall not exceed _1100 kilowatts under any condition of operation, and
- b. The reactor may be operated at power levels not to exceed 1100 kilowatts during-short periods for the purposes of test and calibration.
Basis Thermal and hydraulic calculations indicate that standard TRIGA fuel elements may be safely operated at power levels in excess of 1500 kilowatts with natural convection cooling.
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. Technical. Specifications 9/84 L,
- 3.0-LIMITING CONDITIONS FOR. OPERATION 3.1 REACTIVITY LIMITS
-3.1.1 Shutdown Margin.
Applicability This specification applies to the-. reactivity margin'by which
~
the reactor core will be considered shutdown when the
-reactor is not operating.
Objective The objective is to' assure that the reactor can be shut down
- safely by a margin that is sufficient to compensate for the failure.of a control rod or the movement of an experiment.
Specification (s)
The reactor shall not:be operated unless-the shutdown margin-provided by control rods is greater'than~0.24 k/k with:
a.
the reactor in the cold xenon free condition, b.
the most-reactive control rod fully withdrawn, c.
the highest worth non-secured experiment in its most reactive state.
Basis The value of the shutdown margin assures that the reactor can be' shut down from any operating condition even if the-highest worth control rod should remain in the fully withdrawn position and an unsecured experiment is in a high reactivity state.
3.1.2 Excess Reactivity Applicability This specification applies to the reactivity condition of the reactor core in terms of tre available excess above the cold xenon free, critical condition.
Objective 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.-
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Tschnical specifications'9/84 Specification (s)
Maximum excess _ reactivity shall be 4.9% 6k/k.
Basis Maximum' excess core reactivity is 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 oto reach the fuel element temperature safety limit during any condition of operation.
3.1.3-Transient Insertions Applicability This specification applies to the tc.al potential. worth of' 1-theltransiant 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.
Specification (s)
Total worth of transient rod shall be limited to 2.84 6k/k, and a.
The reactivity to be inserted for pulse operation shall be initiated from power levels less than 1-
- kilowatt, b.
The pulse reactivity insertion shall.not exceed 2.2% 4k/k, and shall be limited by a mechanical block'on the pulse-rod.
Basis Experiments with pulsed operation of TRIGA reactors indicate
'that insertion up to 3.5% 6 k/k have -not exceeded the fuel temperature safety limit.
Calculations demonstrate that the rotal insertion of all the transient rod' worth will not exceed the fuel temperature safety limit.
Thus for a 2.24-6k/k pulse a. substantial safety margin exists.between the fuel element safety limit and the rise of peak fuel temperature above the ambient temperature of 500C.
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Technical Specifications 9/84 m
3.2 CONTROL AND SAFETY SYSTEM 3.2.1 Operable Control Rods Applicability This specification applies to the function of the control rods.
S Objective The' objective is to determine the operability of the control rods by specification of the scram times for scrammable control rods and reactivity insertion rates for standard control rods.
Specification (s)
The reactor shall not be operated unless the control rods are operable, and a.
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 2 seconds.
b.
Maximum reactivity insertion rate of a standard control rod shall be less than 0.2% 6k/k per-second.
Basis The specification for rod scram time assures that the reactor will shut down promptly when a scram signal is initiated.
The specification for rod reactivit'y insertion rates assures that the reactor will start up controllably when rods are withdrawn.
Analysis has indicated that for the range of transients anticipated for a TRIGA reactor the specified scram time and insertion rate is adequate to assure the safety of the reactor.
3.2.2 Reactor Control System Applicability These specifications apply to logic of the reactor control system.
Objective The objective is to determine the minimum control system interlocks operable for operation of the reactor.
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Technical Specifications 9/84 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 Steady-State Pulse
- a. All Control Rods 1
prevent for X
Startup Withdrawal less than 2 counts per sec
- b. All Control Rods 1
prevent for X
Simultaneous Withdrawal two or more rods
- c. Transient Rod 1
prevent X
Withdrawal unless all rods are down
- d. Transient Rod 1
prevent any X
rod withdrawal except transient
- e. Transient Rod 1
reinsert transient X
rod within 15 secs Basis Interlocks are specified to prevent function of the control rod drives unless certain npecific conditions exist.
The interlock to prevent startup of the reactor at power levels less thgn 2 neutron cps, which corresponds to approximately 4 x 10 watts. 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.
Several interlocks applied to the transient rod determine the proper rod operation duri.ng pulse operation and protect against inadvertent pulse operation.
The interlock to prevent withdrawal of the motor driven rods in the ptise mode is designed to prevent changing the critical state of the reactor prior to the pulse.
A preset timer insures that the transient rod will not remain in the pulse position for an extended time after the pulse.
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':S-Technical Specifications 9/84 L3.2.3 Reactor Safety System
- 3
. Applicability i
These specifications apply to operation of the reactor Lsafety system.
Objective The objective.is to determine the minimum safety. system scrams operable for the operation of.the reactor.
