ML12031A170

Transmittal of University of California, Irvine, Technical Specifications for the Triga Mark I Nuclear Reactor

ML12031A170
Person / Time
Site:	University of California - Irvine
Issue date:	01/12/2012
From:	Geoffrey Miller University of California - Irvine
To:	Lising A, Meyer W Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML12031A170 (40)

Text

UNIVERSITY OF CALIFORNIA, IRVINE BERKELEY - DAVIS

• IRVINE - LOSANGELES - RIVERSIDE - SANDIEGO

• SAN FRANCISCO SANTA BARBARA

• SANTACRIUZ George E. Miller IRVINE, CA 92697-2025 Senior Lecturer Emeritus (949) 824-6649 or 824-6082 Department of Chemistry and FAX: (949) 824-8571 Director,Nuclear Reactor Facility email : gemiller@uci.edu FacultyAdvisorfor Science, UCI Centerfor Education Partnerships January 12, 2012 US Nuclear Regulatory Commission Document Control Desk Washington DC 20555 Attention:

Walter Meyer, Senior Project Manager

Jason Lising, Senior Project Manager Re: Docket 50-326 R-116 Relicense

Dear Mr Meyer and Mr Lising:

Please find enclosed a refined Technical Specifications for the facility in response to suggestions recently discussed.

I declare under penalty of perjury that the foregoing and the attached are true and correct to my knowledge.

Executed on January 1 2 th 2012 Dr. George E. Miller

1. 2'D

APPENDIX A To Facility License R-1 16 Docket 50-326 Technical Specifications for the U. C. Irvine TRIGA Mark I Nuclear Reactor January 2012

TABLE OF CONTENTS DEFINITIONS 1 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 Safety Limit - Fuel Element Temperature 5 2.2 Limiting Safety System Setting 5 LIMITING CONDITIONS FOR OPERATION 3.1 Reactor Core Parameters 6 3.2 Reactor Control and Satlety Systems 9 3.3 Coolant Systems 12 3.4 Confinement (blank) 14 3.5 Ventilation Systems 14 3.6 Emergency Power 15 3.7 Radiation Monitoring Systems and Effluents 16 3.8 Limitations on Experiments 17 3.9 Facility-specific Requirements following extended Shutdown (blank). 17 SURVEILLANCE REQUIREMENTS 4.0 General 19 4.1 Reactor Core Parameters 19 4.2 Reactor Control and Safety System 20 4.3 Reactor Pool Water 21 4.4 Containment or Confinement (blank) 22 4.5 Ventilation Systems 22 4.6 Emergency Power 23 4.7 Radiation Monitoring Systems and Effluents 23 4.8 Experiment Limits 24 DESIGN FEATURES 5.1 Site and Facility Description 25 5.2 Reactor Coolant System 25 5.3 Reactor Core and Fuel 26 5.4 Fuel Storage 27 5.5 Ventilation System 28 ADMINISTRATIVE CONTROLS 6.1 Organization and Structure 29 6.2 Review and Audit 31 6.3 Radiation Safety 33 6.4 Operating Procedures 33 6.5 Experiment Review and Approval 34 6.6 Required Actions 34 6.7 Reports 35 6.8 Records 37

1. DEFINITIONS The following frequently used terms are defined to aid in the uniform interpretation of these specifications.

AUDIT An examination of records, logs, procedures, or other documents to ascertain that appropriate specifications and guidelines are being followed in practice. An audit report is written to detail findings and make recommendations.

CHANNEL A combination of sensor, lines, amplifier and output device which are connected for the purpose ofl measuring the value of a parameter.

CHANNEL CALIBRATION An adjustment of the channel such that its output corresponds with acceptable accuracy to known values of the parameter that the channel measures. Calibration shall include equipment actuation, alarm or trip, and shall be deemed to include a CHANNEL TEST.

CHANNEL CHECK A qualitative verification of acceptable performance by observation of channel behavior. This verification, where possible, shall include comparison of the channel with other independent channels or systems measuring the same variable.

CHANNEL TEST An introduction of a signal into the channel to verify that it is operable.

CLOSE-PACKED ARRAY is a fuel loading pattern in which the fuel elements are arranged in the core by filling the inner rings first.

CONFINEMENT is the enclosure of the overall facility designed to limit release of effluents between the enclosure and the external environment through controlled or defined pathways.

CONTROL ROD is a device fabricated from neutron absorbing material or fuel or both which is used to establish neutron flux changes and to compensate for routine reactivity changes. A control rod may be coupled to its drive unit allowing it to perform a safety function when the coupling is disengaged. Types of control rods shall include:

a. Regulating (REG): a rod having electric motor drive and scram capabilities. Its position may be varied manually or by an electronic controller. It shall have a fueled-follower section.

b. Shim (SHIM): a rod having electric motor drive and scram capabilities. Its position shall be varied manually. It shall have a fueled-follower section.

c. Adjustable Transient (ATR): a rod with scram capabilities that can be rapidly ejected from the reactor core to produce a pulse. It has an electric motor drive to adjust its position or length of travel. It shall have a void follower.

d. Fast Transient (FTR): a rod with scram capabilities that can be rapidly ejected from the reactor core to produce a pulse. It shall have a void follower.

CORE CONFIGURATION describes a particular arrangement of fuel, control rods, graphite reflector elements, and experimental facilities inserted within the core grid plates.

CORE LATTICE POSITION is defined by a particular hole in the top grid plate of the core designed to hold a standard fuel element. It is specified by a letter, indicating the specific ring in the grid plate and a number indicating a particular position within that ring.

UCI Technical Specifications page I

EXCESS REACTIVITY is that amount of reactivity that would exist if all control rods were moved to the maximum reactive condition from the point where the reactor is exactly critical (ket-= I) at reference core conditions.

EXPERIMENT is any operation, hardware or target (excluding devices such as detectors or foils) which is designed to investigate non-routine reactor characteristics or which is intended for irradiation within an irradiation facility. Hardware rigidly secured to a core or shield structure so as to be part of their design to carry out experiments is not normally considered an experiment.

Specific experiments shall include:

a. SECURED EXPERIMENT is any experiment or component of an experiment that is held in a stationary position relative to the reactor by mechanical means. The restraining forces 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 malfunctions.

b. UNSECURED EXPERIMENT is any experiment or component of an experiment that does not meet the definition of a secured experiment.

c. MOVEABLE EXPERIMENT is any experiment where it is intended that the entire experiment may be moved in or near the core or into or out of the core while the reactor is operating.

