ML20116D493
| ML20116D493 | |
| Person / Time | |
|---|---|
| Site: | University of Texas at Austin |
| Issue date: | 04/30/1985 |
| From: | TEXAS, UNIV. OF, AUSTIN, TX |
| To: | |
| Shared Package | |
| ML20116D479 | List: |
| References | |
| NUDOCS 8504290427 | |
| Download: ML20116D493 (52) | |
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Technical Specificationo 4/85 Table of Contents 5
1.0 DEFINITIONS 5 1.1 Certified Operators Class A Reactor Operator 5 1.1.1 Class B Reactor Operator 5 1.1.3 5
1.2 Channel Channel Test 5 1.2.1 1.2.2 Channel Check 5 1.2.3 Channel Calibration 5 6
1.3 confinement 6
1.4 Experiment 1.4.1 Experiment, Moveable 6 Experiment, Secured 6 1.4.2 Experimental Facilities 6 1.4.3 6
1.5 Fuel Element. Standard 6 1.6 Fuel Element. Instrumented 7 1.7 Mode, Steady State 7
1.8 Mode, Pulse 7
1.9 operable 7
1.10 Operating 7
1.11 Protective Action 1.11.1 Instrument Channel Level 7 Instrument Subsystem Level 7 1.11.2 i
Instrument System Level 7 1.11.3 1.11.4 Reactor Safety System Level 8 8
1.12 Reactivity, Excess 8
1.13 Reactivity Limit 8
1.14 Reactor Core. Standard 8 1.15 Reactor Core, Operational 8 1.16 Reactor Operating 8
1.17 Reactor Safety System L 8 1.18 Reactor Secured 9 1.19 Reactor Shutdown ~ 9' 1.20 Reference Core Condition 9 t
1.21 Research Reactor 10
! 1.22 Control Rod 10 1.22.1 Rod, Regulating Rod, Safety 10 1.22.2 Rod, Shim 10 i 1.22.3 Rod Transient 10 1.22.4 Rod, Standard 10 -
1.22.5 10 1.23 Safety Limit r 310' 1.24 Scram Time ill 1.25 Shutdown Margin 11 1.26 Shutdown, Unscheduled 11 1.27 Surveillance Intervals 12 1.28 Surveillance Activities 12 1.29 Value. Measured 12 1.30 Value. True l
Page 2
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Technical Specificationo 4/85 13 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 13 2.1 SAFETY LIMIT 14 2.2 LIMITING SAFETY SYSTEM SETTINGS 14 -
2.2.1 Fuel Element Temperature Operating Power 15 2.2.2 5 16 3.0 LIMITING CONDITIONS FOR OPERATION 16 3.1 REACTIY7.TY LIMITSExcess Reactivity 16 3.1.1 ,
16 3.1.2 Shutdown Margin ,
Transient Insertions 17.
3.1.3 18 321.4 Fuel Elements 18 CONTROL AND SAFETY SYSTEM 3'. 2' 19' -
3 3.2.1 s Control Assemblies 19 s
Reactor. Control System , . g.:., "
3.2.2 13,gjp , 23 -
t .; Reactor Safety System L 3.2.3 21,gt ,,
'3.2.4 Reactor Instrument System 22 'C/
3.3 OPERATIONAL SUPPORT SYSTEMS 23 Wi J' 3.3.1 Water Coolant Systems 24 ~;'4" '
3.3.2 Air Confinement Systems Radiation Monitoring Systems 25-3.3.3 26 3.4 LIMITATIONS ON EXPERIMENTS 26 3.4.1 Reactivity 27 3.4.2 Irradiations 28 3.4.3 Materials 4.0 SURVEILLANCE ELyUIREMENTS
.30 30 4.1 RElCTIVITY LIMITS 30 4.1.1 Excess Reactivity ~
Shutdown Margin 30' 4.1.2 31 4.1.3 Transient Insertions 31 4.1.4 Fuel Elements , 3 2;; , 'ls 4.2 CONTROL AND SAFETY SYSTEM 32; m_
4.2.1 Operable Control Rods 33
Reactor-Control Syatem 4. p; 4.2.2 P
4.2.3 ' Reactor Safety System 33.g.fi(^/O, L 4. 4.2.4 Reactor-Instrument System ,
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'; i 4.3 OYERATIONAL SUPPORT SYSTEMS Water Coolant Systems 34j'$bb 3461 34 M d -
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4.3.1 i$i
' Air Confinement Systems 4.3.2 Radiation Monitoring Systems 351'.;Jficftti 36]Qgi.
4.3.3 g.g 4.4 LIMITATIONS ON EXPERIMENTS 36ggg;gy^
3 6 /, - 931 4.4.1 Reactivity 4.4.2 Irradiations 374 h'?*
l 3 7.y :.p w(s' eV 4.4.3 Materials _9(nt * ,
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> Page 3 e . _ . _
Technical Specifications 4/85 36 5.0 DESICN FEATURES 36 5.1 SITE AND FACILITY DESCRIPTION 36 5.1.1 Location 36 5.1.2 Confinement 37 5.1.3 Safety Related Systems 38 5.2 REACTOR COOLANT SYSTEM 38 5.3 REACTOR CORE AND FUEL 38 .
5.2.1 Fuel Elements 39 5.2.2 Control Rods 38 5.2.3 Configuration 42-5.4 REACTOR FUEL ELEMENT STORAGE 43 6.0 ADMINISTRATIVE 43 6.1 ORGANIZATION 43 6.1.1 Structure 43 Responsibility 6.1.2 44 6.1.3 Staffing 6.1.4 Selection and Training 44 of Personnel 44 6.2 REVIEW AND AUDIT 6.2.1 Composition and Qualifications 4445 6.2.2 Charter and Rules 45 6.2.3 Review Yunction 45 6.2.4 Audit Function 46 6.3 OPERATING PROCEDURES 47 6.4 EXPERIMENT REVIEW AND APPROVAL 47 6.5 REQUIRED 6.5.1 ACTIONSAction to be Taken 47 in Case of Safety Limit violation 6.5.2 Action to be Taken in the Event of a Reportable 47 Occurrence 48 6.6 REPORTS 48 6.6.1 Operating Reports 49 6.6.2 Special Reports 50 6.7 RECORDS ;
6.7.1 Records to be Retained for -
a Period of at Least Five n.
Tears or the Life of the 50 ,
Component 6.7.2 Records to be Retained for 51 at Least One Training Cycle ,
6.7.3 Records to be Retained for 51 the Lifetime of the Facility f.
4 Page 4
Technical Specifications 4/85 1.0 DEFINITIONS 1.1 Certified Operators An individual authorized by the chartering or licensing organization to carry out the responsibilities associated with the position requiring the a
certification.
1.1.1 Class A Reactor Operator the activ it ie s An individual who is certified to direct Such an individual is of Class B reactor operators.is commonly referred to as also a reactor operator and a Senior Eeactor Operator.