Specification (s)
The reactor shall not be operable unless the minimum safety channels are operable.
The following control rod scram E
. safety channels shall be operable.
l Number Effective Mode Rafahy channel Onarable Function Steady-Stata Pulna a.
Scram on~
X X
p Console Button operator demand b.
Fuel Temperature 1
Scram at 550 C X
X c.
Linear Power Level 1
Scram at 110%
X of full scale d.
Percent Power' Level.
1 Scram at.110%
X t
[
of full scale i
e.
Peak Pulse Power 1
Scram at 110%
X of full scale s
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LHigh Voltage 1
Scram on X
X loss of I
g.
Magnet Current 1
Scram on X
X loss of l
i li,
-Basis
}
L I
I' Manual operation of the reactor safety system is considered l
part of the protective action of-the reactor safety system.
Signals-for control rod insertion and reactor shutdown provide, scrams on excessive fuel temperature and power level.
i that is short of the fuel element temperature safety limit.
Operation without adequate control and safety system power I
supplies is. prevented by scrams on neutron detector high voltage and control ~ rod magnet current.
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Technical Specifications 9/84 3.2.4 Reactor Instrument System Applicability These specifications apply to measurements of reactor operating parameters.
Objective The objective is to determine the minimum instrument system channels to.be operable for continued operation of the reactor.
Specification (s)
A minimum configuration of measuring channels shall be operable.
The following minimum reactor parameter measuring channels shall be operable:
Number Effective Mode Measuring channel Operable Steady-State Pulse a.
Fuel Temperature 1
X X
b.
Linear Power Level 1
X c.
Percent Power Level 1
X d.
Peak Pulse Power 1
X Basis The minimum measuring channels are sufficient 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.
Measurements of the same or different parameters provide redundancy.
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L Technical Specifications 9/84 3
3.3 OPERATIONAL ~ SUPPORT SYSTEMS 3.3.1
- Reactor Coolant Conditions Applicability This specification applies to the operating conditions for the reactor pool and coolant water systems.
Objective-LThe. objective is to assure that adequate conditions are maintained to provide shielding of the reactor radiation, protection agaitist corrosion of the reactor ~ components,
. cooling of the reactor fuel, and prevent leakage from the primary coolant..
Specification (s)
Corrective action shall be taken or the reactor shall be.
shutdown ~if the following reactor coolant water conditions are observed:
a.
the water conductivity, averaged for periods of one month, is greater than 5.0 naho/cm, or b.
.the bulk pool water temperature exceeds 48?C, or c..
the water depth, measured from the top grid plate to.the pool water surface,'is less than 5.0 meters, or d.
the pressure difference during heat exchanger operation, measured between.the chilled water outlet pressure and the pool water inlet pressure to the heat exchanger, is less than.7kPa -(1 psi).
Basis The specifications for conditions of the pool water coolant
- system provide controls that are to control radiation exposures and radioactive releases associated with the reactor fission product inventory.
a.
Average measurements of pool coolant water conductivity 5.0 umho/cm provide sufficient information to control the effects offcorrosion and activation of coolant water impurities.
b.
The bulk water temperature constraint assures that sufficient core cooling exists under all anticipated operating-conditions and protects the water purification system resin from deterioration.
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- .n Tachnical Specifications 9/84-c.
Calculations and experience at TRIGA facilities have shown that 5.0 meters of water above the reactor core is sufficient to provide reasonable radiation levels above the reactor pool.
d.
A pressure difference at the heat exchanger chilled water outlet and pool-water inlet of 7kPa tshould be. sufficient to prevent loss of pool water to the secondary chilled water system from the primary reactor coolant system in the event of a leak-in the heat exchanger.
3.3.'2 Air Ventilation Conditions Applicability This specification applies to the air ventilation conditions in the reactor area during reactor operation.
Objective The objective is to control'the air flow from experimental facilities and the reactor bay by isolation or controlled release of~the ventilation exhaust.
Specification (s)
The reactor shall not be operated unless minimum conditions for airfconfinement are functional.
The_following minimum
. conditions shall exists Equipment shall be operable to isolate the reactor a.
bay by closure of access doors and ventilation
- dampers, b.
Air from experimental facilities and the reactor bay shall be exhausted above the reactor bay roof line.
Total argon-41 released from the faciligy shall be c.
3 limited to an annual average of 5 x 10 pCi/cm.
Basis The specifications for exhaust ventilation and isolation of the reactor bay provide control for radioactive releases by both routine and non routine operating conditions.
Page 22
Technical Specifications 9/84 3.3.3 Radiation Monitoring Conditions Applicability This specification 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. area of the reactor for indication of a radioactive release.
Specification (s)
The reactor shall not be operated unless minimum conditions for radiation measurement are functional.
The following minimum conditions shall exists a.
A continuous air monitor (particulate) shall be operable with readout and audible alarm.
b.
An area radiation monitor (gamma) shall be operable with readout and audible alarm.
