ML20028H660
| ML20028H660 | |
| Person / Time | |
|---|---|
| Site: | 05000192 |
| Issue date: | 01/16/1991 |
| From: | Crutchfield D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20028H659 | List: |
| References | |
| R-092-A-012, R-92-A-12, NUDOCS 9101240338 | |
| Download: ML20028H660 (42) | |
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UNITED STATES J' ') /$
NUCLEAR REGULATORY COMM".310N i
W ASHINGToN. D.C. 20846 o
N.u....f RENEWAL OF FACILITY LICENSE DOCKET NO. 50-192 THE UNIVERSITY Of TEXAS Amendnent No.12 License No. R-92 1.
The U.S. Nuclear Regulatory Comission (the Comission) has found that:
A.
The application for renewal of facility License No. R-92 filed by the University of Texas, (the licensee), dated October 19, ISSO.
complies with the standards and requirements of the Atomic Energy Act of 1954, as amendeo' (the Act), and the Comission's regulations as set forth in 10 CFR Chapter I; D.-
Construction of the f acility was completed in substantial conformity with the application dated November 1,1961, as amended, Construction permit No. CPRR-70, the provisions of the Act, and the regulations of the Comission; C.
The facility will be naintained in conformity with the application, the provisions of the Act, and the regulations of the Commission; D.
There is reasonable assurance:
(1)thattheactivitiesauthorized by this license can be conducted without endancering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; E.
The licensee is technically and financially cualified to engage in the activities authorized by this license in accordar.ce with the regulations of the Commission; F.
The licensee is a nonarofit educational institution and has satisfied the applica>1e provisions of 10 CFR Part 140, " Financial Protection Requirements and Indemnity Agreements," of the Comission's regulations; G.
The issuance of this license will r.0t be inimical to the comon defense and security or to the health and safety of the public; H.
The issuance of this license is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements i
have been satisfied; and
$101240338 910116 PDR ADOCK 05000192 P
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1.
The possession and use of the byproduct mater 161s as authorized by this license will be in accordance with the Commission's regulations in 10 CFR Part 30, including Section 30.33, and 10 CFR Part 70.
2.
Accordingly, facility License No. R-92 is hereby amended in its entirety to read as follows:
A.
This license applies to the TRIGA Mark I pool-type nuclear reactor that is owned by the University of Texas and located on the main campus, Taylor Hall, at Austin, Texas, and described in the -
licensee's application for license renewal dated October 19,_1990.
B.
Subject to the conditions and requirements incorporated herein, the Commission hereby. licenses the University of Texas:
l-1.
Pursuant to Section 104c of the Act and 10 CFR Part 50, "Oomestic Licensing of Production and Utilization facilities,"
to possess, but not to operate, the reactor in accordance with the procedures and limitations set forth in this license;
-2.
Pursuant to the Act and 10 CFR Part 70, " Domestic Licensing of Special Nuclear Material," to possess and transfer up to 4
5.620 kilograms of contained uranium-235 that was used in connection with operation of the reactor; 3.
Pursuant to the Act and 10 CFR.Part 30, " Rules of General Applicability to Domestic Licensing of Byproduct Material,"
to receive, possess and transfer, a 6-curie sealed polonium-
-beryllium neutron source and a 2-curie sealed americium-beryllium neutron source, either of which may have been used for reactor startup, and 1200 micrograms of californium-252 which may have been used in the reactor for experimental pur-poses; and to possess and transfer, but not to separate, such byproduct material as may have been produced by operation of the reactor.
4.
Pursuant to the Act cd 10 CFR Part 70, " Domestic Licensing of Special Nuclear Material," to receive, possess, and transfer, up to 10 milligrams of uranium-233, 50 milligrams of uranium-235, 10 milligrams _of plutonium-240, 10 milligrams of plutonium-241, 10 milligrams of plutonium-239'in the form of foils, 1 gram of-plutonium-239 in the form of reference material, 10 grams of uranium-235 in the form of reference materials, and 150 grams of plutonium-239 contained in sealed stainless pins, all-for experi-mental purposes.
5.
' Pursuant to the Act and 10 CFR Part 30, " Rules of General-Applicability to Domestic Licensing of Byproduct Material," to possess and use, including transfer, a 10 kilocurie cobalt-60 irradiator as described in the application for amendment, dated January 23, 1968, as supplemented April 29, 1968.
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6.
Pursuant to the Act and 10 CFR Part 40, " Domestic Licensing of Source Material," to possess and transfer up to 8 milligrams of uranium-236 and 150 experimental purposes. grams of uranium-238 as foils for C.
This lictnse shall be deemed to contain and is subject to the conditions specified in Parts 20, 30, 50, 51, 70 and 73 of 10 CFR, Chapter I, to all applicable provisions of the Act, and to the rules, regulations and orders of the Comission now or hereaf ter in effect, and to the additional conditions specified below:
1.
Maximum Power Level The reactor will not be in a " Reactor Operating" condition as defined in the Technical Specifications definitions.
2.
Technical Specifications The Technical Specifications contaired in Appendix A as revised through Amendment No.12, are hereby incorporated into this license..The licensee shall maintain the facility in accordance with the Technical Specifications.
3.
_ Physical Security The licensee shall maintain and fully implement all the provisions of the Comission-approved physical security plan, including-amendirents and changes made pursuant to the authority of 10 CFR 50.54(p). 'The a) proved security plan consists of documents withheldfrompu'>1icdisclosurepursuantto10CFR2.790(d),
entitled " University of Texas Physical Security Plan for the Protection of Reactor Facilities and Special Nuclear Materials of Low Strategic Significance," submitted'by letter dated June 30,'1983 (plan dated June 1983).
4 3.
This license amendment is effective as of its date of issuance and shall expire at midnight February 12, 1993.
FOR THE NUCLEAR REGULATORY COW.ISSION W hw
~
Dennis M. Crutchff
, Director Division of Advanced Reactors and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
Arspendix A Technical Specifications Date of issuance: January 16, 1991
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APPDOIX A Technical Specificationa Technical Specifications Revision 6/90 Docket $0-192 The University of Texas at Austin TRIGA Reactor June 1990 Page 1 l
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R) vision 6/90 Technical Spselfications 6