4 1.1.2 Class B Reactor Operator is certified to manipulate the
- An individual who Such an individual is commonly
' controls of a reactor.
a Reactor Operator.
referred to as 1.2 Instrumentation channel combination of sensor, l it. . ,
A channel is the device which are connected for amplifier, and of output measuring the value of a parameter.
the purpose 1.2.1 Channel Test 4
introduction of a signal into the Channel test is the it is operable.
channel for verification that 1.2.2 Channel check Channel check is a qualitative verification of l acceptable performance by observation of channe shall behavior. This verificationchannel where possible, with other include comparison of thesystems measuring the same independent channels or variable.
1.2.3 Channel Calibration is an adjustment of the channel Channel calibration corresponds with acceptable such that its output of the parameter which the accuracy to known values i
Calibration shall encompass actuation, the alarm, channel measures. including equipment entire channel, channel test.
or trip and shall be deemed to include a Page 5
4 Technical Specificationo 4/85 l 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. ,
1.4 Experiment
- f n '. '
component, or target (excluding ice's Any operation, such as detectors.. foils..etc.), which is~desiga.2fto-investigate non-routine reactor characteristics'o'ryk-which is intended for irradiation within the pool??fon-or in a beamport or irradiation facility'and which-is ~
not rigidly secured to a core or shield st'ructure'(so as to be part of their design. 'jy.
1.4.1 Experiment, Moveable ,
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A moveable experiment is one where it is'intendedEthat-the entire experiment may be moved in or near the core
' or into and out of the reactor while the reactor is operating.
1.4.2 Experiment, Secured
~
A secured experiment is any experiment, experiment y facility, or component of an experiment that is held l.. in I
a stationary position relative to the reactorbeby fx . ' .
mechanical means. The restraining force must ..y .
substantially greater than those to which the -45.W :1,.
experiment might be subjected by hydraulic, pneumatic, buoyant, or other, forces which are normal to the;,< ,, ,
operating environment.of the experiment, or by.for,ces-which can arise as a result of credible condition's'.p'<.:p.gtM.n, .n Experimental Facilities .yyl[~[
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1.4.3
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Experimental facilities shall mean rotary specimenAlgy
rack, pneumatic transfer tube, central thimble, @ .,) j beantubes and irradiation facilitiestin the coreNo'r?.in the pool and will include the cobalt-60 facility.f,-d
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Fuel Element. Standard . g,pj . f ,
'1.5 Ok'b. -
A fuel element is a single TRIGA element of'standardt type. Fuel is U-ZrH clad in stainless steel clads.5, Zirconium to hydrogen ratio is nominal 1.6. .if 9 ,
1.6 Fuel Element. Instrumented An. instrumented fuel element la a specialThe fuelelement element fabricated for temperature measurement.
shall have at least one thermocouple embedded in the fuel near the axial and radial midpoints.
Page'6,
Technical Spocificationo 4/85 1.7 Mod 7, Steady State Steady state mode operation shall mean operation of'.'the reacter with the mode selector switch in the steady-state position. ,
1.8 Mode. Pulse . 1s; Pulse mode operation shall mean any operation o'ffche reactor with the mode selector switch in the p'u1(e( position.
1.9 operable Operable means a component or system is capable of. ,,d(.1 performing its intended function. .
1.10 Operating '
Operating means a component or system is performingc its' intended function.
1.11 Protective Action i
Protective action is the initiation of a signal cr the the reactor safety: system operation in response of equipment withinto a variable or condition of the reactor {'
I facility having reached a specified limit. . , . .
-at;.s 1.11.1 Instrument Channel Level ,
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At the protective instrument channel level, protective ~
action is the generation and transmission of a: trIi331 signal indicating that a reactor variable has rEAc.hEdi,.
the specified limit. ]g::
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1.11.2 Instrument Subsystem Level- .:rc.g;ps;Lf;>
%.R'Qjd ,g' At the protective instrument subsystem level, l-J protective action is the generation and transmiss'i'onlof specified limit hAs p%3 H' ,
trip signal indicating that a I a been reached. m lf.'/::$.e - ' f:
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1.11.3 Instrument System Level ,
17 At the protective instrument system level,prote'etiie[j,(
action is the generation and transmission of the g hi fp9{L l command signal for the safety shutdown equipment':to;g,y u operate.
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Technical Specifications 4/85 1.11.4 Reactor Safety System Level At the reactor safety system level, protective 1 action is the operation of sufficient equipment to imme'diately i shut down the reactor.
,L ,
1.12 Reactivity, Excess ,
- f Excess reactivity is that amount of reactivity that. )
would exist if all the control rods were moved.co'/the.
maximum reactive condition from the point where.the.
reactor is exactlyicritical.
,l 1.'13 Reactivity Limits c.v.w . .. . L th i The reactivity limits are those limits imposed on)jj;e-:.y$F ' '
reactor core excess reactivity. Quantities are) c; referenced to a reference core condition. q+f,5g ,
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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.
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1.15 Reactor Core, Operational . :.
I An operational core is a standard core for which ther-l core parameters of excess reactivity, shutdown margin, fuel temperature, power calibration, and reactivity.fA., cc j worths of control rods and experiments have been set forthlin%the determined to satisfy the requirements
/ Technical Specifications. , .4b 3 . :p. y;-. !;j. ,
id 1.16 Reactor Operating . ;g,@ f. .? d:', .
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The reactor is operating whenever it is not secur'edi;or0 ($$hy3I .
shutdown.
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1.17 Reactor Safety Systems .gj ,7 ,
lNb , a Reactor safety systema are those systems, includin'g!.pg. ,
their associated input channels, which are designedTtok initiate automatic reactor protection or to providek$h[
inf ormation f or initiation of manual protective . ia c't' .sg, ion,.
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1.18 Reactor Secured The reactor is secured wheni l
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Technical Specifications 4/85 1.18.1 fissile material or moderator It contains the insufficient control rods or adjacent present in toreactor, attain criticality under optimum or experiments, conditions of moderation and reflection, available 1.18.2 absorbing control
- a. The minimum number of neutron safety devices rods are fully inserted or otheras required by technical are in shutdown position, specifications, and in the off position and b.
The console key switch is the key is removed from the lock, and fuel, core in progress No work is installed control involving coreor control rod
- c. rods, structure, they are physically decoupled from drives unless the control rods, and reactor are being No experiments in or near the on movement, a moved or serviced that have,the maximum allowed for d.
is reactivity worth exceedingor one dollar which ever a single experiment smaller.
1.19 Reactor Shutdown The reactor is shutdown if it is suberitical by at core condition and least one dollar in the reference is accounted for.
the reactivity of all experiments 1.20 Reference Core Condition is at ambient i The condition of the core when itreactiviity worth of xenon f temperature (cold) and the i is negligible (<.30 dollars).
1.21 Research Reactor a device designed to is defined as for A research reactorself-sustaining neutron chain reaction support a educational, training, or research, development, and which may have provisions experimental purposes, for the production of radioisotopes.
i
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Technical Specifications 4/85 4
4 4
1.22 Rod, Control 4
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 2
drive unit allowing it to perform a safety function when the coupling is disengaged.
1.22.1 Regulating' Rod I A regulating rod is a low worth control rod used level and may primarily to maintain an intended power j
be varied manually or by a servo-controller. The regulating rod may have scram capability.