FUEL ELEMENT is a single TRIGA fuel rod.

INITIAL STARTUP is the first start-up from reactor secured condition on any day when the reactor is to be operated in order to verify core excess and other instrument parameters before operation during the day at a steady-state power level above I kilowatt, or by pulsing the reactor.

INSTRUMENTED FUEL ELEMENT is an element in which one or more thermocouples are embedded for the purpose of measuring fuel temperature during reactor operation.

IRRADIATION FACILITIES are pneumatic transfer systems, central tube, rotary specimen rack, and the in-core facilities (including single element positions, three-element positions, and the seven element position) and any other facilities in the tank designed to provide locations for neutron or gamma ray exposure of materials.

MEASURED VALUE is the value of a parameter as it appears on the output of a channel.

OPERABLE means a component or system is capable of performing its intended function.

OPERATING means a component or system is performing its intended function.

OPERATIONAL CORE means a CORE CONFIGURATION that meets all license requirements, including Technical Specifications.

PULSE MODE means any operation of the reactor with the mode switch in the PULSE position that satisfies all instrumentation and license requirements, including technical specifications, for pulse operation of the reactor.

UCI Technical Specifications page 2

REACTIVITY WORTH OF AN EXPERIMENT means the value of the reactivity change that results from the experiment being inserted into or removed from its intended position.

REACTOR FACILITY is the physical area defined by rooms B64, B64A, B54, B54A, and B54B in the service level of Rowland Hall on the campus of the University of California Irvine.

REACTOR OPERATING means any time at which the reactor is not secured or shutdown.

REACTOR SAFETY SYSTEMS are those systems, including their associated input channels, that are designed to initiate automatic reactor scram or to provide information for the manual initiation of a scram for the purpose of returning the reactor to a shutdown condition.

REACTOR SECURED. The reactor is secured when:

Either (1) There is insufficient moderator available in the reactor to attain criticality or there is insufficient fissile material present in the reactor to attain criticality under optimum available conditions of moderation and reflection; Or (2) The reactor is shutdown and all the following conditions exist:

(a) All neutron-absorbing control rods are fully inserted; (b) The console key switch is in the "off' position and the key is removed from the console lock; (c) No work is in progress involving core fuel, core structure, installed control rods, or control rod drives unless they are physically decoupled from the control rods; (d) No experiments are being moved or serviced that have a reactivity worth exceeding the maximum value allowed for a single experiment, or $1.00.

REACTOR SHUTDOWN. The reactor is shut down if it is subcritical by at least $1.00 in the reference core condition with the reactivity worth of all installed experiments included.

REFERENCE CORE CONDITION is when the core is at ambient temperature (cold) and the reactivity worth of xenon is negligible (less than $0.30).

REVIEW means a qualitative examination of AUDITS, reports and records, procedures or other documents from which appropriate recommendations for improvements are made.

RING means one of six concentric bands in the grid plate locations surrounding the central opening of the core. The rings are designated by the letters B through G, with the letter B used to designate the innermost band.

SAFETY CHANNEL means a measuring channel in the reactor safety system.

SCRAM TIME is the elapsed time between the initiation of a scram signal and a specified movement of a control or safety device.

SEVEN ELEMENT POSITION is a hexagonal section which can be removed from the upper grid plate for insertion of specimens up to 4.4 in. in diameter after relocation of all six B-ring elements and removal of the central tube irradiation facility.

UCI Technical Specifications page 3

SHALL, SHOULD and MAY. The word SHALL is used to denote a requirement; the word SHOULD is used to denote a recommendation; and the word MAY is used to denote permission, neither a requirement nor a recommendation.

SHUTDOWN MARGIN refers to the minimum shutdown reactivity necessary to provide confidence that the reactor can be made subcritical by means of the control and safety systems starting from any permissible operating condition and with the most reactive rod in its most reactive position, and will remain subcritical without further operator action.

STEADY-STATE MODE is whenever the reactor is OPERATING with the mode selector switch in the STEADY-STATE position.

SUBSTANTIVE CHANGES are changes in the original intent or safety significance of an action or event.

SURVEILLANCE INTERVALS that are permitted are established as follows:

a. quinquennial - interval not to exceed 6 years

b. biennial - interval not to exceed 2-1/2 years

c. annual - interval not to exceed 15 months

d. semi-annual - interval not to exceed 7-1/2 months

e. quarterly - interval not to exceed 4 months

1. monthly - interval not to exceed 6 weeks

g. daily - refers to each day when the reactor is to be operated or before any operation extending more than one day THREE ELEMENT POSITION is one of two triangular-shaped removable sections of the upper grid plate, one encompassing CORE LATTICE POSITIONS D5, E6 and E7 and the other D14, E18 and E 19, designed to accommodate experiments. When fuel elements are placed in these locations, a special fixture shall be inserted to provide lateral support.

UCI Technical Specifications page 4

2. SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 Safety Limit - Fuel Element Temperature Applicability. This specification applies to the fuel element temperature.

Objective. The objective is to define the maximum fuel element temperature that can be permitted with confidence that no fuel element cladding damage will result.

Specification. The temperature in a stainless steel clad, high hydride fuel element shall not exceed 1000IC under any condition of operation.

Basis. The important parameter for a TRIGA reactor is the fuel element temperature, since it can be measured. The loss in the integrity of the fuel element cladding could arise from an excessive build-up of pressure in the fuel element. The safety limit for high hydride TRIGA fuel is based on data including the experimental evidence obtained during high performance reactor tests of this fuel. These data indicate that the stress will remain below the ultimate stress provided the fuel temperature does not exceed 11 50'C and the fuel cladding is water cooled.

The safety limit for the stainless steel clad, high hydride (Zr/Hi. 7) fuel element is based on NRC accepted limits in NUREG 1537 section 14.1 which also indicates that the stress in the cladding due to the hydrogen pressure from the dissociation of the zirconium hydride will remain below the yield stress provided the temperature of the fuel does not exceed 1I50'C and the fuel cladding is water cooled.

2.2 Limiting Safety System Settings Applicability. This specification applies to the scram setting for the fuel element temperature channel.

Obiective. The objective is to prevent the safety limit from being reached.