~
c.
A portable radiation monitoring device shall be available.
The portable monitor may be substituted for the installed monitors during short periods of inoperability.
Basis The radiation monitors provide information to operating personnel of impending or existing hazards from radiation so that there will be sufficient time to evacuate the facility or take the necessary steps to control the exposure of personnel and release of radioactivity.
u -
PaSe 23
Technical ~ Specifications 9/84 3.4 LIMITATIONS ON EXPERIMENTS 3.4.1 Reactivity Applicability This specification applies to the reactivity associated with experiments located in the reactor core.
Objective The objective is control the amount of reactivity associated with experiments to values that will not endanger the reactor safety limit.
Specification (s)
The reactor shall not be operated unless the following conditions governing experiment reactivity exists a.
Non-secured experiments shall have reactivity worths less than 1 dollar.
b.
The reactivity worth of any single experiment shall be less than 2.5 dollars.
c.
The total reactivity worth of in-core experiments shall not exceed 3.00 dollars, including the potential reactivity which might result from malfunction, flooding, voiding, or removal and insertion of the experiments.
Basis
- a. The worth of single 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 cause 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 excessive power levels from being attained.
- c. The maximum worth of all experiments is limited so that removal of the total worth of all experiments will not exceed the fuel element temperaturo safety limit.
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3.4.2 Irradiations s
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Applicability,
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This specification applies to tryadialicas performed in the installed irradiation fa.cilitice contained in the. reactor pool as defined tin Sectioh 1.10.* Irradiations @re' a cubclass of experiments that fall within the specificationsq hereinafter stated in this section.
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Objective
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The' objective is to prIevent danage to the reactor, excessive release of radioactive. materials, or excessive personnel radiation expostare during the performance of an irradiation.
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specification (s)
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A device or material s a 1 liot be irradiated in an-
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irraciationeracility-under the classification of an irrgdiation'unless thi following conditions exist:
+
s.a.
The irradiation meets all the specifications ^of
.,.$ection 3.4 for an experiment, b.
The device ~6r material is encapsulated in a suitable container,
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c.
The reactivity worth of the device or material is.
0.25 dollars w h ss, otherwise it shall be m
classed as an,. experiment, d.
The expected radiation field produced by the device or sample upon removal from the reactor-is not more than 10 rem /hr at one foot after 10 min.,
otherwise'it shall be classed as an experime.nt, y.,
e.
The device or ma'terial does not remain in, the reactor for a period of over'15 days, otherwfse it
'shall be classed as an experiment.
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,<.u This specification is inte.n.deq to provide assurance that the special class of experiments called irradiations will be performed in a safe mann?r.l',"
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, y Technical Specifications 9/841 3.4.3:
Mat'erials i
Applicability These. specifications apply to experiments installed in the reactor and its-experimental facilities.
10bjective TheLobjective is to prevent the release of radioactive material.in.the. event of an experiment failure, either by ifailure.of the experiment or' subsequent ~ damage'to the
- reactor: components.
. specification (s)-
The. reactor shall not_'be-operated unless the following conditions governing experiment materials exists a..
Experiments containing materials corrosive to.
reactor components, compounds highly reactive with water,-potentially explosive materials, and liquid fissionable materials shall be doubly' encapsulated.
b.
Ifia capsule fails and releases material 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: corrective ~ action. The results of the inspection and any corrective Laction taken,shall be reviewed by the Director, or his-designated alternate, and determined to be satisfactory before operation of the. reactor is resumed.
c.
Each fueled experiment shall be controlled such that-the total-inventory of iodine isotopes 131 through 135 in the experiment is no greater than 1.5 curies and the maximum strontium inventory is no greater than 5. millicuries.
d.
Explosive materials, such as gunpowder, nitroglycerin, trinitrotoluene, or' pentaerythritol
'j tetranitrate in quantities greater than 25 i
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 j
and/or experimentally demonstrated to be less than i
the design pressure of the container.
1 i
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Page 26
97
+
- Technical'Sp3cifications 9/84 i
1 Experimentmaterials,hxceptfuelmaterials,which i
e.
- could off gas,_ sublime, volatilize, or produce aerosols under -(1) normal operating conditions of
,, the experiment.or reactor, (2) credible accident conditions in the, reactor, (3) possible accident
-conditions in the experiment shall be limited'in activity such that if 1004 of the gaseous activity
- . or radioactive aerosols produced escaped to the reactor room or the atmosphere, the airborne concentration of radioactivity, averaged over a l
- year would not exceed the occupational limits for l
maximum permissible 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 on high radiation ~ level, at least 10% of the gaseous activity or aerosols produced will escape.
(2) If the' effluent from'an experimental facility exhausts through a filter installation designed for greater than 994 efficiency for 0.25 micron
. particles, at least 104 of these vapors can escape. (3).For materials whose boiling point.is above 550C and-where vapors. formed by boiling this material can escape only through an undisturbed column of water above the core, at least 10% of these vapors can escape.