1.22.2 Safety Rod A safety rod is a control rod having an electric motor drive and scram capabilities.
1.22.3 Shim Rod A shim rod is a control rod having an electric motor drive and scram capabilities.
1.22.4 Transient Rod A transient rod is a control rod that is capableaofpower providing rapid reactivity insertion to produce pulse.
1.22.5 Standard Rod The safety, shin and regulating rods are standard control rods.
1.23 Safety Limits safety limits are limits on important process variables reasonably which are found to be necessary to protect the integrity of the principal barriers which guard The against the uncontrolled release of radioactivity.
principal barrier is the fuel element cladding.
1.24 Scram Time Scram time is the elapsed time between reaching a limiting safety system set point and a specified control rod movement.
Page 10
Technical Specifications 4/85 1.25 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 safety systems starting from any permissible operating condition although the most reactive rod is in its most reactive position, and that the reactor will remain su.beritical without further operator action.
1.26 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 response to conditions which could adversely affect safe operation, not including shutdowns which occur during testing or check-out operations.
1.27 Surveillance Intervals Maximum intervals are to provide operations Established 1
flexibility and not to reduce. frequency.
frequencies shall be maintained over the long term.
Allowable surveillance intervals shall not exceed the following:
1.27.1 5 years (interval not to exceed 6 years) 1.27.2 2 years (interval not to exceed 2-1/2 years) 1.27.3 Annual (interval not to exceed 15 months) 1.27.4 Semiannual i (interval not to exceed 7-1/2 months) (
1.27.5 Quarterly (interval not to exceed 4 months) 1.27.6 Monthly (interval not to exceed 6 weeks) 1.27.7 Weekly (interval not to exceed 10 days) 1.27.8 Daily (must be done during the calendar day)
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Technical Specifications 4/85 1.28 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 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 generally specified specified as monthly as to quarterly. Calibrations are annually to biennially.
1.29 value. Measured The measured value is the value of a parameter as it appears on the output of a channel.
1.30 Value, True The true value is the actual value of a parameter.
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Technical Specifications 4/85 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 Safety Limit Applicability i
This'specificacion applies tothetemperatureofthe"kesctor PY fuel in a standard TRIGA' fuel element. %,1?
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Objective. 4 ., ,
The objective is to define the maximum temperature th'atl[can be permitted with confidence that no damage-toithe fueijg*:', '?'-
element cladding will result. - .2; ,
49323;y LSpecification(s) . : MQ@
The1 maximum. temperature in a standard TRIGA 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.
i Basis The important parameter for a TRIGA reactor is the fuel '
element temperature. This parameter is well suitedxasfla: .
single specification since it can be measured directly.- A
~
loss in the integrity of the fuel element cladding could.
.arise from a build-up of excessive pressure between the.'
4 fuel-moderator and the cladding if the fuel temperature'
-exceeds the safety limit. 'The pressure is caused bysthe:
presence of air, fission product gases, and hydrogen from, ~
the dissociation of the hydrogen and sitconium i n t h e;.,] .,g g fuel-moderstor. Hydrogen' pressure is the most significant.b component. The-magnitude'of-this pressure?is determinedi.by' i the- fuel-moderator- temperature and the ratio of hydrogen:to
. %.0 E zirconium in the; alloy. - ., at . n .c:.
- 4
.. onM4 The. safety limit for.the standard TRIGA-fuel is base
'Theresultsiy$.hf/h k.v.o m #
calculations sad experimental evidence.
(' indicate that1the stress >in the. cladding due to hydrogen; Mi pressure from-the dissociation ~of airconium hydride 10iE1? P, remain below.the ultimate stress provided that thef.)$f!@d 1.
temperature of the fuel does not' exceed 1150_C and-the'nf cladding does not exceed 500_C. For conditions that7mlght cause thecladtemperaturestoexceed500_Cthesafi,tjpf.init "i "Ar
- of the fuel should be set at 950_C.
4 J
Page:13 ,
F Technical Specificationo 4/85 2.2 Limitine Safety System Settines 2.2.1 Fuel Temperature i
Applicability This' specification applies to the protective action'forithe . h?J reactor' fuel element temperature.
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c.gzy Objective .s mQ% :.
The objective is to prevent the fuel element temperaturel, safety limit from being. reached. } .
Specification (s) . li.J The limiting-safety system setting shall be 550_C.;asTQ;g measured in an instrumented fuel element. The. instrumented element shall be located in the 5 ring of the reactor (core configuration.
Basis The limiting safety system setting is a temperature wh'ich, if exceeded, shall cause a reactor scram to be initiated. A setting preventing the safety limit from being exceeded. -
l of 550_C provides a safety margin at the point of measurement of at least 400_C for standardA TRIGA part offuel the-elements in any condition of operation.
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 temperaturesswi'll
- be only: s. f ew : degrees: since the thermocouple junctioniisyf
~
1:
l' near:;the center and'the mid plane of the fuel element
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pulse operation'of the reactor, thesame;11mitlng#
.ForLthe:
! safety systenVsetting will apply. .However, the.tempirature
' channel will have no effect en limiting the peak po.w{[s.g generated because of its relatively long time constantMY, '"$4@ <
(seconds) as; compared with the width of the pulsetemperatuRe{,Erip however, the (milliseconds).icIn this mode, will act to limit the Eenergy release af ter the puls'eyif3the transient rod should not reinsert and the fuel tempera,ture il;,f continues to increase. .g , A Page 14
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Technical Specifications 4/85 2.2.2 Operating Power 4 Applicability This specification applies to the protective action for power generated in the reactor during continuous operation.
1 Objective The objective is to prevent the fuel element temperature safety limit from being reached.
Specification (s)
The maximum operating power level for the continuous operation of the reactor shall be 1100 kilowatts.
Basis 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.
Page 15
Technical Specificationo 4/85 3.0 LIMITING CONDITIONS FOR OPERATION 3.1 Reactor Core Parameters 3.1.1 Excess Reactivity Applicability ..
This specification applies to the reactivity conditionfof the reactor co're in terms of the available excess.aboveithe
- . ss' cold xenon free, critical ~ condition. .
Objective The objective is to prevent the fuel element temperatur'e-safety limit from being. reached by limiting the potential reactivity available in the reactor f or any condition of ,
operation.
Specification (s)
Maximum excess reactivity shall be 4.9% _k/k.
Basis Maximum excess core reactivity is sufficient to provide the core rated power, xenon compensation and reactivity fpre that~no shutdown. Analysis of the reactor core demonstrates single component represents sufficient potential reactivity to reach the fuel element temperature safety limit during(. 'i F. , e any condition of operation.
3.1.2 Shutdown Margin ., 3 s, J.M
- ify,, 9, Applicability
- GW. -.
i This specification applies to the reactivity margin b'yjwhich
-the reactor core will be' considered shutdown when thes. AJ reactor is n'ot operating.
- w. -
Objective The objective is to assure that the reactor lcan be shut'down safely by a margin that is sufficient to compensate'for th'e failure of a control rod or the movement of an experiment.