Table of Contents 1.0 der 1N1710NS 5
1.1 Certified Operators 5
1.1.1 Senior Reactor Operator 5
1.1.3 Reactor operator 5
1.2 Channel.
5 1.2.1 Channel Test 5
1.2.2 Channel Check 5
i 1.2.3 Channel Calibration 5
1.3 Confinement 5
1 1.4 Experiment 6
1.4.1 Experinent, Hoveable 6
1.4.2 Experiment, Secured 6
1.4.3 Experimental racilities 6
- 1. 5 ruel Elenent, Standard 6
i-1.6 ruel Element, Instrument 6
1.7 Hodes Manual, Pulse 6
1.8 Steady State 6
1.9 Operable 7
1.10 Operating 7
1.11 Protective Action 7
1.11.1 Instrument Channel Level 7
h 1.11.2 Instrument System Level _
7 1.11.3 Reactor Safety System Level 7
1.12 Reactivity, Excess 7
1.13 Reactivity LJndt 7
1.14 Reactor Core, Standard 8
1.15 Reactor Core, operations 1 8
1.16 Reactor Operating B
1.17 Reactor Safety System 8
1.18 Reactor Secured 8
1.19 Reactor Shutdown 9
1.20 Reference Core Condition 9
1.21 Research Reactor 9
1.22 Rod,-Control 9
1.22.1 Shim Rod-9-
1.22.2 Regulating Rod 9
1.22.3 Standard Rod 9
1.22.4 Transient Rod 9
1.23 Safety Lindt 10-1.24-Scram Time 10 1.25 Shall, should and May 10 1.26 Shutdown Hargin.
10 1.27 Shutdown, Unscheduled 10 1.28 Value, Hessured 10 1.29 Value, True 10 1.30 Surveillance Activities 11 1.31 Surveillance Intervals 11 6/90 Page 2 l
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Rovision 6/90 U
Technical Sp2cifications 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 12 i _
2.1 SAFETY LIMIT 12 4
2.2 LIMITING SAFETY SYSTEM SETTINGS 12 a
3.0 LIMITING CONDITIONS FOR OPERATION 13 3.1 REACTOR CORE PARAMETERS 13 3.1.1 Excess Reactivity 13 3.1.2 Shutdown Margin 13 3.1.3 Transient Insertions-13 3.1.4 Fuel Elements 13 3.2 REACTOR CONTROL AND SATETY SYSTEM 13 3.3 OPERATIONAL SUPPORT SYSTEMS 13 3.3.1 Water Coolant Systems 13 3.3.2 Air Confinement Systems 14 3.3.3 Radiation Monitoring Systems 14 4.0 SURVEILLANCE REQUIREMENTS 15 4.1 REACTOR CORE PARAMETERS 15 4.1.1 Excess Reactivity 15 4.1.2 ruel Elements 15 4.2 REACTOR CONTROL AND SATETY SYSTEM 15 4.2.1 Control Assemblies 15 4.3. OPERATIONAL SUPPORT SYSTEMS 15 4.3.1 Water Coolant Systems 15 4.3.2 Air Confinement Systems 16 4.3.3 Radiation Monitoring Systems 16 5.0 DESIGN TEATURES 17 5.1 SITE AND TACILITY DESCRIPTION-17 5.1.1 Location 17 5.1.2 Confinement 17 5.1.3 Safety-Related Systems 17 5.2 REACTOR COOLANT SYSTEM 18 5.2.1 Natural Convection IB 5.2.2 Siphon Protection 18 5.3 REACTOR CORE AND FUEL 18 5.3.1 ruel Elements 18 5.3.2 Control Rods-1B
'5.3.3 Configuration 19 5.4 REACTOR TUEL ELEMENT STORAGE 19 5.5 REACTOR POOL GAMMA IRRADIATOR 19 l '
6/90 Page 3 a.
Rsvision 6/90 Technical Spacifications 6.0 ADMINISTRATIVE 20 6.1 ORCANIZATION 20 6.1.1 Structure 20 6.1.2 Responsibility-21 6.1.3 Staffing 21 6.1.4 Selection and Training of Personnel 22 6.2 REVIEW AND AUDIT 22 6.2.1 Composition and Qualifications 22 6.2.2 Charter and Rules 22 6.2.3 Review runction 22 6.2.4 Audit runction 23 6.3 OPERATING PROCEDURES 23 6.4 EXPERIMENT REVIEW AND APPROVAL 24 6.5 REQUIRED ACTIONS 24 6.5.1 Case of Safety Limit Violation 24 6.5.2 Event of a Reportable occurrence 24 6.6 REPORTS 25 6.6.1 Operating Reports 25 6.6.2 Special Reports 25 6.7 RECORDS 27 6.7.1 Lifetime of the racility.
27 6.7.2 rive Years or the Life of the Component 27 6.7.3-One Licensing Cycle 27 APPENDIX A.1 Introduction 2B A.2 Objectives & Bases for Safety Limits 20 A.3 Objectives & Bases for Limiting Conditions for Operations 30 A.4 Objectives.& Bases for Surveillance Requirements 33 A.5 Objectives & Bases for Design Features 35 l
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R3 vision'6/90 Technical $pacifications 1.0 der 2NITIONS 1.1 Certified Operators
. An-individual authorized by the U.S. Nuclear Regulatory Conadssion to carry out the responsibilities = associated with the position requiring the i
certification.
1.1.1 Senior beactor Operator l
An individual who is certified to direct the activities of reactor operators.
Such an individual may be referred to as a class A operator.
1.1.2 Reactor Operator An individual-who is certified to manipulate the controls of a reactor.
Such an individual may be referred to as a class B operator.
1.2 2nstrumentation Channel A channel is the combination of sensor, line, amplifier, and output device which are connected for the purpose of measuring the value of a parameter.
1.2.1 Channel Test
. Channel test is the introduction of a signal into the channel for verification that it is operable.
1.2.2 Channel Check Channel check is a qualitative verification of acceptable performance by observation of channel behavior.
This verification where possible, shall include comparison of the channel with other independent channels or systems neasuring the same variable.
' 1.2.3 Channel Calibration Channe1' 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.
1.3 Confinement Confinement means an enclosurefon the overall facility which controls the movement of air into it and out through a controlled path.
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Rovisien 6/90 Tochnical Spoeifications 1.4 Experiment Any operation, component, or target (excluding devices such as detectors, foils, etc.), which is designed to investigate non-routine reactor characteristics or which is intended for irradiation within the pool, on or in a beam tube or irradiation facility and which is not rigidly secured to a core or shleid structure so as to be part of their design.
- 1. 4.1 Experiment, Hoveable A moveable experiment is one where it is intended that all or part of the experiment may be moved in or near the core or into and out of the reactor while the reactor is operating.
1.4.2 Experiment, Secured A secured experinent 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 arise as a result of credible conditions.
1.4.3 Experimental racilities Experimental facilities shall mean rotary specimen rack, pneumatic transfer tube, central thimble, beam tubes and irradiation f acilities in the core or in the pool.
1.5 ruel Element, Standard A fuel element is a single TRIGA element of standard type.
ruel is U-ZrH clad in stainless steel clad.
Hydrogen to tirconium ratio is nominal 1.6.
1.6 ruel Element, Instrumented An instrumented fuel element is a special fuel element fabricated for temperature measurement.
The element shall have at least one thermocouple embedded in the fuel near the axial and radial midpoints.