Basis
- a. Double encapsulation is required to lessen the experimental hazards of some types of materials.
1
- b. Operation of the reactor with the reactor fuel or structure damaged is prohibited to avoid release of fission products.
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- c. The 1.5-curie limitat on on iodine 131 through 135 i
assures that in the event of failure of a fueled experiment leading to total release of the iodine, the exposure dose =at the exclusion area boundary will be b
l d.-This specification is intended to prevent damage to-reactor components resulting from' failure of an experiment involving explosive materials.
- e. This specification is intended to reduce.the likelihood that airborne activities in excess of the maximum allowable limits will be released to the atmosphere outside the facility boundary.
- f. This specification provides guidance for the calculation of conditions in part (e).
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Technical Specifications 9/84 4.0-SURVEILLANCE' REQUIREMENTS 4.1 REACTIVITY LIMITS 4.1.1 Shutdown Margin j
Applicability This. specification applies to the measurement'of reactor shutdown margin.
Objective The' objective is to periodically determine the : ore shutdown reactivity avr.ilable for reactor shutdown.
~
. Specification (s)~
l Excess reactivity and shutdown margin shall be determined annually of after significant core or control rod changes.
Basis Annual. determination of shutdown margin and~ measurements l'
after reactor core or control rod changes are sufficient to monitor significant changes in the core shutdown margin.
l 4.1.2' Excess Reactivity Applicability This specification applies to the measurement of reactor j.
excess reactivity.
Objective l
i-I' The objective is to periodically determine the changes _in l
core excess reactivity available for power generation.
Specidication(s)
Excess reactivity shall be determined annually of after t
significant reactor core or control rod changes.
o Basis Annual determination of excess reactivity.and measurements after reactor core or control rod changes are sufficient to monitor significant changes in the core excess reactivity.
= - - -
Tschnical Specifications 9/84 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.
Specification (s) i The transient rod drive cylinder and assnciated air supply shall be inspected, cleaned, and lubricated annually, and a.
A reactor pulse shall be performed annually to compare fuel temperature, peak power and energy measurements with those of previous pulses.
b.
The reactor shall not be pulsed routinely until l
such comparative measurements have not been made.
Basis Annual inspections of the pulse rod drive system should be sufficient to detect and correct changes in the system that i
could impair operability.
The annual measurement of pulse parameters provides data to monitor changes in the reactor core transient characteristics.
j J
4.2 CONTROL AND SAFETY SYSTEM j
4.2.1 Operable Control Rods l.;
Applicability f
L This specification applies to the surveillance of the control rods.
Objective The objective is to assure the operability of the control rods by periodic measurement of the scram times and i
insertion rates.
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Page 29
J Technical' Specifications 9/84
~
' Specification (s).
Control rod wortha shall be determined annually of after significant. core or control rod changes,-and a.=
The scram time of a scrammable control rod shall be measured annually.
~b..
The reactivity' insertion rate of.a standard
- control rod shall be measured annually.
)
Basis Annual determination of control rod worths.or measureme'nts after significant core changes provide information about changes in reactor total reactivity and individual rod worths.
The specification' intervals for scram' time and'
. insertion rate assure operable performance of the rods.-
Deviations that are significant from acceptable standards o
L will be promptly corrected.
~4.2.2
. Reactor Control System
.Ap_711cability This specification Lpplies.to the tests of the logic of the
. reactor control system.
Objective
.The objective is to'apecify intervals for test, check or calibration of the minimum control system interlocks.
Specification (s)
The minimum safety interlocks shall be tested at semiannual-
' intervals.
Basis
' The periodic test of the interlock-logic at semiannual-intervals: provides adequate information that the function of the control: system interlocks'are functional.
Checks or calibrations of the control system logic are~not considered applicable functions.
- 4.2.3 Reactor Safety System Applicability
- This specification applies to tests of the function of the reactor safety system.
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Tcchnical Specificctions 9/84 Objective The objective is to specify intervals for test, check or calibration of the minimum safety system scrams.
Specification (s)
The minimum safety channels shall be calibrated annually and tested prior to each days operation or prior to each extended period of operation.
Basis The-periodic calibration at annual intervals provides adequate information that the setpoints of the safety system scrams are functional.
Tests of the safety system prior to each planned operation assure that each intended scram function is operable.
4.'2.4 Retctor 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 minimum instrument channels.
Specification (s)
The minimum instrument channels shall be calibrated annually.
Calibration of the power measuring channels shall be by the calorimetric method.
A check and test of each channel shall be made prior to each days operation or prior to each extended period of operation.
Basis Annual calibration of instrument channels are scheduled to allow adjustments for changes in reactor and instrumentation parameters.
Checks and tests are applied prior to system operation to verify function of the system.
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T3chnical Specifications 9/84 4.3 OPERATIONAL SUPPORT SYSTEMS 4.3.1 Reactor Coolant Conditions Applicability This specification applies to surveillance conditions for the reactor pool and coolant water systems.