Page 16
Technical Specificationo 4/85 I
i Specification (s) j The reactor shall not be operated unless the shutdown margin j provided by control rods is greater than 0.2% _k/k with:
- a. the reactor in the reference core condition, 4
^
- b. the most reactive control rod fully withdrawn,
- c. the highest worth moveable experiment in its most i
e reactive state.
- Basis j
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 i reactivity state.
I 3.1.3 Transient Insertions I Applicability This specification applies to the total potential worth of l
the transient rod and the allowable reactivity insertion for reactor pulse operation.
j 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.
l l
Specification (s) l Total worth of transient rod shall be limited to 2.8% _k/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% _k/k, and shall be limited by a mechanical block on the pulse rod.
Page 17
1 Technical Specifications 4/85 Basis Experiments with pulsed operation of TRIGA reactors by the manufacturer indicate that insertion up to 3.5% _k/k have not exceeded the fuel temperature safety limit.
Calculations demonstrate that the total insertion of all the transient rod worth will not exceed the fuel temperature safety limit. Thus for a 2.2% _k/k pulse a substantial safety margin would exist between the fuel element safety limit and th'e rise of peak fuel temperature above an assumed ambient pool temperature of 50_c.
3.1.4 Fuel Elements Applicability This specification applies to the measurement parameters for the fuel elements.
Objective The objective is to verify the physical condition of the
' fuel element cladding.
Specification (s)
The reactor shall not be operated with damaged fuel. A. fuel t
element shall be considered damaged and must be removed from f the core if:
I
- a. In measuring the elongation, the length exceeds the original length by 2.54 mm (1/10 inch) or,
- b. In measuring the transverse bend, the bend exceeds the original bend by 1.5875 mm (1/16 inch) or, indicated by release of
- c. A clad defect exists as fission products.
Basis 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 hac been 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 no hot spots resulting in damage to the fuel caused by this touching. Experience with TRICA reactors has shown that fuel element bowing that could result in touching has occurred without deleterious effects.
Page 18
l l
Technical Specifications 4/85 3.2 Reactor Control and Safety System i 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'.
ivity
-the scram times for scrammable control rods and react insertion rates for standard control rods.
Specification (s) ,
i l The reactor shall not be operated unless the control rods are operable, and
- n. Control rods shall not be operable if damage is 4
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 insertion rate of a standard control rod shall be less than 0.2% _k/k per
' second.
Basis-
Thel apparent ? condition of the control . rod assemblies;.-will provide assurance'that-the rods will continue to perform, reliably and as-designed. The specification for rod,(sc. ram time assures thet the reactorThe i 2 will sh'ut;down promptlyswhen.an.
specification for rod.# ,
scram signal is initiated.
reactivity insertion rates assures that the reactor will Analysis;~h'as start.up contro11 ably when rods are withdrawn.for'the range of transient indicated that 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.
Page 19
m 3
Technical Specificationo 4/85 l
Objective The objective is to determine the minimum control system interlocks operable for operation of the reactor.
.I Specification (s)
The reactor shall not be operable unless the minimum' safety interlocks are operable. The following control system
' safety int'erlocks shall be operable: .
Interlocks Number Effective Mode Function Steady-State-Pulse
. Rod Drive Control Onerable I
prevent for X
- s. All Control Rods 1 less than 2
' Startup Withdrawal counts per sec prevent for X
- b. All Control Rods 1 two or more rods Simultane.ous Withdrawal prevent I l
- c. Transient Rod 1 unless all Withdrawal rods are down prevent any :I
, r:e
, Basis- _
.:1;
~
Interlockscare specified to prevent function of the control-
- rod drives unless certain specific conditions, exist..,QThe. e interlock.to. prevent startup of the reactor at to powerd1.vels approximately less 'thgnwatts,
- 2 neutron cys, which assures corresponds that sufficient neutrons are: j}/ #
4 x 10 Simu ltaneous > -
available for contr.olled reactor startup.
control rod is preventedjbytan withdrawal of more than one interlock to limit the maximum positive reactivity >insertior.
rate available for steady state operation. Several' y'. ,
interlocks applied to the transient rod determine'therproper against ,
rod operation during pulse operationThe and protect interlock to prevent inadvertent pulse operation.
withdrawal of the motor driven rods in the pulse 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.
f Page 20
I Technical Specifications 4/85 3.2.3 Reactor Safety System Applicability These specifications apply to operation of the reactor safety system.
i Objective The objective is to determine the minimum safety system i l
scrass operable for the. operation of the reactor. l l
' Specification (s) l 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 Steady-State Pulse l
l Scram on X X I a. Manual Scram 1 Console Button operator demand I
1 Scram at 550_C X X
- b. Fuel Temperature
- d. Peak Pulse Power 1 of full scale Scram at 110% X
- e. Percent Power Level 1 of full scale Scram on X X High Voltage 1 f.
loss of Scram on X X I
- g. Magnet Current 1 l loss of l
Fasis Manual operation of the reactor safety system is considered part of the protective action of the reactor safety system.
Signals for control rod insertion and reactor shutdown provide scrans on excessive fuel temperature and power level that is short of the fuel element temperature safety limit.
Operation without adequate control and safety system power supplies is prevented by scrams on neutron detector high voltage and control rod magnet current.
P 21
Technical Specifications 4/85 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 Ooerable Steady-State Pulse Measurine Channel K K Fuel Temperature 1 a.
I
- b. Linear Power Level 1 K
- c. Peak Pulse Power i K
- d. Percent Power Level 1 Basis The minimum measuring channels are sufficient to Signals provi'defrom signals for automatic safety system operation.
the measuring system provide information to the control and l safety system for a protective action. Measurements of the l same or different parameters provide redundancy.
Page 22
\
Technical Specifications 4/85 3.3 Ooerationsi Suonort Systemt Water Coolant Systems 3.3.1 Applicability ditions for This specification applies to the operating s con the reactor poo.1 and coolant water system . I
-Objective are l
The. objective is to assure that'. adequate conditionsshielding onents, fof maintained to provide leakage from the-protection against corrosion of the reactor comp ]
cooling of the reactor fuel,'and prevent %
primary coolant.' 0 Specification (s) hut down Corrective if the following action reactorshall be water coolant taken or the are conditions reactor s observed: d 48_C, or i
the bulk pool water temperature excee s . j
- a. asured or i
- b. the water depth is less than 6.5 meters mefrom 5.0 _mbo/cm th, or
- c. the water conductivity is greater thanaveraged hanger :
the pressure difference during heat exc ed ' T.
d.
operation is less than 7 kPa (1 psig) measurpressure and the c
j exchanger.
between the. chilled water outletpressure to the heat pool water inlet t, Basis s l water coolant j The specifications for conditions of the pooare to control'the radiation-
~
iated with the system provide controls thatexposures and radioactive rele inventory.
reactor fission product constraint assures that ll anticipated The bulk water temperature s.
sufficient core cooling exists under a i of the operating conditions and protects the resion. n
/
water purification system from deteriorat l
sufficient to bove the l
l
- b. A pool water so that depth of 6.5 meters isprovide mo l
reactor pool arecorereasonable at levels.