1.7 Hodes Manual, Pulse Each mode operation shall mean operation of the reactor with the mode selection switches in the manual or pulse position.
1.8 Steady-state Steady-state mode operation shall mean any operation of the reactor with the mode selection switch in the manual position.
The pulse mode switch will define pulse operation.
6/90 Page 6
Rovision 6/90 technical specifications 1.9 Operablo Operable neans a component or system is espable of performing its intended function.
1.10 Operating Operating means a component or system is performing its intended function.
1.11 Protective Action Protective action is the initiation of a signal or the operation of equipnent within the reactor safety system in response to a variable or condition of the reactor f acility having reached a speelfied lindt.
1.11.1 Instrunent Channel Level At the protective instrument channel level, protective action is the generation and transmission of a trip signal indicating that a reactor variable has reached the specified limit.
i 1.11.2 Instrument System Level At the protective instrument system level, protective action is the generation and transmission of the command signal for the safety shutdown equipment to operate.
d 1.11.3 Reactor Safety System Level s
At the reactor safety system level, protective action is the operation of sufficient equipment to immediately shut down the reactor.
1.12 Reactivity, Excess Excess reactivity is that amount of reactivity that would exist if all the control rods were moved to the maximum reactive condition from the point where the reactor is exactly critical.
1.13 Reactivity Limits yhe reactivity lindts are those limits imposed on the reactor core excess reactivity. Quantities are referenced to a reference core condition.
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Ravision 6/90 Technical Sp2cifications 1.14 R3 actor Coro, Standard A standard core is an arrangement of standard TRIGA fuel in the reactor grid plate and may include installed experiments.
1.15 Reactor Core, Operational An operational core is a standard core for which the core paraneters of excess reactivity, shutdown margin, fuel temperature, power calibration, and reactivity worths of control rods and experiments have been determined to satisfy the requirements set forth in the Technical Specifications.
1.16 Reactor Operating The reactor is operating whenever it is not secured or shutdown.
1.17 Reactor Safety Systems Reactor safety systems are those systems, including their associated input channels, which are designed to initiate automatic reactor protection or to provide information for initiation of manual protective action.
1.18 Reactor Secure The reactor is secure when 1.18.1 Suberitical :
There is insufficient fissile material or moderator present in the reactor, control rods or adjacent experiments, to attain criticality under optimum available conditions of moderation and reflection, or 1.18.2 The-following conditions exist The minimum number of neutron absorbing control rods are fully a.
inserted in shutdown position, as required by technical specifications.
b.
The console key switch is in the off position and the key is removed from the lock, No work is in progress involving core fuel, core structure, installed c.
control rods, or control rod drives unless they are physically decoupled from the control rods.
d.
No experiments 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.
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'R3 vision 6/90 Technical Specifications 1.19 Reactor Shutdown The reactor is shutdown if it is suberitical by at least one dollar in the j
reference core condition with the reactivity of all installed experiments i
includnd.
I 1.20 Reference Core condition The condition of the core when it is at ambient temperature (cold) and the reactivilty worth of xenon is negligible (<.30 dollars).
1.21 Research Reactor A research reactor is defined as a device designed to support a self-sustaining neutron chain reaction for research, development, educational, training, or experimental purposes, and which may have provisions for the production of radioisotopes.
1.22 Rod, Control A control rod is a. device fabricated from neutron absorbing material or fuel which is used to establish neutron flux changes and to compensate for routine reactivity loses. A control rod _may be coupled to its drive unit allowing it to perform a safety function when the coupling is disengaged.
1.22.1 shim Rod A shim rod is a control rod having an electric motor drive and scram capabilities.
1.22.2 Regulating Rod A regulating rod is a control rod used to maintain an intended power level and may be varied menually or by a servo-centro 11er.
The regulating rod shall have scram capability.
1.22.3 Standard Rod The regulating and shim rods are standard control rods.
1.22.4 Transient Rod A transient rod is a control rod used to initiate a power pulse that is operated by a motor drive and/or air pressure.
The transient rod shall have scram capability, l'
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Ravi@lon 6/90 Technical Spocifications
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1.23 Safoty Limits safety limits are limits on important process variables which are found to be necessary to protect reasonably tne integrity of the principal barriers which guard against the uncontrolled release of radioactivity.
The principal barrier is the fuel element cladding.
1.24 Scram Time Scram time is the elapsed time between reaching a lindting safety system set point and a specified control rod movement.
1.25 Shall, Should and May The word shall is used to denote a requirement.
The word should is used to denote a recommendation.
The word may is used to denote permission, neither a requirement nor a recommendation.
1.26 Shutdown Margin Shutdown margin shall mean the minimum shutdown reactivity necessary to provide confidence that the reactor can be made suberitical by means of the t
control and safety systems starting f rom any permissible operating condition and with the.most reactive rod in its most reactive position, and that the reactor will remain suberitical without further operator action.
1.27 Shutdown, Unscheduled An unscheduled shutdown is defined as any unplanned shutdown of the reactor caused by actuation of the reactor safety system, operator error, equipment malfunction, or a manual shutdown in response to conditions which could adversely affect safe operation, not including shutdowns which occur during testing or check-out operations.
1.28 Value, Hessured The measured value is the value of a parameter as it appears on the output of a channel.
1.29 Value, True The true value is the actual value of a parameter.
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Rovision 6/90 Technical specifications 1.30 surveillsnes 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 unless reactor operation is necessary for performance of the activity.
Surveillance activities scheduled to occur during an operating cycle which cannot be performed with the zeactor 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.
1.J1 Surveillance Intervals Maximum intervals are to provide operational flexibility and not to reduce frequency.
Established frequencies shall be maintained over the long term.
Allowable surveillance intervals shall not exceed the following:
1.31.1 5 years (interval not to exceed 6 years).
1.31.2 2 years (interval not to exceed 2-1/2 years).
1.31.3 Annual (interval not to exceed 15 months).
1.31.4 Semiannual (interval not to exceed 7-1/2 months).
1.31.5 Quarterly (interval not to exceed 4 months).
1.31.6 Honthly (interval not to exceed 6 weeks).
1.31.7 Weekly (interval not to exceed 10 days).
1.31.8 Daily (must be done during the calendar day).
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Rovision 6/90 Technical Sp3cifications 2.0 SArETY LIMITS AllD LIMITING $ATETY SYSTEM SETTING $
2.1 gaiety t1mlt Specification (s)
The maximum temperature in a standard TRIG \\ fuel element shall not exceed 1150'c for fuel element clad temperatures less than 500'C and shall not exceed 950'C for f uel element clad temperatures. greater than 500*C.
Temperatures apply to any condition of operation.
2.2 timitine safety system settings Specifica tion (s)
Not applicable 6/90 Page 12
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Rovision 6/90 Technical Specifications i
e 3.0 LIMITING CONDITIONS FOR OPERATION 3.1 PJtactor core l'a ramattIA 3.1.1 Reactivity Specification (s)
The reactor core shall have no excess reactivity and the shutdown margin with all control rods withdrawn shall be greater than 0.2% Ak/k.