Objective The objective is to maintain the reactor' coolant conditions within acceptable specifications.
Specification (s)
The following measurements shall monitor the reactor coolant conditions:
a.
The water conductivity sensor shall be checked annually.and pool water conductivity measured monthly.
b.
The water temperature sensor shall be checked-annually, tested monthly and monitored continuously during reactor operation.
c.
The water depth sensor shall be checked annually, tested monthly and monitored continuously during operation of the reactor.
d.
The pressure difference sensor shall be tested prior to each days operation or prior to each extended period of operation of the heat exchanger and monitored continuously during operation.
Basis 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 psrform its intended function.
4.3.2 Air Ventilation Conditions Applicability This specification applies to surveillance conditions for the air ventilation in the reactor area.
Page 32
Technical Specifications 9/84 Objective q
The objective issto demonstrate the function of confinement and release of air from the reactor bay.
- 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.
Calibration of argon-41 measurements shall be made annually and measurements or calculations performed monthly.
Basis
. Periodic evaluations of air confinement criteria are determined by examination, test, and calibration of the appropriate ventilation functions. the reactor. bay provide
_ control for radioactive releases by both routine and non routine operating. conditions.
4.3.3 Radiation Monitoring Conditions Applicability This specification applies to the surveillance conditions of the radiation monitoring' channels.
Objective The objective is to assure the radiation monitors are functional.
Specification (s)
The minimum radiation monitors specified to be operable.
during reactor operation shall be p.
Calibrated at semiannual intervals.
b.
Checked at-monthly intervals.
Basis Periodic calibrations and frequent checks are specified to maintain reliable performance of the radiation monitoring instruments.
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Technical Spscifications 9/84
'.4 LIMITATIONS ON EXPERIMENTS 4
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.
Specification (s)
The reactivity of an experiment shall be measured before an experiment.is considered functional.
Basis The measured reactivity or determination that the reactivity is not significant will provide data that configuration of the experiment or experiments is allowable.
4.4.2 Irradiations
'I Applicability This specification applies to the surveillance requirements for reactor irradiations.
Objective The objective is to provide a record of experiments inserted in the reactor as irradiations.
Specification (s)
Experiments classified as irradiations shall be identified and a log or other record maintained while the sample is in the reactor.
Basis Experiments performed as irradiations are monitored by data on-the sample-location, identification and other pertinent information.
F Page 34
Technical Spscifications 9/84 4.4.3 Materials 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.
Specification (s)
Any surveillance conditions or special requirements shall be specified as a part of the experiment approval.
Basis JL careful evaluation of all experiments is performed to classify-the experiment as an approved experiment.
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Technical Spacifications 9/84 5.0 DESIGN' FEATURES 5.1.
QUALITY CONTROL 5.1.1.-
. Safety Related' Systems Applicability-
.This specification. applies to.the requirements of any system frelated to reactorisafety..
Objective The objective is to assure the proper function of any system
~.related to reactor safety..
Specifications Any modifications or maintenance to.the reactor shield, the pooltoriits penetrations, the pool coolant system,-the core and its-assceiated support structure, the rod drive mechanisms,.the. reactor safety system.or'the air ventilation.
system shall-be made and' tested.in accordance with the specifications to which the systems were originally designed
- and fabricated.
Alternate specifications may be approved by.
the' reactor operations committee.-
A. system shall not be considered operable until after it is tested successfully.
. Basis 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 specificat, ions are assumed also meet'the presently accepted operating criteria.
Questions
.that may include an unreviewed safety question are. referred to the reactor operations committee.
- 5.1. 2 :
Fuel Element Inspections Applicability This specification applies to the inspection requirements for.the fuel elements.
Objective The' objective is to inspect the physical condition of the ~
fuel element cladding.
Page 36
T:chnical Sp;cifications 9/84 l
Specification (s)
The reactor shall not be operated with damaged fuel and a visual inspection of the fuel elements shall be made at biennial intervals.
A fuel element shall be considered damaged and must be removed from the core if:
a.
In measuring the transverse bend, the bend exceeds the original bend by 1/16 inch or, b.
In measuring the elongation, the length exceeds the original length by 1/10 inch or, c.
A clad defect exists as indicated by release of fission products.
Basis 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.
The limit of transverse bend has been shown to result in no difficulty in disassembling the the core.
Analysis of the removal of heat from touching fuel elements shows that there will be no hot spots resulting in damage to the fuel caused by this touching.
Experience with TRIGA reactors has shown that fuel element bowing that could result in touching has occurred without deleterious effects.
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.
5.1.3 Control Rod Inspections Applicability This specification applies to the inspection requirements for the control rods.
Objective The objective is to inspect the physical condition of the reactor. control rods.
Specification (s)
The reactor shall not be operated with damaged control rods and a visual inspection of the rods shall be made at biennial intervals.