Specifications. For a core composed entirely of stainless steel clad, high hydride fuel elements, a limiting safety system setting applies to the standard instrumented fuel element (IFE) which shall be located in the B- or C-ring as indicated in the following table:

Location Limiting Safety System Setting Core lattice positions B2, B4, C5, C6, or C7 425 0 C Basis. Fuel temperature is measured by a fuel element designed for this purpose (IFE) in a system designed to initiate a reactor scram if a limit is exceeded. The limiting setting is conservatively chosen for five possible core positions that calculations in the SAR, as supplemented by letter dated June 7"' 2011, indicate are similar in expressing the highest power density and thus the highest fuel temperatures attained in the core. In addition, the maximum recorded temperatures for the UCI reactor IFE for the period since 1969 are 250'C at steady state power operation, and 350'C for pulse operation. The LSSS is extremely conservative compared to the fuel temperature safety limit.

UCI Technical Specifications page 5

3. LIMITING CONDITIONS FOR OPERATION 3.1 Reactor Core Parameters 3.1.1 Steady-state Operation Applicability. This specification applies to the energy generated in the reactor during steady-state operation Obiective. The objective is to assure that the fuel temperature safety limit is not exceeded.

Specification. The reactor power level in steady-state operation shall not exceed 250 kilowatts.

Basis. Calculations have been performed which show that for operation at 250 kW, the maximum fuel temperature is 253 TC and the minimum DNB ratio is greater than 7.27. In addition, experience at other TRIGA reactors and thermal and hydraulic calculations for this core (SAR, as supplemented by letter dated June 7'1 2011) indicates that these power levels can be safely used with natural convection cooling of the fuel elements in the designed core configuration.

3.1.2 Shutdown Margin Applicability. These specifications apply to reactivity condition of the reactor and the reactivity worths of the control rods and experiments. They apply for all modes of operation.

Obiective. The objective is to assure that the reactor can be shut down at all times.

Specification. The reactor shall not be operated unless the following conditions exist The shutdown margin provided by the control rods shall be greater than $0.55 with:

irradiation facilities and experiments in place and the total worth of all unsecured experiments in their most reactive state; and

, the most reactive control rod fully withdrawn; and

. the reactor in the reference core condition.

Basis. The value of the shutdown margin and limits on experiments assure that the reactor can be shut down from any operating condition even if the most reactive control rod should remain in the fully-withdrawn position.

UCI Technical Specifications page 6

3.1.3 Core Excess Reactivity Applicability. These specifications apply to reactivity condition of the reactor and the reactivity worth of the control rods and experiments. They apply for all modes of operation.

Objective. The objective is to assure that the reactor can be shut down at all times and to assure that the fuel temperature safety limit shall not be exceeded.

Specification. The maximum available core excess reactivity based on the reference core condition shall not exceed $3.00.

Basis. An excess reactivity limit of $3.00 allows for flexibility in operating the reactor in steady state mode while limiting the reactivity addition for pulse operation. Computations presented in the SAR (Chapter 13.3) establish that a sudden insertion of $3.00 results in a fuel temperature of approximately 350 0 C, well below the established safety limit for this fuel (TS 2.1). Such calculations are conservative, using a purely adiabatic model. The specifications assure that no insertion of reactivity above this value is possible, even under non-normal operating conditions.

3.1.4 Pulse Mode Operation Applicability. These specifications apply to fuel temperatures generated in the reactor as a result of a pulse insertion of reactivity.

Objective. The objective is to assure that the fuel temperature safety limit shall not be exceeded.

Specifications. The reactor shall not be operated in the pulse mode unless, in addition to the other requirements of Section 3.1,

a. the steady-state power level of the reactor is less than 1 kilowatt; and

b. the total reactivity worth of the two transient control rods (ATR + FTR) is measured to not exceed $3.00.

Basis. The fuel temperature rise during a pulse transient has been calculated conservatively using an adiabatic model. Insertion with the power level below I kw assures that the starting temperature for a pulse rise is below 25'C. The temperature rise from a $3.00 reactivity insertion pulse is thus calculated to bring the peak fuel temperature to less than 400'C, well below the safety limit and well below the recommended maximum fuel temperature limit of 830'C. (GA Report, A16613, 1981.)

3.1.5 This section intentionally left blank.

UCI Technical Specifications page 7

3.1.6 Fuel Element Inspection Parameters Applicability. The specifications apply to all fuel elements, including fuel follower control rods.

Objective. The objective is to maintain integrity of fuel element cladding.

Specifications. The reactor shall not be operated with any fuel element identified to show damage.

An exception is made for operation up to a power level at which a leak becomes detectable solely in order to be able to identify the leaking element. A fuel element shall be identified as showing damage and be removed from core if:

a. the transverse bend exceeds 1/16"' inches (0.0625 in) over the length of the element; or

b. the growth in length over original measurements exceeds 1/8"' inch (0.125 in); or

c. a cladding defect is suspected by a finding of release of any fission products; or

d. visual inspection identifies unusual pitting, bulging, or corrosion.

Basis. These criteria are established by NRC 1537 section 14.1.

3.1.7 Core Configuration Applicability. This specification applies to the configuration of fuel and in-core experiments.

Objective. The objective is to assure that provisions are made to restrict the arrangement of fuel elements and experiments so as to provide assurance that excessive power densities will not be produced.

Specifications.

a. The core shall be an arrangement of TRIGA 8.5/20 LEU fuel.

b. The core fuel elements shall include at least one 8.5/20 LEU fuel element with embedded thermocouples to enable monitoring of fuel element temperature.

c. The core fuel elements shall be kept in a close-packed array except for control rods, single- or three-element or seven-element positions occupied by in-core experiments, irradiation facilities (including transfer system termini), and a central dry tube.

d. The reflector, excluding experiments and experimental facilities, shall be graphite or a combination of graphite and water.

e. A control rod shall not be manually removed from the core unless calculations show that the core will be subcritical excluding the worth of the rod being worked on and the worth of the most reactive remaining control rod.