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The number of fuel elements in the reactor core grid shall not fill more than two of the grid structure rings.
3.1.2 Tuel Elements Specification (s)
The reactor shall not be operable with fuel element damage. A fuel element shall be considered damaged if:
In measuring the elongation, the length exceeds the original length by a.
2.54 mm (1/10 inch).
b.
In measuring the transverse bend, the bend exceeds the original bend by 1.5875 mm (1/16 inch).
A clad defect exists as indicated by release of fission products or c.
visual observation.
3.2 Reactor Control and Mafetv Svstem specification (s)
Not' Applicable 3.3 Doeratlenal Eunoert Rvntamm 3.3.1 Water Coolant Systems i
Specification (s)
Corrective action shall be taken or the reactor shut down if any of the following reactor coolant conditions are observed I
The bulk pool water temperature exceeds 48'C.
a.
b.
The water depth is less than 6.5 meters measured from the pool bottom to the pool water surface.
The water conductivity exceeds 5.0 pmho/cm for the average value-c.
during measurement periods of one month.
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-R2 vision 6/90 Technical speelfications d.
Th3 pressure difference during heat exchanger operation is less than 7 kPa (1 psig) measured between the chilled water outlet pressure and the pool water inlet pressure to the heat exchanger, Pool water data from periodic measurements shall exist for water pH e.
and radioactivity.
Radioactivity measurements will include total alpha-beta activity and gamma ray spectrum analysis.
3.3.2 Air Confinement Systems Specification (s)
Not Applicable 3.3.3 Radiation Monitoring Systems Specification (s)
Radiation-monitoring while the reactor is operating requires the following minimum conditions a.
A continvous air monitor (particulate) shall be operable with readout and audible alarm. _The monitor shall sample reactor room air within 5 meters of the pool at the pool access level.
The particulate continuous air monitor shall be operating when the reactor is operating. A set point of the monitor will inititiate an audible warning signal.
b.
Area radiation monitors (gamma) shall be operable with reac%t and audible alarm, one of which shall be located in the vicinity of tne top of the reactor pool.
One area radiation monitor shall be operating at the pool level when the reactor is operating.
Two additional area radiation monitors shall be operating at other reactor areas when_the reactor is operating.
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R3 vision 6/90 Technical Specifications
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4.0 SURVEILLANCE REQUIREMENTS 4.1 Peacter core I aramelen 4.1.1 Reactivity Specification (s)
The number of elements and physical location in.the grid structure shall be verified monthly.
4.1.2 ruel Elements Specification (s)
The reactor fuel elements shall be examined for physical damage by a visual inspection, including a check of the dimensional measurements, made at biennial intervals, if the fuel has bSen in the operating core during the interval.
4.2 Reactor control and Safety System 4.2.1 Control Assemblies Specification (s)
Not Applicable 4.3 Cperatienni support Mystema 4.3.1 Water Coolant Systems Specification (s)
The following measurements shall monitor the reactor coolant conditions:
The pool temperature channel shall have a channel check annually, a.
b.
The pool water depth shall have a channel check monthly.
The water conductivity channel shall have a channel calibration c.
annually and pool water conductivity will be measured weekly, d.
The pressure difference channel shall have a channel test prior to each days operation, after repair or modifications, or prior to each extended period of operation of the heat exchanger and will be continuously monitored during operation, Measure pool water pH with low lon test paper or equivalent quarterly.
e.
Sample pool water radioactivity quarterly for total alpha-beta activity.
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Revision 6/90 Technical Specifications l
4.3.2 Air Confinement Systems Specification (s)
Not Applicable 4.3.3 Radiation Monitoring Systems Specification (s)
The following conditions shall apply to radiation monitoring systems Calibrate particulate air monitor at semiannual intervals and check a.
operability weekly, b.
Calibrate area radiation monitors at semiannual intervals and check operability weekly.
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Mvision 6/90 Technical Spselfications 5.0 DESIGN TEATURES 5.1 sit. anet raeliity_ nemerletion i
5.1.1 Location Specification (s)
The site location is on the main campus o's The University of Texas at a.
Austin.
b.
The TRIGA reactor is installed in a designated room, room 131, of a building constructed as an engineering laboratory and classroom building, Taylor Hall.
The reactor core is assembled in a below ground shield and pool c.
structure with vertical = access to the core.
d.
License areas of the facility for-reactor operation shall consist of the room enclosing the reactor shield and pool structure, (room 131 and' room 131a).
5.1.2 Confinement i
specification (s)-
The_ reactor room shall be designed to restrict leakage and will have a a.
minimum enclosed air volume of 680 cubic meters, b.
Ventilation system shall circulate air within the room and shall isolato air in the reactor area upon shut off of the circulation f an.
5.1.3 Safety Related Systems Specifications Any modifications to the air confinement or ventilation system, the reactor shield, the pool or its penetrations, the pool coolant system, the core and its associated support-structure, the rod drive mechanisms or the reactor safety rystem shall be made and tested in accordance with the specifications to which.i.to systems were originally designed and f abricated.
Alternate specifications may be approved by the Nuclear Reactor Committee. A system i
l-shall not be considered operable until af ter it is tested successfully l
5.2 Reacter coolant svntam 5.2.1 Natural Convection Specification (s) l The reactor core shall_be cooled by natural convection flow of water.
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e' Ravision 6/90 Technical $pacifications t
5.2.2 Siphon Protection Specification (s)
Pool water level shall be protected by holes for siphon breaks in pool water system pipe lines.
5.3 Reacter core and runi 5.3.1 ruel Elements Specification (s)
The standard TP!UA fuel element at f abrication shall have the following characteristics:
J a.
Uranius content: 8.5 wtl uranium enriched to a nominal 19.7% Uranium-235.
b.
Zircottium hydride atom ratio: nominal 1.6 hydrogen to zirconium, ErH.
c.
Cladding: 304 stainless steel, nominal.020 inches thick.
5.3.2 control Roda j
- Specification (s)
The shim, regulating, and transient control rods shall have scram capability, and Include stainless steel or aluminum clad and may be followed by air or a.
aluminum, or for a standard rod may be followed by fuel with stain 1::s steel
- clad, b.
Contain borated graphite, B C powder, or boron and its compounds in 4
solid form as a poison, 1
i The transient rod shall have an adjustable limit to allow a variation c.
of reactivity insertions.
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R vision 6/90 Tochnical specificottons 5.3.3 configuration Specification (s)
The reactor shall be an arrangement of core single grid positions occupied by fuel elements, control rods, and graphite elements.
Single element j
positions may be occupied by voide, water or experiment facilities.
Special single element positions msy be occupied by approved experiments.