Page 37
r e
Technical Specifications 9/84-Basis
'The frequency of. inspection for the control rods will
. provide periodic verification of the condition of the control rod linkages and the control rod clad.
.5.2 REACTOR CORE 5.2.1 Configuration Applicability This specification applies to the configuration of fuel elements, control rods, incore experiments and other reactor components.
Objective The_ objective is to_ assure that provisions are made to restrict the arrangement of fuel elements and experiments.so
,as to provide assurance that excessite power densities will not be produced.
Specification (s)
The reactor shall be an arrangement of core single grid positions occupied by fuel elements,. control rods, and graphite elements.
Single element positions may be occupied by voids, water or-experiment facilities.
'Special multielement positions or single element positions may be
. occupied by approved experiments.
Basis Standard TRIGA cores have been in use for years and their characteristics are well documented.
5.2.2 Standard Fuel Elements Applicability This specification applies to the fuel elements used in the reactor core.
Objective 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.
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F J.T Technical Specifications 9/84
~
Specification (s)
The standard TRIGA. fuel element at fabrication shall-have the_following' characteristics:
ca.
Uranium content: '8.5 Wt% uranium enriched to a nominal 19.74 Uranium-235;
~
b.
. Zirconium hydride. atom ratio: nominal 1.6 hydrogen to zirconium,_ZrHx; c.-
Cladding: 304 stainless steel, nominal.020 inches thick.
~
Basis The Design basis of_the standard.TRIGA core' demonstrates that 1.5 megawatt! steady or 36 megawatt-sec pulse operation
_ presents:a1 conservative limitation with. respect to safety Llimits'for the maximum temperature generated in the fuel.
The fuelLtemperatures are not expected to' exceed 550_C during any condition of normal operation.
5.2.3 Control Rods Applicability This specification applies to the control rods used in the reactor core.
Objective-The objective is to assure that the control rods are of such-a designeas to permit their use'with a high degree of reliability with respect to their physical and nuclear characteristics.
Specification (s)-
- The safety, shim,. regulating, and-transient control rods-shall have scram capability, and a.
Contain borated graphite, B4C powder, or boron and its compounds.in solid form as a-poison in aluminum or stainless steel cladding.
b.
1The safety, shim and regulating rods may1have a fuel follower.
c.
The. transient rod shall have an adjustable limit to allow a variation of' reactivity insertions and the' rod may contain an air follower.
Page 39-
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~
Technical Specifications 9/84 Bases TheLpoison requirements for the control rods are satisfied by using neutron absorbing borated graphite, B4C powder, or boron:and its compounds.
These materials must be contained Lin~.a suitable: clad material,~such as aluminum or stainless steel, to insure mechanical stability.during movement and to b
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 designed for a reactor pulse.
e.
5.3 FACILITY DESIGN
.5.3.1 Reactor Shield, Pool and Coolant Applicability.
This specification applies ~to the shield structure, the reactor pool and the cooling water system.
Objective The objective is to assure that adequate radiation shielding and cooling water are available for reactor operation.
Specification (s) n a.
The. basic reactor shield structure and pool coolant system shall be designed for dose rates of 1 mrem /hr at 1500 kW.
b.
Pool water level shall be protected by holes for siphon-breaks in coolant pipe lines.
.c.
The reactor core shall be cooled by natural convective water flow.
1 Bases a.-Calculations of the isodose curves for the reactor shield
^
- show that the design radiation levels should be less than'l mrem /hr at locaticns that are not above the pool or in the vicinity of beam ports.
.b. Siphon breaks set the subsequent' level for loss of coolant byLthe prevention of inadvertant pumping of water from the pool or accidental loss of water by siphon without the' associated return of coolant water.
Page 40 j
3
Technical Specifications 9/84 c.'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.
5.~3.2 Air 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 restrict the amount of release of radioactivity into the environment.
Specification (s)
The reactor bay shall be designed to restrict a.
leakage and will have a minimum enclosed air volume of 4120 cubic meters.
b.
The ventilation system will maintain a negative pressure compared to ambient air conditions,
' Ventilation system shall isolate reactor bay air c.
upon detection of a radiation limit signal.
Basis.
a.~ Calculations for' dilution of radioactivity associated.
with safety of reactor operation and release of effluents depends on the available air volume.
Nominal activity are calculated for the specified volume.
- b. Air leakage from the reactor bay during operation is restricted to the exhaust stack by control of the pressure
. difference relative to the external ambient pressure.
- c. The isolation dampers and fan motors for the reactor bay supply and exhaust air are controlled by a logic signal from a radiation sensor to provide automatic air isolation.
5.3.3 Radiation Monitoring Applicability This specification describes the function and essential components of the area radiation monitoring equipment and the system for continuously monitoring airborne radioactivity.
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N-4 Technical Specifications 9/84
. Object'ivez
.The objective-is to describe the. radiation monitoring 1
. equipment that is available to the' operator to assure safe-operation.of the reactor.