UCI Technical Specifications page 8

Bases.

a. TRIGA cores have been in use for years and their characteristics are well documented. LEU cores including 8.5/20 fuel have also been operated successfully at many facilities. In addition, analysis indicates that the low uranium loading, LEU 8.5/20 core will safely satisfy all operational requirements. See chapters 4 and 13 of the SAR as supplemented by letter dated Junc 7 "'2011.

b. The IFE provides a signal to the fuel temperature safety channel.

c. Inner core lattice positions contain experiments or an experimental facility to prevent accidental fuel additions to the reactor core. Vacancies are permitted only on the periphery of the core, where reactivity worths are lower.

d. Graphite and water reflectors are used for neutron economy and the enhancement of experimental facility radiation characteristics.

e. Manual manipulation of control rods will be allowed only when a single manipulation can not result in inadvertent criticality.

3.2 Reactor Control and Safety Systems 3.2.1 Control Rods Applicability. This specification applies to the function of all control rods.

Objective. To assure control rods are operable and that prompt reactor shut down following a scram is accomplished.

Specifications. The reactor shall not be operated unless the control rods are operable. Control rods shall not be considered operable if:

a. damage is apparent to any rod or drive assembly that could affect operation; or

b. the scram time for any control rod is greater than 1 second for 90% reactivity insertion; or

c. the total reactivity worth of the two transient control rods (ATR and FTR) is greater than $3.00.

Basis. Experience has shown that rod movement is assured in the absence of damage and that scram timcs o1" less than I second are more than adequate to reduce reactivity and fuel temperatures rapidly to assure safety in view of known transient behavior of TRIGA reactors. The total worth of the two transient rods is limited so as to restrict the pulse size.

UCI Technical Specifications page 9

3.2.2 Reactor Measuring, Channels Applicability. This specification applies to the information which shall be available to the reactor operator during reactor operation.

Obiective. To specify that minimum number of measuring channels that shall be available to the operator to assure safe operation of the reactor.

Specifications. The reactor shall not be operated in the specified mode unless the measuring channels described in Table I are operable.

Table 1. Minimum Measuring Channels Measuring Channel Operating Mode Steady-state Pulse Fuel Element Temperature I I Linear Power Level I Log Power Level Power Level (%) 1 1 (peak power)

Nvt circuit I Note I. Any single power level channel may be inoperable while the reactor is operating solely for the purpose of calibration and/or channel tests or checks on that channel.

Note 2. Any single power level channel that is not required for safety scram purpose by TS 3.2.3 and ceases to be operable during reactor operation shall be returned to operating condition within 5 minutes or the reactor shall be shut down. For channels required by TS 3.2.3 the reactor shall be shut down immediately if the channel becomes inoperable.

Basis. The fuel temperature displayed at the control console gives continuous information on the parameter which has a specified safety limit. The power level monitors assure that measurements of the reactor power level are adequately covered at both low and high power ranges in appropriate modes.

Notes I and 2 allow for necessary tests for resolving of problems or recalibration while maintaining sufficient information for safe operation.

UCI Technical Specifications .page 10

3.2.3 Reactor Safety System Applicability This specification applies to the reactor safety system channels.

Objective 'T'o specify the minimum number of reactor safety system channels that shall be operable in order to assure that the fuel temperature safety limit is not exceeded.

Specification. The reactor shall not be operated unless the safety system channels described in Table 2 and the interlocks described in Table 3 are operable in the appropriate operating modes.

Table 2. Minimum Reactor Safety Channels Safety Channel Function and trip level Operating Mode maxinmum setting Steady-state Pulse Fuel Element Scram - 425°C (IFE) I I Temperature Reactor Power level Scram - 110% of 250 kw 2 Loss of FIV and/or Scram 1 1 signal on any required channel Manual Bar Scram I I Preset Timer Scram pulse rods < 15 seconds - I after pulse Seismic Switch Scram - if motion of 3% g 1 1 (0.03g) is exceeded Pool Water Manual Scram I "Temperature if >= 25 0 C Table 3. Minimum Interlocks Operating Mode Interlock Function Steady- Pulse state Wide Range Power Prevent control rod withdrawal when power level is < I x I -

Level Channel (Log) l0-7 % of full power REG, SHIM, ATR Prevent application of air to fast transient rod when all I -

Control Rod Drives other rods are not fully inserted REG, SH IM, ATR Prevent simultaneous withdrawal of more than one rod I Control Rod Drives REG, SHIM, ATR Prevent movement of REG and SHIM rods in pulse mode Control Rod Drives ATR Cylinder Drive Prevent application of air to adjustable transient rod 1 unless cylinder is fully down Wide Range Linear Prevent ATR or FTR withdrawal unless power level < 1 I Power Channel kilowatt UCI Technical Specifications page I11

Bases Scrams. The fuel temperature scram provides the protection to assure that if a condition results in which the safety limit is approached, an immediate shutdown will occur to keep the fuel temperature well below. The justification basis is described in section 2.2. The power level scrams are provided as added protection against abnormally high fuel temperature and to assure that reactor operation stays within the licensed limits. The manual scram allows the operator to shut down the system if an unsafe or abnormal condition occurs. A high voltage scram on each channel assures that detector response is operating at all times. The seismic switch will scram the reactor if earth movement in any dimension exceeds 3%g (0.03g) in case the operator is prevented from operating the manual scram at the time. This level corresponds to movement noticeable by most persons, but (by MM scale) results in no damage to structures. The preset timer scram provides pulse "clipping" to reduce energy production at the tail of a pulse. The pool water level temperature limit is the value used for the thermal hydraulic analysis input coolant temperature in the SAR as supplemented by letter dated June 711 2011, and also is designed to reduce stress between the aluminum tank liner and its concrete surround.

Interlocks. [he interlock to prevent startup of the reactor with less than 10-7 % power indication assures that indication of neutron multiplication is present as reactivity is inserted. The interlocks on control rod drives are provided to prevent withdrawal of more than one control rod at a time avoiding multiple simultaneous reactivity insertions by operators. The interlocks which prevent the firing of the transient rods in the steady-state mode or if the power level is greater than 1 kilowatt prevent inadvertent pulses or pulsing when fuel temperature is too high.

3.3 Coolant Systems 3.3.1 Pool Water Level Applicability. These specifications apply to the water level in the reactor pool at all times.

Objective. To assure there is sufficient water in the reactor pool to provide cooling and shielding for radiation from the core, and to check for potential pool leakage.

Specifications.

a. The reactor shall not be operated unless the pool water level is at least 24 feet above the tank floor (I foot below the tank edge).

b. An audible alarm, with reporting to the UCIPD dispatch desk if not locally silenced by an operator, shall operate 24/7 to alert personnel if the water level in the reactor pool falls below the above limit. Visual checking of water level shall be substituted every 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> during periods when the alarm is found to be inoperable and no substitute level device has been implemented.

c. Records shall be maintained of the date, time and quantity of all make up water added to the pool.