- - - - - - - - - _ _ _ _ _ _ _ _ . _ _ _ _ _ *""ee., , -
Technical Specifications 4/85 water conductivity Average measurements of pool coolant of 5.0 _mho/cm assure that water purity is maintained c.
to control the effects of corrosion and activation of coolant water impurities.
- d. A pressure difference at the heat exchanger chilled water outlet and the pool water inlet of 7 kPa will be sufficient to prevent loss of' pool water from the primary reactor coolant. system to the secondary chilled water system in the event of a leak in the heat exchanger.
3.3.2 Air Confinement Systems Applicability This specification applies to the air ventilation conditions in the reactor area during reactor operation.
Objective The objective is to control the release of air in the reactor area or experimental facilities.
Specification (s) l The reactor chall not be operated'unless minimum The followingconditions minimum l
for air confinement are functional.
l conditions shall exist:
- a. Equipment shall be operable to isolate the reactor area by closure of all access doors and closure of ventilation supply and exhaust dampers.
- b. A radioactivity level signal shall initiate confinement of the reactor ares ventilation and an emergency air purge shall be operable with high efficiency particulate adsorption filters.
- c. The annual average release ofargon-g1 fro"She facility shall be limited to 2 x 10 _Ci/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 24
Tec'anical Specificationo 4/85 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 i
conditions in the area of the reactor for indication of a radioactive release.
Specification (s)
The reactor shall not be operated unless minimum conditions The following for radiation measurement are functional.
minimum conditions'shall exist:
- a. A continuous air monitor (particulate) shall be j operable with readout and audi.ble alarm.
1
- 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 radiation monitor may be substituted for a monitor that is not operable for periods not to exceed 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
Basis The radiation monitors provide information to operating personnel of impending o- 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.
\
i Page 25 t
Technical Specificaticuo 4/85 3.4 Limitations on Exneriments 3.4.1 Reactivity Applicability
]
1 This specification applies to the reactivity associated with experiments-located in the reactor core.-
Objective The objective is control the amount of reactivity associated l
with experiments to values that:will not endanger the reactor safety limit. ,
f
' specification (s)
The reactor shall not be operated unless the~following conditions governing experiment reactivity exist:
I
- a. A moveable experiment shall have a reactivity worth less than I 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 f shall not exceed 3.00 dollars, includi.ng the i
potential reactivity which might result from malfunction, flooding, voiding, or removal and i
insertion of the experiments.
L Basis s
- s. The worth of single moveable experiment is. limited so t' hat sudden removal movement of the experiment:will not cause. prompt; criticality. Worthoof 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 experiment's is limited so that removal of the total worth of all experiments will l
not exceed the fuel element temperature safety limit.
l Page 26
i Technical Specifications 4/85 J
' 3.4.2 Irradiations Applicability This specification applies to irradiations performed in the installed irradiation facilities contained in the reactor pool as defined in Section 1.10. Irradiations are a subclass of experiments that fall within the specifications hereinafter stated in this section.
Objective .
The objective is to prevent damage to the reactor, excessive release of radioactive materials, or excessive personnel j
radiation exposure during the performance of an irradiation.
i Specification (s)
! A device orfacility irradiation material shall the under not classification be irradiated inofan an irradiation unless the following conditions exist:
- a. The irradiation meets all the specifications of Section 3.4 for an experiment, i
t
- b. The device or material is encapsulated in a suitable container, 1
- c. The reactivity worth of the device or material is 0.25 dollars or less, otherwise it shall be classed as an experiment,
- d. The expected radiation field produced by the device or sample upon removal from the reactor is not more than 1 res/hr at one meter after 10 min.,
otherwise it shall be classed as an experiment,
- e. The device or material does not remain in the reactor for a period of over 15 days, otherwise it shall be classed as an experiment.
Basis that the This specification is intended to provide assurance special class of experiments called irradiations will be performed in a safe manner. ,
i j
Page 27 2
Technical Specifications 4/65 3.4.3 Materials Applicability These specifications apply to experiments installed in the l
reactor and its experimental facilities.
i objective _
The objective is to prevent the release of radioactive material in the event of an experiment failure, either by failure 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 exist:
r
- a. Experiments containing materials corrosive to reactor components, compounds highly reactive with and' liquid water, potentially explosive materials, fissionable materials shall be doubly encapsulated.
- b. .If a capsule fails and releases material which could damage the reactor removal fuel or structure and physical by corrosion or other means, inspection shall be performed to determine the consequences and need for corrective action. The results of the inspection and any corrective action taken shall be reviewed by the Director, or his designated alternate, and determined to beis satisfactory before operation of the reactor 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 millieuries.
- d. Explosive materials, such as gunpowder, nitroglycerin, trinitrotoluene, or pentaerythritol tetranitrate in quantities greater than 25 milligrams shall not be irradiated in the reactorin or experimental facilities. Explosive materials quantitles 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.
i, Page 28
J Technical Specifications 4/85
- e. Experiment materials, except fuel materials, which could off-gas, sublime, volatilize, or produce aerosols under (1) normal operating conditions of the experiment or reactor, (2) credible accident i
conditions in the reactor, (3) possible accident conditions in the experiment shall be limited in activity such that if 100% of the gaseous activity
' or radioactive aerosols produced escaped to the reactor room or the atmosphere, the airborne concentration of radioactivity averaged over a year would not exceed the occupational limits for
' maximum permissible concentration.
- f. In calculations pursuant to e. above, the f ollowing assumpt ions 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 ser'osols produced will escape.
(2) If the effluent from an experimental facility exhausts through a filter installation designed l
for greater than 99% efficiency for 0.25 micron l particles, at least 10% of these vapors can escape. (3) For materials whose boiling point is i
above 55_C and where vapors formed by boili'ng this material can escape only through an undisturbed I
column of water above the core, at least 10% of f these vs.pors can escape.
l 1
Basis
- a. Double encapsulation is required to lessen the experimental hazards of some types of materials.
- b. Operation of the reactor with the reactor fuel or structure damaged is prohibited to avoid release of fission i
products.
- c. The 1.5-curie limitation on iodine 131 through 135 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 is limited.
- d. This specification is intended to prevent damage to reactor components resulting from failure of an experiment involving explosive materials.
I
- 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).
i l
Page 29
- . . _ _ _ _ _ - _ . - _ _ _ _ _ . - . _ _ . . _ _ _ _ . . _ _ _ _ _ _ . _ . _ _ _ _ _ _ - ~ . _ _ __
Technical Specificationo 4/85 4.0 SURVEILLANCE REQUIREMENTS 4.1 Reactivity Limits 4.1.1 Excess Reactivity Applicability This ' specification applies to the measurement of reactor excess reactivity.
Objective
~
The objective is to periodically determine the'changesdia core; excess reactivity available for power generation. , f Specification (s)
Excess reactivity shall be determined annually of after 1
significant reactor core or control rod changes.
Basis Annual determination of excess reactivity and measurements sufficient to after reactor core or control rod changes are monitor significant changes in the core excess reactivity.