Specification (s)
Lair radiation monitoring equipment shall. consist.of fixed-and portable instruments.
Geiger tube type detectors are common buttother types of radiation. sensors may.be applied to specific measurements.- Air particulate radioactivity will monitor-material deposited.on. filters.
JBasis Radiation measurement is necessary,to provide information forTroutine operation or the occurrence of a design basis accident.
Multiple or different' radiation sensors are provided for duplication of radiat* 1 measurements and'for identification of radioactivity conditions.-
5.4 REACTOR FUEL ELEMENT STORAGE Applicability-4 This specification applies to.the storage.of reactor fuel at i
times when it is not in the reactor core.
Objective The objective -is.tx) assure'that fuel storage will not.become critical and.will not exceed design temperatures.
. 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 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.
Bases The limits imposed by these specifications are considered sufficient-to provide conservative. fuel storage and assure safe storage.
f Page 42
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-Tachnical Spscifications 9/84 6.0 ADMINISTRATIVE. CONTROLS
~6.1 ' ORGANIZATION 6.1.1-Structure TheLfacility shall be under the direct con' trol of the
~
cDirector or a licensed senior operator designated to be in direct control.
The management for operation of the
. facility shall-consist of the organizational structure established as follows:
^
Office, President University of Texas at Austin Vice President for Academic Affairs and Research Dean College of Engineering Radiation
-Chairman.
Reactor Safety Department 1of.
Operation Committee Mechanical Engineering-Committee Director Nuclear Engineering
. Teaching Laboratory Supervisor Reactor Operations 6.1.2-
. Responsibility The. Director shall be responsible to the Dean of the' College of-Engineering;and the' Chairman of-the Department of
' Mechanical Engineering for safe operation and maintenance of
- the reactor and its associated equipment.
The Director _or.
~
- his1 appointee shall review and approve all experiments and experimental procedures prior to their use in the reactor.
LIndividuals of the~ management organization shall be
' responsible for the. policies and operation of the facility,
>and shallibe responsible for safeguarding the public'and facility personnel from undue radiation exposures and for adhering to the operating license and technical specifications.
Page 43
n;..
Technical Specifications 9/84 i
.6.1.3 Staffing l
~
The minimum' staffing when the reactor.is not secured shall be:
- a.-.A certified operator in the control room.
- c. A' designated' Class A' operator readily available.
The available operator'should be within thirty minutes of the facility and reachable by telephone.
- b. A second person in the facility area that can perform: prescribed written instructions.
Unexpected absence for two hours shall require immediate action-to Lobtain an alternate person.
~ Events requiring the direction of a Class A 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 will require documented verbal concurrence if the cause is unknown.'
A list of reactor facility personnel by name and telephone s
number'shall be available to the operator in the control
+
room.
The list shall include:
- a. Management personnel.-
~b. Radiation safety personnel.
- c. Other operations personnel.
-6.1.4; Selection and Trainingoof Personnel A qualification program shall1be applied to personnel for
.the selection and training of certified operators.
6.2 REVIEW AND AUDIT 6.2.l' Composition and Qualifications A Reactor Operations Committee shall consist of at least three (3) members 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 an ex-officio member of the Reactor Committee.
The
. committee will perform the functions of review and audit or
-des'ignate a knowledgeable person for audit functions.
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Technical Specifications 9/84 6.2.2 Charter and-Rules Th'e : operations of, the-Reactor Committee shall be in accordance-with an established charter,-including provisions
--for:-
a.: Meeting frequency,
- b. Voting rules,
- c. Quorums,.
.d.
Use of subcommittees, and-e.-Review, approval, and dissemination of minutes.
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 experimenta that could affect reactivity or result in the release of r
radioactivity.
- d. Changes in-technical specifications or license.
- e. Violations of technical-specifications or license.
Lf. 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 examination of operating records, logs, or other documents.
An area will be audited by a person not directly responsible-for the records _and may include discussions with cognizant personne]
or. observation of operations. -The following items shall be audited:
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-l Technical Specifications 9/84 H
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^
- a. Conformance of facility operations with license and technica1' 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. certified operators at least once every other calendar year.
H
- d. The reactor. facility emergency plan and physical security-plan, and implementing procedures at least-once every.other year.
6L3 OPERATING PROCEDURES' i
Written operating proceddres shall be prepared reviewed and approved by the Director or a: designated alternate and the Reactor Operations Committee prior to initiation'of the following activities:
- a. Startup, operation, and_ shutdown of the reactor;
- d. Fuel loading, unloading and rovement-in the reactor;-
- c. Routine maintenance 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; I
- e. Administrative controls for operation,' maintenance,.
and the conduct of experiments or irradiations that could have an effect on reactor safety;
- f. Personnel radiation protection consistent with applicable regulations;
- g. Implementation.of required plans such as the emergency plan or physical security plan.