Basis. Facility design calculations and subsequent measurements show that these water levels are sufficient to reduce full power operational radiation levels to acceptable levels within the facility and in any occupied areas above or surrounding the reactor. This is also true for shut down levels.

The alarm will notify appropriate responders well before any increase in radiation levels to the surroLHndings occurs. The alarm and the operational make up water' records will, if it occurs UCI Technical Specifications page 12

unusually frequently, alert operators to the possibility that pool leakage might be occurring. The pool level is normally maintained at approximately 10 inches below the tank edge. Thus the alarm level is at 2 inches below the normal level corresponding to evaporation or leakage of only 160 gallons (640 liters, or 0.6% of total pool water). The maximum water leak rate calculated (SAR) indicates that the water would be at a sufficient level over the core for at least 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> to prevent unsafe release of radiation to the surrounding areas. Procedures call for a substitute pool level alarm system to be implemented during any extended period of failure.

3.3.2 Pool Water TeMperature Applicability. This specification applies to the water temperature in the reactor pool at all times.

Objective. To assure the water in the reactor pool stays within limits that provide sufficient cooling of the fuel and that minimizes stresses to the tank and reactor components.

Specification. The pool water temperature shall be maintained between 17'C and 25°C Basis. These temperature limits are easily maintained using the available cooling system and guard against temperatures that might prodluce undue stresses on tank components or water purification systems. The thermal hydraulic anaiysis was based on an inlet core temperature of 25 TC.

3.3.3 Pool Water Conductivity Applicability. This specification applies to the conductivity of water in the reactor pool at all times.

Obiective. To assure the water in the reactor pool is maintained at high purity to minimize potential corrosion of reactor components.

Specification. The pool water conductivity level shall be maintained less than 3 micromhos/cm.

Make-up water shall meet this specification before being added to the pool.

Basis. Experience at other reactor facilities indicates that maintaining the conductivity within 5 micromhos/cm (plS/cm) is adequate to provide acceptable control of corrosion (NUREG 1537). An additional margin of assurance is provided by this lower specification. Degradation from this conductivity also aids in assessing possible leakage of treated secondary coolant water into the primary coolant water.

3.3.4 Pool Water pH Applicability. This specification applies to the pH of water in the reactor pool at all times.

Objective. To assure the water in the reactor 1p001 is maintained at high purity to minimize potential corrosion of reactor components.

Specification. The pool water pH level shall be maintained between 5.5 and 7.5.

Basis. While no credible mechanism exists in the pool for pH to be out of this range, ANSI 15.1 and NUREG 1537 recommend such limits.

UCI Technical Specifications page 13

3.3.5 Pool Water Radioactivity Applicability. This specification applies to the radioactivity of water in the reactor pool at all times.

Objective. To assure the water in the reactor pool is maintained at high purity.

Specification. The average pool water radioactivity level shall be maintained within limits for sewer disposal as established by 10 CFR 20, Appendix B, Table 3 for radionuclides with half-lives longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Basis. Maintenance at this level will assure that any disposal of pool water, either planned or inadvertent, will be within appropriate and significant radioactivity limits. It also will provide verification of absence of fission product leakage.

3.4 This section intentionally left blank 3.5 Ventilation Systems 3.5.1 Ventilation System.

Applicability. This specification applies to the operability and operation of the facility' ventilation system.

Obiective. To assure that the ventilation system is operable to mitigate the consequences of possible relcase,, ol radioactive materials resulting from reactor operation.

Specification.

a. The reactor shall not be operated unless the ventilation system is operating as indicated by:

1. a minimum of 0.10 inches of water negative pressure difference between the reactor room and the control room and between the reactor room and the air outside the building; and

2. a minimum total exhaust flow rate from the reactor area of 4000 cfm is present.

Note: The ventilation system may be inoperable for periods of time not to exceed two hours to allo\w repair. maintenance or testing of the system. During such an exception, no pulses shall be fired.

b. The reactor shall not be operated unless it is verified that the ventilation system goes into the emergency mode upon manual actuation or a signal of high radiation activity from a continuous particulate air monitor (CAM) measuring air from above the pool as described in TS 3.5.2.

Verification shall be by observing the emergency flow rate is at least 240 cfm, the absence of regular exhaust flow, and the pressure difftrential reading between the reactor area and the outside is negative.

Basis. lhrough a combination of inflow dampers and outflow exhaust, facility design establishes and exceeds these pressure diflerentials and flows. The differential pressure assists in confinement of radioactive materials. The SAR establishes that normal operation effectively dilutes 4 Ar levels below 10 CFR20 limits and as detailed in Ilicility annual reports. An automatic emergency mode with a small filtered purge exhaust is provided to limit release of radioactivity to the environment.

UCI Technical Specifications page 14

Operation of the normal system adequately dilutes tile 41'Ar released during experimental operations. The two hour exemption should not diminish the effectiveness of the CAM in detecting any release of radioactivity. The requirement not to pulse while the ventilation system is undergoing repair reduces the likelihood of fuel element failure during such times.

3.5.2 Ventilation During Emergency Situations Applicability. This specification applies to the ventilation system provided for emergency sittuations.

Objective. To assure there is confinement of radioactive releases by closing of normal ventilation and establishing emergency ventilation.

Speci ication. A signal of high radiation activity alarm from a continuous particulate air monitor (CAM) ineasuring air flrom above the pool or manual operation from the control room shall carry out the Ibilowing functions:

a. close off inflow air by closing damnpers: and

b. close off outflow air by closing dampers in exhaust ducts and removing power from relevant exhlaust ialns and fuime hood; and

c. remove power from pneumatic transfer system so it can no longer operate to transfer air through any core region; and Li. open outflow damper in a small "purge" exhaust duct system equipped with a HEPA filter.

Basis. '1hcse actions will resuRlt in conlincment of'any released radioactive materials, while beginning to purge contaminated air through a high grade filter. Experience has shown that fission product release fIrom fuel elements is most rapidly detected by a CAM operating in this manner.