5.4 Reactor ruel Plement storagg Specification (s)
All fuel elements shall be stored in a geometrical array where the a.
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 valuer.
5.5 Reactor Pool Irradiator Specification (s)-
- a. A 1,000 Curie gamma irradiator may be located in the reactor pool.
The irradiator isotope will be cobalt-60.
Pool water sample requirements will enonitor pool water for source leakage.
4
- b. The irradiator assembly will be an experiment facility.
Location of the assembly will be at a depth of at least 2.0 meters and at a distance of at least 0.5 meters from the reactor core structure.
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i R3 vision 6/90 Technical Spacifications
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6.0 ADMINISTP.ATIVE CONTROLS 6.1 QIsanisation 6.1.1 Structure The facility shall be under the contrsl of the Director or a supervisory Senior Reactor Operator.
The management for operation of the facility shall consist of the organizational structure established as follows:
President of The University of Texas at Austin i
Executive Vice President and Provost
................. 1evel 1 Radiation l Dean College of Engineerino l Nuclear Reactor Safety Committee Committee Radiation Safety Offleer i
1 g
Chairman Department of Mechanical Enoineering i
1 I
Director Nuclear Engineering Teaching Laboratory
.................. level 2 l
Reactor Supervisor l
l Health Physicist l
.................. level 3 Reactor Operators, Technielans, others
.................. level 4 Responsibility ---
Communication 6/90 Page 20 j
R3vasion 6/90 Technical Specifications 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 a supervisory Senior Reactor operator shall review and approve all experiments and experimental procedures prior to their use in the Individuals of the management organization shall be responsible reactor.
for the policies and operation of the facility, and shall be responsible for safeguarding the public and facility personnel from undue radiation exposures and for adhering to the operating license and technical specifications.
6.1.3 staffing The minimum staffing when the reactor is not shutdown shall be:
a.
A certified operator in the control room.
b.
A second person in the facility area that can perform prescribed written instructions. Unexpected absence for two hours shall require immediate action to obtain an alternate person.
A senior reactor operator readily available.
The available operator c.
should be within thirty minutes of the facility and reachable by telephone.
Events requiring the direction of a senior reactor operater shall be:
All fuel element or control rod relocations within the reactor core a.
region, if the core grid structure capacity exceeds two full rings, b.
Relocation of any experiment with a reactivity worth of greater than one dollar.
A list of reactor fscility personnel by name and telephone 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.
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Rovision 6/ft Technical specifications 6.1,4 Selection and Training of *ersonnel 4
The selection, training and tequilfication of operators shall rneet or er.ceed the requirements of American National Standard for S33iction and 2
Training of Personnel for Research Reactors ANSI /AN1 - 15.4.-
Qualification ant requalification of cert,1fied operators shall be subject to en approved NPC (Nuclear Regulatory Comission) program.
6.2 agel.w a w Au m 6.2.1 Composition and Qualifications A Nuclerir-Reactor Corinittee shall consist of at least three (31 members appointed by the Dean of the College of Engineering that are knowledgeable in fielde which relate to nuclear safety. The University Radiological Safety Officer shall be a member or an ex-officio member of the Nuclear Reactor Comittee.
The committee will perf >rm the f unctions of review and audit or designate a knowledgaable person for audit functions.
6.2.2 Charter and Rules
'The operations of the Nuclear Reactor Committee shall b? in eccordance with an established charter, including provisions fort Meeting f requency (at least once each six months).
a.
P b.
Quorunn:(not less than one-half the membership where the operating staf f does not represent a majority).
.c.
Dissemination, review, and approval of minutes, i
d.-
Use of subgroups.
j 6.2.3 Review rune'. son 11 The review funccion thril include facility operations related to reactor and radiological safety.
The following items shall be reviewedt Determinations that proposed chrnges in equipment, systems, rests,
-a.
experiments, _or-procedures do not involve an unreviewed safety question.
b.
All new precedures and major revisionJ thereto, and proposed changes in reactor f acility equipment or syst ems having safety significance.
All now experiments or classes of experimunts that could affect c.'
reactivity _or result in the release of radioactivity.
d.
Changes in technical specificaticns or license.
Violations of technical specifications or license.
e.
f.
Operating abnormalities or violatione of procedores having safety significance.:
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R3 vision 6/90 Technical Specifications t
g.
Other reportable occuriences.
h.
Audit reporta.
6.2.4 Audit runction The audit function shall be a selected ext mination of operating records, logs, or other documents. An audit will be by a person not directly responsible for the records and may include diceussions with cognizant personnel or observation of operations.
The following items shall be audited and a report made within 3 months to the Direc*,or and Nuclear Reactor Conedttee t l
a.
C. nfor nance of f acility operations with license eSd technical specificatlocs at least once each calendar year.
I b.
Result 1 ot actions to correct deficiencies that may occur in reactor i
facility equeomei.5 s.ructures, systems, or methods of operation that affect safety at i'a-: Lace per calendar year, c.
Function of t,( retraining and requalification program for certified operators at leust nce Svery other calendar year.
d, reactor i cility emergency plan and physical seev-ity plan, and in; ng proccJures at least once every other year.
6.3 Doerating precedurea Wiltten oporating procedures shall be prepared reviewed and appt4Dal by the Director or a gly tvisory Senior Reactor Operator and the Nuclear 7(*ctor Committee pr,ot to J'dtiation of the following activities:
l a
Ltartup, ut iratis s and shutdown of the reactor.
b.
Fuel loading, un7e iding and movenent in the reactor, Routine maintenMace of major components of systems that could have an o
c.
f offect on reactor saf'aty.
d.
Surveillancs calibrations and tests required by the technical specifications or those that could have en effect on reactor safety.
i
(
AdmQf$1(ra,(ve controls for operation maintenance, and the conduct of
. e.
experiments or 3raediations that could have an effect on reactor safety, f.
Personnel radiat on protection consistent with appilcable regulations i
or guldelines shall incaide a man (gement commitment and programs to l
- maititeln exposures and reicates at low as reasonably achievable.
g.
Implementation of regofrai plans such as the emergency plan or physic.s1 security plan.
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- 1 L-R3 vision 6/90 Tochnical-Sp3cifications
' Substantive. changes to the above procedures shall be made effective after approval by the Director or a supervisory Senior Reactor Operator and the Nuclear Reactor Committee. _ Minor modifications to the original procedures which do not change the original intent may be made by a senior reactor operator but the_nodifications.must be approved by the Director.or a supervisory Senior _ Reactor Operator. Temporary deviations from the.
procedures may be made by a senior reactor operator in order to deal with special or unusual circumstances or conditions.
Such deviations shall be documented and reported to the Director or a supervisory Senior Reactor Operator.