Substantive changes to the above procedure shall be made effective after approval of the Director a designated alternate and the Reactor Operations Committee.. Minor modifications to the original procedures which do not change the original' intent may be made by a Class A operator but the modifications must be; approved by the Director or a designated alternate.
Temporary deviations from the procedures may be made by a Class A operator in order to
. deal with special or unusual circumstances or conditions.
f:
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' Technical Specifications 9/84
- Such deviations shall be documented and-reported to the Director.or the designated alternate.
-6.4 EXPERIMENT REVIEW AND APPROVAL All: new experiments or classes of experiments shall be approved by.the Director a designated alternate and the
' Reactor Operations Committee.
i
- 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.
- c. Minor changes to an experiment that do not significantly alter the experiment may be made by a Class A operator.
6.5 REQUIRED ACTIONS 6.5.1 Action to be Taken in Case of a Safety Limit:
Violation s
-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 of the violation is prepared and authorization of the licensing agency.
- b. The safety limit violation shall be promptly reported to the Director or designated alternate.
- c. The safety limit violation shall be subsequently reported to the licensing agency.
i d..A safety limit violation report shall be prepared and submitted to the Reactor Operations Committee. 'The report shall describe; (1) Applicable circumstances leading to the violation including, when known the n
cause and contributing factors, (2) Effect of the violation on reactor facility components, systems, or structures and on the health and safety of the public, i
(3) Corrective actions taken to prevent recurrence.
u 6.5.2-Action to be Taken in the Event of an Occurrence that is Reportable.
In the event of a reportable occurrence, the following action shall be taken:
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-Technical Specifications 9/84
- a. Reactor conditions shall be returned to normal or
-the reactor shutdown.
If it is necessary to shut down the-reactorfto correct the occurrence, operations shall not be resumed unless authorized by-the Director er his designated alternate.
b.- Occurrence shall be reported to the Director.or his
-designated alternate and to licensing authorities as required.
- c. Occurrence shall be reviewed by the Reactor m
Operations Committee at the next regularly scheduled meeting.
6.6 REPORTS 6.6.1 Operating Reports Routine annual' reports covering the activities of the
' reactor facility during.the previous calendar year shall be submitted to licensing authorities 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 cf 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 owner-operator 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 present in the~ effluent.
If the estimated average release after dilution or diffusion is less than 25% of the concentration allowed or recommended, a statement to'this effect is sufficient.
- f. A summarized result of environmental surveys performed outside the facility.
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Tcchnical.Sp3cifications'9/84 g.-A summary of exposures received by facility.
personnel andcvisitors where such exposures are greater:
than 25% of that allowed or recommended.
6.6.2:
'Special' Reports
-l There shall be a report not later.than the following working day by telephone and. confirmed in writing by telegraph or similar conveyance.-to the licensing authorities-to be-followed by.a written report within 14 days that describes the circumstances of the event of any of the following:
Violation of fuel. element-temperatureisafety limit.
Release.of radioactivity above allowable limits.
~!
Other reportable occurrences Other events that will be considered reportable events are
' listed in this section.
A return to normal operation or curtailed operation until authorized by management-will occur.. Appropriate reports shall be submitted to license authorities.
(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 the' technical specifications unless prompt remedial action is taken.
- c. A reactor safety system component malfunction which renders or could render the reactor safety system incapabid of performing-its intended safety.
function unless the malfunction or condition is discovered during maintenance tests or periods-of reactor shutdowns.
- d. 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.
- e. An observed inadequacy in the implementation of administrative or procedural controls such that the Page 49
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Techhical Specifications 9/84 inadequacy causes or could.have caused the existence or
{
development of an unsafe condition with regard to reactor operations.
A report within.30 days-to the licensing authorities of:
- a. Permanent changes in the facility organization involving Director or Supervisor.
- b. Significant changes in the transient or accident analysis.as described in the Safety Analysis Report.
A report within 90 days after completion of startup testing of the reactor upon receipt of a new facility license or an amendment to the license-authorizing an increase in reactor
-power level describing the measured values of the operating conditions or characteristics of the reactor under the new conditions including:
- a. An evaluation of facility performance to date in comparison with design predictions and specifications; and
- b. A reassessment of the safety analysis submitted with the license application in light of measured operating characteristics when such~ measurements indicate that there may be substantial variance from prior analysis.
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:
(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) Radiation exposure for all personnel monitored.
(d) Updated drawings of the reactor facility.
6.~7.2 Records to be Retained for a Period of at Least Five Years or for the Life of the Component Involved whichever is shorter:
(a) Normal reactor facility operation (supporting documents such as checklists, log sheets, etc.
vana 50
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Technical Spscifications 9/84 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) Fuel inventories, receipts, and shipments.
(h)' Approved changes in operating procedures.
(i) Records of meeting and audit reports of the review and audit group.
6.7.3 Records to be Retained for at Least One Training Cycle:
Retraining and requalifications of certified operations personnel. -Records of the most recent complete cycle shall be maintained at all times the individual is employed.
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