The SAR establishes that the emergency purge system will, in the event of a radioactive gas release, be effective in limiting release to the environment and also providing personnel with sufficient time to evacuatc belbre experiencing serious exposure. It is shown in Chapter 13 of the SAR, as supplemented by letter dated Dec 2'` 2011, that operation of the emergency exhaust system reduces off-site doses to below 10 C17R Part 20 limits in the event of a TRIGA fuel element failure. It is show,n also that, if the reactor were to be operating at full steady-state power, fuel element failure will not occur even if all the reactor tank water were to be lost immediately.

3.6 EmerLgency Power Applicability. This specification applies to the availability of emergency power.

Obiective. To assure certain information related to personnel safety is available in the event of main electrical power failure.

Specification. Emergency electrical power, activated rapidly upon main electrical power failure, shall be provided to facility lighting, radiation monitoring and security monitoring systems.

Basis. Provision of power to these systems will assure that personnel present at the time, or resj)onuing to an event, will have inlbrmation to assist in monitoring their safety and the safety and security ol'the Ifacility.

UCI Technicai Sp*cifications Page 15

3.7 Radiation Monitoring Systems and 1-fI'lluCnts 3.7.1 Radiation Monitoring Systems Applicability. This specification applies to monitoring of radiation levels.

Obiective. To assure information is available to provide assurance of radiological safety of personnel at the tacility, and of the absence of excessive releases beyond the facility.

Specifications.

a. The reactor shall not be operated unless the lollowing minrimurn radiation monitoring instrunients are operating:

Radiation Area Monitors (RAM): 2 Continuous Particulate Radiation Monitor (CAM): I

b. Environmental monitoring dosimeter packs, exchanged at least quarterly, shall be in place at the primary exhausts of the flacility at all times, except when undergoing exchange. Additional packs shall be located in adjacent buildings, and in a more remote control location for comparison.

Basis. These instruments and dosimeters will provide adequate notification of abnormal levels that could result in exposures or uncontrolled releases. The environmental dosimeters provide information that can be used to track long term trends that might need attention.

3.7.2 EfftluCnts Applicability. This specification applies to the release rate of4 'Ar gas and liquid effluents.

Obiective. To assure that concentration of4 'Ar in accessible unrestricted areas shall be below the applicable limits of 10 CFR Part 20.

Specilication.

a. The annual average concentration of 4tAr released to the environment shall not exceed I x 10-8 jiCi/mL.

b. The quantity of radioactivity in liquid effluents released from the facility to the sewer system shall not exceed the limits of"10 CFR 20. Appendix B, Table 3.

Basis.

a. [he inalysis presented in Chapter 13.2 of the SAR, as supplemented by letter dated Oct 3 rd 2011, concludes that the building exhaust and room ventilation system normally provides a dilution factor of l00 at. the point of external release for airborne concentrations in the facility area. Under extremely unlikely conditions involving system fallures, it provides a dilution factor of at least 30, reducing the tacility room conccntration predicted from calculations and measurements as a result of normal reactor operation to be well below 10CFR Part 20 Appendix B, Table 2 requirements (1 x 10-1 ptCi/il). This will be further assured since releases are permitted to be averaged over a one year perioci. The exposure risk to the public is reduced since the discharge plume is at a high level above the roof Annual reports flrom this faciliiy have shown that levels released have been well below this value.

b. This specification establishes assurance that any release of radioactive materials contained in liquids released to the sewer system does not exceed the limits required by regulations.

UCI Technical Specifications page 16

3.8. LinitLations on LX)perilennts 3.8.1 Reactivity Limits Applicability. This specification applies to experiments placed in the reactor and its experimental facilities.

Objective. The objective is to prevent damage to the reactor or excessive release of radioactive materials in the event of an experiment Ihailure.

Specifications. The reactor shall not be operated unless the following conditions governing reacti it\ wvorths exist:

a. The reactivity worth oflany unsecured experiment shall not exceed $1.00, and

b. The reactivity worth of an individual experiment shall not exceed $3.00, and

c. The sum of the absolute values of reactivity worths of all experiments shall not exceed

$3.00.

Basis. The limit on an unsecured experiment is to prevent an inadvertent pulse, and to maintain shutdown margin limitations. The insertion of $3.00 pulses has been analyzed as a safe operating condition lor this reactor (SAR Chapter 13). Limitation of experiments such that a pulse larger than this value could not occur is prudent and stays well within safe limits. The limitations also assure that achecvement of margins 1or shluLtd\\ n i.-, assured.

3.8.2 Materials Applicability. This specification applies to experiments placed in the reactor and its experimental facilities.

Objective. To prevent damage to the reactor and to minimize excessive release of radioactive materials in the event of an experiment failure.

Spccifications. The reactor shall not be operated unless the following conditions governing experilliilnts exist:

1. !'ueled experiments shall be limited such that the total inventory of iodine isotopes 131 through 135 in the experiment is not greater than 0.02 curies, and the strontium-90 inventory does not exceed I microcurie.

b. Explosive materials slalll not be irradiated in quantities greater than 25 milligrams of TNT equivalent. Explosive materials in lesser quantities may be irradiated provided that the pressure produced upon accidental detonation of the explosive has been calculated and/or experimentally determined to be less than half the design pressure of the container; and

c. ,xperiments containing corrosive: materials shall be doubly encapsulated. The failure of an encapsulation of"material that could damage the reactor shall result in removal of the sample and physical inspection of potentially damaged components.

UCI Technical Specifications page 17

Bases. In specification a. an assumption is made that complete release of volatile material (iodine) from a fueled experiment is possible. It is shown in the SAR, Chapter 13, as supplemented by letter dated Dec. 2 "'d 2011. that a release of"0.02 curies of iodine activity would result in a maximum dose to the thyroid of a person in the facility who evacuates in 5 minutes of 0.4 rem, or less than 1 /7 5 "'of the recommended (NURE6 1537) TEDE limit of 30 rem to the thyroid which is lower than the 50 rem limit in 10 CFR 20. An individual directly exposed in the exhaust in an unrestricted area under highly unlikely conditions would receive (TEDE) less than 0.54 mrem.. The maximum projected TEDE to a person in the nearest living area will be less than 0.22 torem, far less than the 100 mrem limit in 10 CFR 20. These computations are extremely conservative as they assume no pool water is present. In the event ol'a failed experiment the pool water would be present to absorb/dissolve halogens and reduce the airborne concentrations.

Specifications b. and c. reduce the likelihood of damage to reactor components resulting from experiment f'ailure and use iinformation fIom NRC Reg. Guide 2.2.