6.4 Experlmant Review and A_7ereval Not Applicable 6.5 Reguired Actions i
6.5.1 Action to be Taken in Case of a Safety Lindt Violation In the event of a safety Almit violation, the following action shall be takent The reactor shall be bl.ut down and reactor operation shall not be n.
4esumed until a report of the violation is prepared and authoriration by the Nuclear Regulatory Commission (NRC) is issued, b.
The safety limit violation shall be promptly reported to the Director of the facility or a designated alternate.
The safety limit violation shall be subsequently reported to the NRC.
c.
d.
A safety limit violation report shall be prepared and submitted to the Nuclear Reactor Cotandttee.
The report shall describet (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 teken to prevent recurrence, l
6.5.2 Action to be Taken in the Event of an occurrence that is Reportable.
In the event of a reporta51e occurrence, the following action shall be takent l
Reactor conditions shall be returned to normal or the reactor a.
shutdown.
If it is necessary to shut down the reactor to correct the occurrence, operations shall not be resumed unless authorized by the Director or his designated alternate.
l b.
Occurrence shall be reported to the Director or his designated alternate and to the Nuclear. Regulatory Commission as required.
1 Occurrence shall be rtviewed by the Nuclear Roactor Consdttee at the c.
next regularly scheduled meeting.
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Rsvision 6/90-Technical Specifications 6.6 Renerts 2
A'l written :eports shall be sent within the prescribed interval to the NKt, Msshlagton D.C. 20555, Atten: Document Control Desk, with a copy to the Regional Administrator, Region. IV.
6.6.1 operating Reports Routine annual reports covering the activities of the reactor facility i
during the previcus calendar year shall be submitted within three months following the end of each prescribed year.
Each annual operating report shall include the following information:
A narrative summary of reactor operating experience including the a.
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, Tabulation of major preventive and corrective maintenance operations c.
having safety significance.
d.
Tabulation of major changes in the reactor facility and procedures, and tabulation of new tests or experiments, or both, that are significantly different from those performed previously, inclucing conclusions that no unreviewed. safety questions were involved, s
A summary of the nature and amount of radioactive effluents released e.
or discharged to the environs beyond the effective control of the university as determined at or before the point of such release or discharge. 'The summary shall include to the extent practicable an estimate of individual radionuclides 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.
L f.
A summary of exposures received by facility personnel and visitors l
where such exposures are greater than 25% of that allowed or recommended, i-g.
A summarized result of environmental surveys performed outside the facility.
6.6.2 Special Reports A written report within 30 days to the NRC of:
Permanent changes in the facility organiration involving Director or a.
Supervisor, b.
Significant changes in transient or accident analysis as described in the Safety Analysis Report.
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akn6/90 Technical-Spacifications i to NRC Oporation Center and Eegion IV by telephone not later than t
- s11owing working day and confirmed in writing by telegraph or similar eyance to be followed by a written report within 14 days that doseribes
,ne circumstances of the event of any of the following Violation of fuel element temperature safety limit.
a.
'b.
Release of radioactivity above allowable limits.
c.
Other reportable occurrences.
Other events that will be considered reportable events are listed in t.11a section. A return to normal operation or curtailed operatic.: until authorized by management will occur.
(Note: Whcre compor.ents 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.)
Operation with actual safety-system settings for required systems a.
'less conservative than the lindting safety system settings specified in t.he technical specifications.
b.
Operation in violation of limiting conditions for operation established in technical specifications unless prompt remedial action is taken.
A reactor safety system component malfunction which renders or could c.
render the reactor safety system incapable of performing its intended safety function unless_the malfunction or condition is discovered during maintenance tests or periods of reactor shutdowns, d.
An unanticipated or uncontrolled change in reactivity greater than it one. dollar. Reactor trips resulting from a known cause are excluded, Abnormal and significant degradation in reactor fuel, or cladding, or e.
both, coolant boundary, or confinement boundary (excluding _ minor leaks) where applicable which could result in exceeding prescribed radiation exposure-limits of personnel or environment, or both, f.
An observed inadequacy in the implementation of administrative or procedural. controls such that-the inadequacy causes or could have ca; sed the existence or development of an unsafe condition with regard to recctor operations.
A written report within 90 days after the initial criticality or 9 months after license issuance, which ever is earlier, of the startup test program, L
to the NRC of:
I Characteristics upon receipt of a new facility license, of the reactor under the new conditions, describing the measured values of the operating conditions including:
6/90 Page 26 l'
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R3 vision 6/90 Technical Spselfications Total control reactivity worth and reactivity of the rod of highest c.
reactivity' worth, b.
Minimum shutdown margin of the reactor both at ambient and operating temperatures.
An evaluation of facility performance to date in comparison with c.
design conditions and measured operating characteristics, and a reassessment of the safety analysis when measurements indicate that there may be substantial variance f rom prior analysia' submitted with the license application.
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 inf ormation, may be used as records in this section.)
Gaseous and 11guld radioactive ef fluents released to the environs, a.
b.
Offsite environmental monitoring surveys required by technical specifications.
Events that impact or etr6ct decommissiong of the facility c.
d.
Radiation _ exposure for all personnel monitored.
Updated drawings of the reactor facility.
e.
6.7.2 Records to be Retained for a Period of at Liast Five Years or for the Life of the Component Involved Whichever is Shorter:
Normal reactor f acility operation (supporting docunents such as a.
checklists, log sheets, etc. shall be maintained for a period of at least one year).
- b. -
Principal maintenance operations, c.
' Reportable occurrences.
d.--
Surveillance activities required by technical-specifications, Reactor facility radiation and contamination surveys where required e.
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 Licensing Cycle:
Retraining and requalifications of licensed operations personnel.
Records
-of the most recent complete cycle shall be maintained at all times the individual is employed.
6/90 Page 27 u,
Rsvision 6/90 Technical Spacifications-APPENDIX A.1.0 DOCKET 50-602 INFORMATION The Tech'nical Specifications of this document depend on the analysis and conclusions of the Safety Analysis Report.
Descriptive information important to each specification is presented in the form of the applicability, objective and bases.
This information defines the conditions effective for each technical specification, except administrative conditions, for the Docket 50-602 f acilty.
A.1.1 Apolleablilty The applicability defines the conditions,' parameters, or equipment to which
-the specification applies.
A.1.2 Ob4ective The objective defines the goals of the specification in terms cf limits, frequency, or other controllable item.
'A.1.3 Ranta The bases presents information important to the specification, including such things as justification,' logical constraints and development methodology.
A.2.0 SAFETY LIMITS = & ' LIMITING SAFETY SYSTEM SETTINGS APPLICABILITY, OBJECTIVES AND BASES A.2.1 safety'tAmit Applicability This specification applies to the temperature of the reactor fuel in a standard TRIGA fuel element.
. Objective The objective is to define the maximum temperature that can.be permitted with confidence that no damage to the fuel element cladding will result.