4.1.2 Shutdown Margin Applicability This specification applies to the measurement of reactor shutdown margin.
objective;
.Ther.ob'jective'is to periodically determine the core shutdown -
' reactivity available for reactor shutdown.
- Specification (s)
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 to
! after reactor core or control rod changes are sufficient l monitor significant changes in the core shutdown margin.
Page 30
Technical Specifications 4/85 l
4.1.3 Transient Insertion Applicability This speciEication applies to suzveillance of the transient
.! rod mechanism and to observation of the reactor transient response.
E 0bjective The objective is to assure the function of the transient rod drive and to compare the reactor pulse insertion parameters.
' Specification (s)
The transient rod drive cylinder and associated air supply l
i }-
shall be inspected, cleaned, and lubricated annually, and l
- a. A reactor pulse shall be performed annually to l compare fuel temperature, peak power and energy measurements with those of previoes pulses.
b.i The reactor shall not be pulsed routinely until j such comparative measurements have been made.
Basis Annual inspections of the pulse rod drive system should be sufficient to detect and correct changes in the system that The annual measurement of pulse could impair operability.
parameters provides data to monitor changes in the reactor core transient characteristics.
4.1.4 Fuel Elements Applicability
~i This specificaticn applies to the inspection requirements for the fuel elements.
Objective The objective is to inspect the physical condition of the fuel element cladding.
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.
Page 31
-- - - - - - - - - - - - - - - - - _ _ _ _ _ _ _ . . 4
e Technical SP ecifications 4/85 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.
4.2 Reactor Control and Safety System 4.2.1 Control Assemblies Applicability This specification applies to the surveillance of the control rods.
Objective The objective is to inspect and the physical establish the condition operable of the condition reactor control rods of the scram times and of the rod by periodic measurement insertion rates.
Specification (s)
Control rod worths shall be determined annually of af t er significant core or control rod changes, and
- a. Each control rod shall be inspected at biennial intervals by visual observation.
l
- b. The scram time of a scrammable control rod shall be measured annually.
l I
1
- c. The reactivity insertion rate of a standard control rod shall be measured annually.
Basis or measurements l
Annual determination of control rod worths l
I after significant core changes provide information about changes in reactor total reactivity and individual rod worths. The frequency of inspection for the control rods condition of the will provide periodic verification ofwill Verification thebe by measurement control rod assemblies.
j of fueled sections and visual observation of absorber j
I sections plus examination of linkages and drives.
The specification intervals for scram time and Deviations insertica rate assure operable performance of the rods.
that are significant from acceptable standards will be promptly corrected.
Page 32
4 4
Technical Specifications 4/85 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.
Specification (s)
The minimum safety interlocks shall be tested at semiannual intervals.
Basis The periodic test of the interlock logic at semiannual t
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 S'afety System l
I Applicability This specification applies to tests of the function of the reactor safety system.
Objective check or The objective is to specify intervals for test, 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 thac the setpoints of the safety-system safety system prior to scrans are functional. Tests of the each planned operation assure that each intended scram function is operable.
Page 33
.-_.m _. _ _ .. _ . _ _ . _ . _ . - . _ _ . _ _ _ _ _ . _ , _ _ _ _ _ _ _
I
- I
! Technical Specifications 4/85 i
1 4.2.4 Reactor Instrument System Applicability
' These specifications' apply to calibrations, checks, and j tests of reactor measurement channels.
Objective J
]
The' objective is to specify intervals for test, check or '
i 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.
I Basis f 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.
4.3 Onerational Suncore Systems 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 maintain the reactor coolant conditions within acceptable specifications.
Specification (s)
The following measurements shall monitor the reactor coolant conditions:
- a. The water temperature sensor shall be checked annually, tested monthly and monitored continuously during reactor operation.
- b. The water depth sensor shall be checked annually, tested monthly and monitored continuously during operation of the reactor.
Page 34 .
4 Technical Specifications 4/85 4
- c. The water conductivity sensor shall be checked annually and pool water conductivity measured monthly.
- 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 that devices the for the coolant reactor coolant system parameters assure I
system will perform its intended function.
4.3.2 Air Confinement Systems Applicability l
This specif'ication applies to surveillance conditions for the air ventilation in the reactor area.
f Objective The objective is to demonstrate the function of confinement and release of air from the reactor bay.
Specification (s)
The following actions shall demonstrate the air confinement i conditions:
- a. Annual examination of door seals and isolation l dampers.
l 1
! b. Monthly functional tests of air confinement isolation.
- c. Calibration of argon-41 measurements shall be made anaually and measurements or calculations performed quarterly.
l Basis Periodic evaluations of air confinement criteria are determined by examination, test, and calibration of the appropriate ventilation functions. the reactor bay provide I
control for radioactive releases by both routine and non l
routine operating conditions.
l Page 35
Technical Specifications 4/85 4.3.3 Radiation Monitoring Systems Applicability This specification applies to the surveillance conditions of the radiation monitoring channels.
Objective are The objective is to assure the radiation monitors functional.
Specification (s)
The minimum radiation monitors specified to be operable during reactor operation shall be
- a. Calibrated at semiannual intervals,
- b. Checked at monthly intervals for fixed monitor.
- c. Checked daily for portable monitor.
Basis Periodic calibrations and frequent checks are specified to maintain reliable performance of the radiatio'n monitoring instruments.
4.4 Limitations on Exneriments 4.4.1 Reactivity i
Applicability l
l 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.
1 Basis the reactivity The measured reactivity or determination that' is not significant will provide data that configuration of the experiment or experiments is allowable.
Page 36
- -~ . _ _ _ _ _ . _ _ _ _ _ . _ . _ . _ - - . - - --- ,. _,______ _ ___ __
t Technical Specificationo 4/85 4
4.4.2 Irradiations Applicability surveillance requirements This specification applies to the for reactor irradiations.
Objective
.The objective is to provide a record of experiments inserted in the reactor as irradiations.
Specification (s) identified Experiments classified as irradiations shall be and a log or other record maintained while the sample is in the reactor.
Basis irradiations are monitored by data f Experiments performed on the sample location, as identification and other pertinent information.
4.4.3 Materials Applicability i
This specification applies to the surveillance requirements for materials inserted into the reactor.
Objective The objective is to prevent 2the introduction of materials that could damage the reactor or its components. .
Specification (s) shall be Any surveillance conditions or special approval.
of the experiment requirements specified as a part Basis A careful evaluation of all experiments is performed to classify the experiment as an approved experiment.
Page 37
Technical Specificationo 4/85 l
j 5.0 DESIGN FEATURES l
5.1 Site and Facility Descrintion 5.1.1 Location
? Applicability '
This specification applies to the TRIGA reactor site'y . ..
location:and specific facility' design features, g, i .
Objective The objeebive is to specify those-features related edidhe '
Safety Analysis evaluation. m. . ' . -
' Specification (s) ,a
~
- s. _TheUniversity
'The site location is in the of Texas northeast at Austin corner.of Balcones Research Center.
- b. The TRIGA reactor is installed in a designated room of a building constructed as a Nuclear Engineering Teaching Laboratory.
- c. The reactor core is assembled in an above ground shield and pool structure with horizontal and vertical access to.the core. .