3.8.3 Failures or Malfunctions Applicabi:tv. This specification applies to experiments placed in the reactor and its experimental facilitics.

Objective. To prevent damage to the reactor as well as to minimize release of radioactive materials in the event of an experiment tiilure.

Spccifications. Where the possibility exists that the failure of an experiment under normal operating conditions oflthe experiment or reactor, credible accident conditions in the reactor, or possible accident conditions in the experiment couhld release radioactive gases or aerosols to the reactor ficility or any unrestricted area, the qLuantity and type of material in the experiment shall be limited such that the airborne radioactivity in the reactor facility or the unrestricted area will not exceed the applicable dose limits in 10 CIFR 20. In calculating such a limit, it shall be assumed that 100% ol the gases or aerosols escape fi'om the experiment, unless a specific effective experiment design is in place for trapping such efflluents, in which case at least 10% of the gases or aerosols shall be assumed to escape.

Basis. This specification is intended to assist experiment review and design in meeting the goals of 10 CIFR 20 b) reducing the likelihood of excessive Iacility personnel or public exposure by gases or aerosols as a result of'experiment FIilure.

3.9. This sctCi ovi intentionally left blank.

UCI Technical Specil'ications pagle I18

4. SURVEILLANCE REQUIREMENTS 4.0 General Applicability. This specification applies to surveillance requirements of any system related to reactor sal'ety.

Objective. To assure the proper operation oflany system related to reactor safety.

Speci fications.

a. Surveillance requirements may be del'erred during prolonged (periods greater than I month) reactor shutdown (except Technical Specifications 4.3.a, 4.3.c, 4.3.e, 4.3.f and 4.3.g.).

However, they shall be completed prior to reactor start-up unless reactor operation is required for performance of the surveillance. Such surveillance shall be performed as soon as practicable after reactor start-up. Scheduled surveillance which cannot be performed with the reactor operating may be delferred until a planned reactor shutdown.

b. All replacements, modifications, and changes to systems having a safety related function including the ventilation system. the core and its associated support structure, the pool, the pool coolant system, the control rod drive mechanisms, and the reactor safety system shall mneet or exceed the requirements of"the original system or component. A safety system shall not be considered operable until it has been properly tested to meet specifications.

Basis. Changes or maintenance can affect reactor operation parameters. This specification will assure that saLfety systems function according to established criteria before any reactor operation.

4.1 Reactor Core Parameters Applicability. This specification applies to the surveillance requirements for reactor core parameters.

Obiectixe. To verify that the reactor does not exceed authorized limits for power, shutdown margin, core excess reactivity. speci ications f1or fuel element condition, and verification of total reacti\ ity worth ol'each control rod.

S _cci icaltions.

a. The total reactivity worth ol'each control rod shall be measured annually or following any signilfcant change (>S0.25) in core configuration.

b. '[he core excess reactivity shall be determined using control rod position data prior to each day's operation, or prior to each operation extending more than one day, or following any signi ficant change (>S0.25) in core configuration.

c. '[he shutdown margin shall be determined at each day's shutdown, or at the end of any operation exceeding one day, or following any significant change (>$0.25) in core con figuration.

d. All core fuel elements shall be visually inspected (under water) and measured for length and bend quinquennially, but at intervals separated by not more than 500 pulses of magnitude greater than $1.00 of reactivity. Fuel f'ollower control rods shall be visually inspected and measured for bend at the same time interval. Such surveillance shall also be performed for elements in the B and C rings in the event that there is indication that fuel temperatures greater than the limiting salety system setting on temperature may have been exceeded.

UCI Technical Specifications page 19

e. Prior to resumption of routine pulse mode operations following a period of no pulse mode operations for more than I year. a test of pulsing performance with a pulse insertion of $1.50 shall be performed to assure pulsing power and fuel temperature response is as predicted from prior experience.

f. Full core, fuel and control rod surveillance shall be conducted before further reactor operation if significant changes are observed in any measured parameters such that it could be concluded that fuel element or control rod integrity has been compromised or fuel element or control rod damage has occurred.

Basis. Experience has shown that the identified freCLuencies are more than adequate to ensure performance and operability for this reactor. The value of significant change is measureable and will assure suffi1cient shutdown margin even taking into account decay of poison.

For fIel elements, the most severe stresses induced in the fuel elements result from pulse operation of the reactor. during which dil'ferential expansion between the fuel and the cladding occurs and the pressure of the gases within the elements increases sharply. The surveillance interval is selected based on the past history of more iCClICuent, uneventful, inspections for over 40 years at this facility and experience at other TRIGA facilities with similar power levels, fuel type, and operational modes. It is also designed to reduce the possibilities of mechanical failures as a result of handling elements, and to minimize potential radiation exposures to personnel.

4.2 Reactor Control and Safety Systems Applicabijity. This specilfication appl ies to the surveillance requirements for the reactor control and safety systems.

Obiective. The objective is to verify perl'ormance and operability of those systems and components which arc directly related to reactor saliety.

Specificatiorns.

a. A channel calibration shall be Made of the power level monitoring channels by the calorimctric mnethod annual ly or iminediately following any significant (>$0.25) core coniLguration change.

b. Control rod scram times for all four control rods shall be determined annually or for individual rods immediately ol0lowine any maintenance work involving that control rod or drive mechanism that may have al'fected rod scram performance.

c. All control rods shall be visuallV inspected for deterioration quinquennially.

d. The transient (pulse) rod pneumatic cylinders and the associated air supply systems shall be inspected annually, and cleaned and lubricated if necessary.

e. On each day that pulse mode operation of the reactor is tplanned, a functional performance check of the transient (pulse) rod system shall be performed.

1'. A channel test of euch of the reactor safety system channels and interlocks in Tables 2 and 3 in section 3, except for the pool water temperature, shall be performed prior to each day's operation or prior to each operation extending more than one day.

UCI Technical Specifications page 20

g. A channel check of the functions 01' the seismic switch shall be performed annually or as soon as possible after an observed seismic event or one reported to be of sufficient magnitude to trip the switch.

h. A channel check of the: pool water teCpCra'urCe measuring channel shall be performed prior to each day's operation or prior to each operation lasting more than one day.

i. A calibration of the fuel temperature measuring channel shall be performed annually.