6/90 Page 28
Revision 6/90 Technical Specifications Bases The important parameter for a TRIGA reactor is the fuel element temperature.
This parameter is well suited as a single specification since it can be neasured directly.
A loss in the integrity of the fuel element cladding could arise f rom a build-up of excessive pressure between the fuel-moderator and the cladding if the fuel temperature exceeds the safety limit.
The pressure is caused by the presence of air, fission product gases, and hydrogen trom 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 zirconium in the alloy.
The safety limit for the standard TRIGA fuel is based on calculations and experimental evidence.
The results indicate that the stress in the cladding due to hydregen pressure from the dissociation of zirconium hydride will remain below the ultimate stress provided that the_ temperature of the fuel does not exceed ll50*C and the f uel cladding does. net exceed 50 0*C.
For conditions that might cause the clad temperatures to exceed 500*C the safety lindt of the fuel should be set at 9 5 0*C.
A.2.2 Limiting Safety Syatem Setting A.2.2.1 ruel 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.
7ases For non pulse operation of the reactor,. the limiting safety system setting is a temperature which, if_ exceeded, shall cause a reactor scram to be initiated preventing the safety limit-f rom being exceeded. A setting of 550*C provides a safety margin at the point of measurement of at least 400'C for standard TRIGA fuel elements in any condition of operation.
'A part of the safety margin is used to account for the difference between the true and measured temperatures resulting from the actual location of the thermocouple._ If the thermocouple element-is located in the hottest p
position in the core, the difference between the true and measured temperatures will be on'ly a few degrees since the thermocouple junction is near the center and-the mid plane of the fuel element.
For pulse operation
-of the reactor, the same limiting safety system setting will apply.
However, the temperature channel will have no effect on limiting the peak powers generated because of its relatively long time constant (seconds) as compared with the width of the pulse (milliseconds).
(
6/90 Page 29
R3 vision 6/90 Technical Sps ifications In this mode, however, the temperature trip will act to lindt the energy release after the pulse if the transient rod should not reinsert and the fuel temperature continues to increase.
A critical core configuration will not be present in the reactor grid structure. Without the capability to generate power in the fuel elements, a safety lindt on temperature, power level or reactivity is not necessary.
Instead, a limit on the number of elements in the reactor grid structure will assure that a critical configuration does not exist.
Filling any two rings of the -grid structure s111 not create a co'nfiguartion with K > or 8.
A. 3. 0 LIMITING CONDITIONS FOR OPERATION APPLICABILITY, OBJECTIVES & BASES A.3.1 Reactor Core Parametern A.3.1.1 Reactivity Applicability This specification applies to the. reactivity condition of the reactor core in terms of the available excess above the cold xenon free, critical condition.
Objective The objective is to prevent the fuel element temperature safety limit f rom being reached by limiting the. potential reactivity available in the reactor for any condition of operation.
Bases
.The reactor core is no longer available for operation.
By limiting the number and location of elements in the grid structure the shutdown margin and excess reactivity are no longer functional constraints.
Excess reactivity is zero and the shutdown margin exceeds those applicable to any operable configuration.
A.3.1.2 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.
6/90 Page 30 l-.
R3 vision 6/90 Technical Specifications Bases The-elongation limit has been specified to assure that the cladding material will not be subjected to stresses that could cause a loss of integrity in the fuel containment and to assure adequate coolant flow.
The limit of transverse bend has 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 demage 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. Measurement of element physical-dimensions are requirments for elements subject the heat load conditions as a result if operation at power.
If no power is being produced by an element physical inspections for indiations of corrosion are more significant than dimensional checks.
Dimensional checks are to be done prior to operation of the element in an operable core.
A.3.2' Reactor control and safetv Svstem Not Applicable.
A.3.2.3 Reactor Safety System Not Applicable A.3.2.4 Reactor Instrument System g Not Applicable A.3.3 Operatinnal supne rt system A.3.3.1 Water Coolant Systems Applicability This specification applies to the operating conditions for the reactor pool and coolant water systems.
Objective The objective is to assure that adequate conditions are maintained to provide shielding of the reactor radiation, protection against corrosion of the reactor components, cooling of the reactor fuel, and prevent leakage from the primary coolant.
[
Bases 1
The specifications for conditions of the pool water coolant system provide L
controls that are to control the radiation exposures and radioactive releases associated with the reactor fission product inventory.
The bulk water temperature constrain *. assures that sufficient core a.
cooling exists under_all anticipated operating conditions and protects the resin of the water purification system from deterioration.
6/90 Page 31 l
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LRavision 6/90 Technical Specificctions s
b.
A pool water depth of 6.5 meters is sufficient to provide more than 5.25 neters.of water above the reactor core so that radiation levels above the reactor pool are at reasonable levels.
Average measurements of pool coolant water conductivity of 5.0 c.
kmho/cm assure.that water purity is maintained 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 te the secondary chilling water system in the event of a leak.in the heat exchanger, Periodic sampling of pool water pH and radioactivity are supplemental e.
measurements'that assist. evaluation of the overall conditions of the reactor' pool.
Protection of aluminum components requires a pH range of 5 to 8.5..Heasurements of radioactivity in the pool water provide information to evaluate working hazards for personnel, leakage indications
'for radioactive. sources in the pool, and monitoring-for activation of unknown components in the water.
A.3.3.2 Air confinement Systems Not Applicable A.3.3.3 Radiation Monitoring Systems 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 reactor area to control exposures or releases.
Bases The radiation monitors provide information to operating personnel of impending or existing hazards from radiation so that there will be sufficient time to take the necessary steps to control the exposure of personnel _and release of radioactivity or evacuate the facility.
Alarm
-setpoints do not-include measurement uncertainty.
These setpoints are measured values are not'true. values Air particulate radioactivity accumulates on the filter of a-a.
continuous monitor that records the radiation levels An alert and alarm set point including remote readouts at the reactor control console inform the operator of the monitor status and activity levels.
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R3 vision 6/90 Technical Sp3cifications
~
Air flow rates provida detection capability of one a4xi'.um permissible concentration at one hour by accumulation of particulates'by the filter.
b.
Several area radiation monitors (six) are part of the permanent installation.
Some locations are experiment areas in which shield configurations determine the levelslof radiation during reactor operation.
At the pool access area radiation levels substantial enough to be a high radiation level may occur.
Alarm levels at 100 mr/hr will monitor radiation areas if the lindt of 2 or 5 mr/hr is not reasonable.
'A.3.4 Limitationn on Erneriments A.3.4.1 Reactivity Not Applicable A.4.0 SURVEILLANCE REQUIREMENTS OBJECTIVES.s BASES A.4.1 Reactor core Parameters A.4.1.1 Reactivity Applicability.
This specification applies to the measurement of reactor excess reactivity.
Objective The objective is to periodically determine that no core excess reactivity exists.
Bases Monthly. checks of the placement of elements in the grid structure will periodically verify the shutdown condition of the reactor core.