- d. Restricted access area of the facility shall .
consist of the room enclosing the.reactori. shield and pool; structure, and the adjacent area. fora 2>
. reactor. control. . i.:;g N'. .
7, _ -
' l5l,'); l ~
~ l ?* h . ' ;WN
. Basis
... J (, 4
? >-
'The TRIGA1 facility l; site is located in:an area
. ye
- s. -
' controlled by TherUniversity of? Texas.at '.
Austing,f' g h g,_ _
- =
^
b '. 'The: room encic-4ing the reactor.has been designed.with-
'.characteristius related to the safe operation ofdthe; '~ ~
_: 33g cfacility. , , ,
' c.
L
'The. shield and-pool structure have.been designed f'or radiation. levels of less than 1 ares /hr at locatio~ns c.
that are not access ports to the reactor structure.
- d. The resticted 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.
Page 38
Technical Specificationo 4/85 5.1.2 confinement Applicability \
I i
This specification applies to the boundary for control of I l sir 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. ' \
l Specification (s) l
' I
- a. The reactor bay shall be designed to restrict
! leakage and will have a minimum enclosed air 1 i
volume of 4120 cubic meters. .
t l
- b. Ventilation system should provide two air changes l per hour and shall isolate air in the reactor area 1 upon detection of a limit signal related to the ,
radiation level. I Emergency ventilation system shall be filtered by I
c.
high efficiency particulate adsorption filters and should maintain a negative pressure compared to ambient air conditions. .
- d. All exhaust air from the reactor area enclosure shall be ejected vertically upward at a point above the facility roof level.
(
Basis
- a. Calculations of the concentrations of released radionuclides within the reactor area depend on the available enclosed air volume to limit the i
concentrations to. acceptable levels.
- b. Control of the reactor area air exchange is by fan motors and isolation dampers for the supply and exhaust air which are controlled by a logic signal from a radiation sensor to provide 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 filtration.
- 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.
Page 39
t Technical Specifications 4/85 5.1.3 Safety Related Systems l Applicability This specification applies to the requirements of any system related to reactor safety.
Objective T'he objective is to assure the proper fu'nction of any system related to reactor safety.
Specifications or
~
Any modifications or maintenance-to the air confinement 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 l
the reactor safety 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 operation 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 specifications are assumed to meet the presently accepted operating criteria.
Questions 7
P that may include an unreviewed safety question,are referred to the reactor operation committee.
5.2 Reactor coolant systna Applicability This specification applies to the reactor. coolant system composed of deionized water.
Objective The' objective is to assure that adequate water is available for cooling and shielding during reactor operation.
Specification (s)
- a. The reactor core shall be cooled by natural convection flew of water.
Page 40
~_ __
l 6
Technical Specificationo 4/85 1
- b. Pool water level shall be protected by holes for siphon breaks in pool water system pipe lines.
Basis This specification is based on thermal and hydraulic
- a. a standard 85 element calculations which showinthat a safe manner at power levels TRIGA core can operate up to 1,900 kW with natural convection flow of thecoo ratio of 2.0.
Siphon breaks set the subsequent poci vater level for
- b. an associated water return loss of coolent withoutpumping caused by inadvertant or accidental siphon of water from the pool.
5.3 Reactor Core and Fuel 5.3.1 Fuel Elements Applicability This specification applies to the fuel elements used in the reactor core.
Objective The objective is to assure that the fuel elementsto arepermit of such a design and fabricated in such a manner as to their use with a high degree of reliability with respect l
their physical and nuclear characteristics.
Specification (s) at fabrication shall have The standard TRICA fuel element the following characteristica:
- b. Zirconium hydride atom ratio:
to zirconium, ErH ;
- c. Cladding: 304 stainless steel, nominal .020 inches thick.
Basis standard TRICA core demonstrates The Design basis that 1.5 megavatt of thesteady or 36 megawatt-sec puist operation to safety presents a conservative limitation with respect in the fuel.
limits for the maximum temperature generated Page 41
Technical Specificationo 4/85 ,
The fuel temperatures are not expected to exceed 550_C during any condition of normal operation.
5.3.2 Control Rods Applicability i'
This specification applies to the control rods used in the I reactor core.
> - ~
Objective-
-The objective'islto' assure that;the control rods are?$f such a design as to' permit their use:'with a h.igh degree of:-
- reliability with; respect to their physical and nuclear '
characteristics.. .
s Specification (s)
The safety, shim, regulating, and transient control rods shall have scram capability, and l
l s. Contain borated graphite, B C 4 powder, or boron and its compounds in solid form as a poison in I
aluminum or stainless steel cladding.
i
- b. The transient rod shall have an adjustable limit to allow a variation of reactivity insertions'and the rod may contain an air follower.
- c. The' safety, shim and regulating rods may have a fuel follower.
o I. Basis -
I . . . '.' . 8
- The poison requirements'for.the control-rods Bare satisfied
~
[
C powderM'or
'by using neutron absorbing borated graphite, 4 J
~
' boron ~and' its compounds.- The'se materials must beicoatsined 4 (in
. steel,a suitable
to-insure clad material. :such mechanical stability as during
-aluminum.or stainless movementiend.co Scram I~
isolate the poison from the. pool water environment.
capabilities are provided for, rapid insertion?of the control rods which' is -the primary- safety cfeature of theireactor.:
The transient' control rod is designed for a reactor' pulse %.
5.2.1 Configuration ,
Applicability to the configuration of fuel This elements, specification control rods, appliesexperiments and other reactor grid plate components.
Page 42
~ ~ ~ ' ~ ~ - - ~ ~ ' - -~ ' - - - - - -. _ _ _ _ _ _ _ _ _ . __ _
i Technical Specifications 4/85 Objective The objective is to assure that provisio'ns are made to restrict the arrangement of fuel elements and experiments so as to provide assurance tha't excessive power densities will not be produced.
Specif.ication(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 exp'eriment facilities. Specisi l
oultielement 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.
5.4 Reactor Fuel Element Storare 1
Applicability This specification applies to the storage of reactor fuel at times when it-is not in the reactor core.
Objective The objective is to assure that fuel storage will not become critical and will not exceed design temperatures.
Specification (s) ,
- a. A11' fuel elements shall be. stored in a geometrical less array.where the effective multiplication is than 0.8'for all conditions of moderation.
~
shall
- b. ' Irradiated fuel elements and fueled devices be stored in an array which will permit sufficient natural convection cooling by water or air such that the fuel element ore, fueled. device temperature will not exceed design values.
Basis The limits imposed by these specifications are considered sufficient to provide conservative fuel storage and assure safe storage.
Page 43
Technical Specifications 4/85 6.0 ADMINISTRATIVE CONTROLS r 6.1 Oreanization 6.1.1 Structure The facility shall be under the direct control of the q.,
Director or a licensed senior. operator designated to be in direct control. The manageme'nt.for operation of the '
~
facility shall consist of the. organizational. structure .
established as follows:
-Office, President: -
4-University'of Texas at' Austin -
Vice President for Academic Affairs and Research 2
Dean College of Engineering Chairman Reactor Radiation Operation Safety Department of Mechanical Engineering Committee Committee Director Nuclear Engineering Teaching Laboratory Supervisor ,
Reactor Operations 6.1.2 Re s pon sib'ility '
The Director shall be responsible to the -Dean -of theico11ege of Engineering and the Chairman of the Department of' j_ ,
Mechanical Engineering for safe operation 1and Themaintenancejof Director;or.
the reactor and its associated equipment.
his appointee shall review and approve all experiments 1and in the reactor.
experimental pr'ocedures priororganization to their use shall be Individuals of the managementand responsible for the policies 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.
Page 44
Technical Specificationc 4/85 6.1.3 Staffing The minimum staffing when the reactor is not secured shall be:
- a. A certified operator in the control room.
- b. A second person in the facility area that can perform prescribedfor written instructions.
two hours shall require Unexpected absence l immediate action to obtain an alternate person.
- c. A designated Class A operator readily available.
The available operator should be within thirty minutes of the facility and reachable by telephone.
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.
Recovery from an unscheduled shutdown will require documented verbal concurrence if the cause is c.
unknown.
A list of reactor facility personnel by name and telephone control number shall be available to the operator in the room. The list shall include:
- a. Management personnel.
- b. Radiation safety personnel.
- c. Other operations personnel'.
6.1.4 Selection'and Training of Personnel The selection, training and regulification of operators shall meet or exceed the requirements of American National Standard for Selection and Training of Personnel for Research Reactors ANSI /ANS - 15.4. Qualification and shall be subject to requalification an approved NRC of certified operators (Nuclear Regulatory Commission) progra 2
Page 45
Technical Specifications 4/85 6.2 Review and Audit 6.2.1 Composition and Qualifications A Reactor Operat' ion Committee shall consist of at least three (3) members appointed by the Dean of the College of Engineering that The are knowledgeable in fields Safety University Radiological which relate to Officer nuclear safety. The shall be an ex-officio member of the Reactor Committee. or committee will perform the functions of review and audit designate a knowledgeable person for audit functions.
6.2.2 Charter and Rules The operations of tae Reactor Committee shall be in accordance with an established charter, including provisions for:
- a. Meeting frequency (at least once each semester),
than one-half the membership),
- b. Quorums (not less
- 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.
All new procedures and major revisions thereto, and proposed changes in reactor facility equipment b.
2 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.
- e. Violations of technical specifications or license.
- f. Operating abnormalities or violations of procedures having safety significance.
- g. Other reportable occurrences.
- h. Audit reports.
Page 46
4 4
7 Technical Specifications 4/C5 J
6.2.4 Audit Function f The audit function shall be a selected examination of operating records, logs, or other documents. An audit will be by a person not directly responsible for the records and
[
may include discussions withThe cognizant personnel or following items shall be
' observation of operations.
audited and a report made to the Reactor Supervisor and Reactor Operation Committee:
- a. Conformance of facility operations with license ,
l and technical specifications at least once each j calendar year. i l
- b. Results of actions to correct deficiencies that l may occur in reactor orfacility equipment, methods of operation that j structures, systems, i
affect safety at least once per calendar year.
- c. Function of the retraining and requalification l program for certified operators at least once I
every other calendar year.
- d. The reactor facility emergency plan and physical security plan, and implementing procedures at l least once every other year.
1 l
6.3 Oneratine Procedures Written operating procedures shall be prepared reviewed and and the
' approved by the Director or a designated alternate Reactor Operations Committee prior to initiation of the following activities:
a Startup, operation, and shutdown of the reactor;
- d. Fuel loading, unloading and movement in the l
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;
- 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; Page 47
i Technical Specificationo 4/85
- 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 '
j 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 I procedures may be made by a Class A operator in order to deal with special or unusual circumstances or conditions.
Such deviations shall be documented and reported to the Director or the designated alternate.
6.4 Exneriment Review sud Anoroval All new experiments or classes of experiments shall be approved by the Director a designated alternate and the Reactor Operations Committee.
- n. 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 Reauired Actions 6.5.1 Action to be Taken in Case of a Safety Limit Violation In the event of a safety limit v io'Is t ion , 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 Nuclear Regulatory Commission (NRC).
- b. The safety limit violation shall be promptly reported to the Director of the facility or a designated alternate.
- c. The_ safety limit violation shall be subsequently reported to the NRC.
Page 48
i I
Technical Specificationo 4/85
- 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 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, (3) Corrective actions taken to prevent recurrence.
6.5.2 Action to be Take'n in the Event of an '
Occurrence that is Reportable.
In the event of a reportable occurrence, the following action shall be taken:
- a. Reactor conditions shallIfbeitreturned to normal or is necessary to shut the reactor shutdown.
down the reactor to correct the occurrence, operations shall not be resumed unless authorized by the Director or his designated alternate.
- b. Occurrence shall be reported to the Director or l
his designated alternate and to licensing authorities as required.
- c. Occurrence shall be reviewed by the Reactor Opera, tion Committee at the next regularly scheduled meeting.
6.6 Renorts 6.6.1 Operating Reports i .
Routine annus1 reports covering the activities of the reactor facility during the previous calendar year shall be submitted to the NRC Region IV with a copy to the Director of the Office of Nuclear Reactor Regulation 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.
I
- b. The unscheduled shutdowns including, where f
l applicable, corrective action taken to preclude recurrence.
- c. Tabulation of major preventive and corrective maintenance operations having safety significance.
,,,, 4, _
Technical Specifications 4/85
- d. Tabulation of major changes in the reactor i 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 a statement to this effect allowed or recommended, is sufficient.
- f. A summarized result of environmental surveys performed outside the facility.
i
- g. A summary of exposures received by facility personnel and visitors where such exposures are greater than 25% of that allowed or recommended.
6.6.2 Special Reports There shall be a report not later than the following working day by telephone and confirmed to the NRC Regionin writing IV toby betelegraph or a followed by similar conveyance written report within 14 days that describes the circumstances of the event of any of the following:
r
- a. Violation of fuel element temperature safety limit.
- b. Release of radioactivity above allowable limits.
I
- c. Other reportable occurrences.
are Other events that will be considered reportable A return to normal eventsor operation listed in this section.
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.)
l Page 50
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Technical Specifications 4/85
- s. Operation with actual safety-system settings for required systems less conservative than the lir.it ing 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 its intended asfety system incapable of performing 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 limits of personnel prescribed radiation exposure or environment, or both, e.
An observed inadequacy in the implementation of administrative or procedural controlscaused such that the the inadequacy causes or could have existence or development of an unsafe condition with regard to reactor operations.
l A report within 30 days to the NRC Region IV of:
l
- 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 or of the reactor, upon receipt of a new facility license, an amendment to the license authorizing an increase in the reactor power level, describing the measured of the values of reactor under operating conditions or characteristics 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.
Page 51
i Technical Specificationo 4/85 I I
6.7 Records }
The records may be in the form of logs, data sheets, or other suitable forms. The required information or a may be combination l'
contained in single or multiple records, 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 I 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.
shall be maintained for a period of at least one year).
I 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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