A.4.1.2 Fuel Elements Applicability.
F This specification applies to the inspection requiremencs for the 'uel elements.
Objective The objective is to inspect the physical condition of the fuel element cladding.
6/90 Page 33
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' Revision 6/90 Technical Spacifications i
Bases l
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 utillaing f uel elements whose.
characteristics are well known.
No use of the_ fuel to produce power or heat energy does not introduce any condition that would cause damage to the fuel unless physical movement or chemical condi.tions of the storage environment. change.
A.4.2 Egacter Control and safety svntem Not Applicable A.4.2.3 Reactor Safety System Not' Applicable A.4.3 coerationni support' systema A.4.3.1 Water Coolant Systems Applicability This specification. applies to surveillance conditions for the reactor pool and coolant water systems..
Objective The objective is to maintain the reactor coolant conditions within acceptable specifications.
Bases Conditions for the reactor coolant are monitored by visual observation of measurements or automatic action of sensors.
Periodic checks and tests of measurement devices for the reactor coolant system parameters assure that the coolant system will perform its intended function.
Measurement l
frequencies of pool parameters relate to the time periods appropriate to detection of abnormal conditions.
Pool temperature, depth, and heat exchanger pressure differences have an immediate effect on system operation.- Water-conductivity, pH as a supplemental indicator, and pool l
radioactive concentrations are conditions that develop at rates detectable l
at monthly-to-annual intervals, l-l A.4.3.2 Air Confinement Systems-l Not Applicable 6/90 Page 34 l-
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Rsvision:6/90, Technical Spacifications p
A.4.3.3_ Radiation Monitoring Systems Applicability This specification applies to the surveillance conditions of the radiation-monitoring channels.
Objective r
The objective is to assure the radiation' monitors are functional.
Bases Periodic calibrations and frequent checks are specified to maintain reliable performanceaof the radiation monitoring instruments.
Calibration.
and check frequencies follow the general recommendations of guidance documents.
A.4.4 Limitatiena en Experiment s Not Applicable A.S.O DESIGN' FEATURES OBJECTIVES'& BASES
-A.5.1 site and racility neseriptions A.5.1.1 Location Applicability
'This specification applies to the TRIGA reactor site location and specific facility design features.
Objective The objective is to specify those-features related to the Safety Analysis
' evaluation.
Bases.
The TRIGA facility site is located in an-area controlled by The a.-
. University of Texas at Austin.-
l
.The room enclosing the reactor has been designed with characteristics L
b.
-related to the safe operation of the facility.
E
.c.
-The shield and-pool structure have been designed to.contain the L
reactor structure in a below ground level pool.-
l d.
The resticted access to specific facility areas assure-that proper L
controls are established for the safety of the public and for the security of special nuclear materials.
6/90 Page 35 t
R3 vision 6/90l Technical Sp3cifications A.5.1.2 Confinement Applicability This specification applies to the boundary for control of air in the area of the reactor.
Objective The objective'is to assure that provisions are.made to control or restrict the amount of release of radioactivity into the environment.
Bases-a.
Calculations of the concentrations of released radionuclides within
-the reactor crea depend on the available enclosed air volume to limit the concentrations to acceptable levels.
b.
Control of the reactor area air axchange to adjacent areas is by.
leakage at doors.and building joints.
Control of the ventilation fan stops the air flow within the room.
A.5.1.3 Safety Related Systems
~ Applicability This specification applies to the requirements of any system related to j
reactor safety.
Objective The. objective is to assure the proper function of any system related to reactor safety.
Bases =
This specification relates to changes in reactor systems which could affect
- the safety of the reactor operation. Changes or-substitutions to these systems that meet'or exceed the-original design specifications are. assumed to meet the presently accepted operating criteria.
Questions that may include an unreviewed safety question are referred to the reactor operation committee..
A.5.2 Enneter coolant qvnt em.
Applicability.
This specification applies to the reactor coolant system composed of delonized water, d
4 6/90 Page 36 4
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R3 vision 6/90 Technical specificationo 4
Objective The objective is to assure that adequate water is available for cooling and shielding during reactor operation.
Bases This specification is based on thermal and hydraulic calculations a.
which show that a standard TRIGA core can operate in a safe manner at power levels exceeding 1500 kW with natural convection flow of the coolant water and a departure from nucleate boiling ratio of 2.0.
b.
Siphon. breaks set the subsequent pool water level for loss of coolant without an associated water return caused by inadvertant pumping or accidental siphon of water from the pool.
h,$,3 Egatter Core and ruel A.S.3.1 Fuel Elements i
Applicability This apecification 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 f abricated in such a manner as to permit their use with a high degree of reliability with respect to their physical and nuclear characteristics.
Bases The' design basis of the standard TRIGA core demonstrates that 1 5 meg steady or 36 megawatt-see pulse operation presents a conservative limitation with respect to safety limits for the maximum temperature generated in the fuel.
can occur without an operable core.No significant fuel temperature greater than 101C C
A.S.3.2 Control Rods Applicability This specification applies to the control rods used in the reactor core.
Objective The objective is ta assure that the control rods are of such physical and nuclear characteristics. permit their use with a high degr a design as to er 6/90 Page 37
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Rovision 6/90 Technical Specifications-
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Bases The_ poison 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 in a suitable clad material, such as aluminum or stainless steel, to-insure mechanical stability during movement and to isolate the poison from the pool water environment.
Scram capabilities are provided for rapid insertion of the control rods which is the pr. mary safety feature-of the reactor. -The transient control rod is designed for a reactor pulse.
A.S.3.3 Configuration Applicability This specification applies to the configuration of fuel elements, control' rods, experiments and other reactor grid plate components.
i Objective The objective: Is to assure that provisions.are made to restrict the arrangement of fuel elements and experiments to provide assurance that excessive power densities will not be produced.
Bases Standard TRIGA ' cores have been in use for years and their characteristics are well documented.
A.S.4 Reacter Fuel Element storace Applicability This specification applies to the storage of reactor fuel at times when it is not in the reactor core.
Objective i
t The. objective is to assure that fuel storage will not achieve criticality.
l-and wil1~not exceed design temperatures, l'
Bases The ~11pdts imposed by these specifications are consicered-sufficient to provide conservative fuel' storage and assure safe storage, i
l l-l 1
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Revision 6/90 Technical Specifications i,
A.5.5 Gamma Pool irradiator l
l Applicability i
This specification applies to the gamma irradiator experiment facility in the reactor pool.
Objective The objective is to assure that the use of the l'rzadiator does not cause any threat to the reactor or safety question.
Bases Location of the irradiator is at a distance from the reactor sufficient to avoid interference with reactor operation. Depth of the pool water for adequate shielding of the irradiator is also a constraint of the location A.6.0 NOTES This section is blank 6/90 Page 39
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