Basis. The control rods are inspected and scram times checked to assure safe scram operations. The surveillance intervals for those and the channel surveillances are selected based on the past history for over 40 years at this fiacility and are adequate to correct lor long term drifts and other instrument problems. The manulacturer of thc seismic switch makes no recommendation for recalibration and believes the accelerometer settings remain Cefective fur the life of the device. The channel test of the seismic switch involves simulation ofra seismic event my tapping the switch to initiate a reactor scram, establishing operational functionality. l'he channel check of the pool water temperature meter involves comparison to a second independent device also measuring pool water temperature.

4.3 Reactor Pool Water Applicability. This specification applies to the surveillance requirements for the reactor pool water.

Objective. The objective is to assure that the reactor pool water level channel is operable, that alarm settings are verified and alarm reporting is I'unctional. In addition, that the water level and purity is being mauintained within acceptable limits.

Specifications.

a. A channel check oflthe pool water level measuring channel shall be performed monthly to iclIide clhannel verification of the alairm reporting system.

b. A channel calibration of the pool water level measuring channel shall be performed annually to include channel verification ofethe alarm set point.

c. The pool water conductivity shall be mneasured at the end of each operating day, or at shuItdo\\ n 1')r a period 01'operation extending more than one day. For periods of extended slLutdown, the conduactivity measurement sliall be made mionthly.

d. The pool water temperature shall be monitored each hour during reactor operation.

e. The pool water p1-I value shall be measured quarterly.

f. The pool water radioactivity shall be measured quarterly.

g. The pool water loss rate shall be evaluated on each occasion when make-up water is added to the pool. Any unusual increase in loss rate shall be investigated as a possible pool leak belbre any further reactor operation, UCI Technical Specilfications page 2 1

h. If there is any indication of focl element leakage of fission products, of pool water leakage from the Lank, or leakage flrom the secondary cooling system into pool water, all pool water quality and quantity measurements shall be re-measured immediately and repeated at least weekly until the absence of any problem is confirmed. When the reactor has not been operated Imr periods greater than I month, all pool water measurements listed above shall be ver lied to meet operational requirements before reactor operation is resumed.

Basis. These verilications will assure that a continued warning system for an unexpected loss of pool water is maintained, and that any perturbation of pool water quality noted then allows for corrective action to minimize corrosion, or buihld-up of radioactivity in the water. The frequent check on conductivity monitors possible leakage into the pool from the secondary water system.

Temperature measurements will assure the pool water is maintained within operating limits.

Radioactivity measurements will enable assessments of long terma impacts of pool leaks and/or fission product leaks from a fuel element.

4.4 [his section intentionally left blank.

4.5 Ventilation Systems Applictibility. This specification applies to the surveillance requirements for the reactor room ventilation system.

Objective. To verify performance is adequate to provide for normal and emergency mode ventilation for the facility to control and confine releases of airborne radioactive materials.

Specifications.

a. A channel check of the existence ofinegative air pressure between the reactor room and the control room, and the reactor room and the outside air in both normal and emergency modes shall be perforlned daily.

b. A channel check of the exhaust flow rates from the reactor area in both normal and emergency modes shall be perlormned daily, to demonstrate that the ventilation system is operable in both normal and emergency modes by observation of flow rates, and valve/damper action.

c. A channel test of the function of the particulate high radiation (CAM) alarm and the control room manual switch to properly set the ventilation system into emergency mode shall be perl'ormed daily.

Basis. Based on experience these surveillances will assure that the ventilation system is functioning as specified. (Section 3. 5).

UCI Technical Specilications page 22

4.6 Emergency Power Applicability. This specification applies to the provision of emergency electrical power to room lighting, radiological safety, and SCCLIInIty ristrumentation.

Objective. To assure proper connection and lunction of the emergency electrical power so that personnel are provided lighting and information relating to radiological safety in the event of main electrical power failure.

Specification. It shall be determined annual l\ that the radiological safety instruments required by Section 3.7. L.a. are attached to the correct circuit f'r emergency electric power provision. It shall be determined annually that the emergency power generator has been successfully tested for operation and automatic load transfer.

Basis. It is important for safety that verification of emergency power functions be carried out. Past experience mias shown that this frequency is adequate to assure continuity of this service.

4.7 Radiation Mo11itorin. Systems and 1Ef'lluents Applicability. This specification applies to the surveillance requirements for the radiation monitoring instrumentation required by Section 3.7. l.a of these specifications and the effluent releases specified by section 3.7.2.

Obiective. The objective is to assure that the radiation monitoring system is operating properly and to verify the approplriate alalrm settings Lnd amounts of radioactivity in effluent releases.

Speci ficatio ns.

a. A channel test of the area radiation monitoring systems required by Section 3.7.L.a. shall be perlbrmed daily. This shall include verification of the alarm set points.

b. A channel check of the Continuous Air Monitor (CAM) required by Section 3.7.1 .a. shall be pe~lormed daily. This shall include verification of the alarm set point.

c. A channel calibration of the radiation monitoring systems required by Section 3.7.1.a. shall bC pemCrmIled annu11ally.

d. Tlhe environmental monitoring dosimeters required by Section 3.7.1 .b. including those mtonitoring exhaust Ce'fluents, shall be evaluated quarterly.

e. Arny liquid effluents to be released to the sewer system from the facility shall be analyzed f1r radioactive content prior to release.

Basis. Survcillance of the equipment and effluents will assure that sufficient protection against excessive radation or release of excessive radioactive materials is available. Past experience has shown that these practices and frequencies are adequate to assure proper operation.

UCI Technical Spci icationspg pulgc 23 2

4.8 Experiment Limits Applicability. This specification applies to the surveillance requirements for experiments placed in the reactor and its experirnental 'lacilitics.

Obiective. The objective is to assLire that cxpkcrinents to be conducted do not damage the reactor or release excessive amoUnts ot radio0a,.1ti\ e materials as a result of experiment failure.

Speci fications.

a. No experiment shall be installed in the reactor unless a safety analysis has been performed and reviewed in accordance with Sections 3.8 and 6.5 ol'the Technical Specifications.

b. The reactivity worth ola new experime.nt shal be verified at a power level less than 2 watts, before reactor operation at higher power with the experiment.

Basis. Past experience has shown that adherence to requiremnents described in Sections 3.8 and 6.5 are adequate to assure safe Cxp)Crimenictation at this lacility.

UCI Technical Specifications pLIg e. 2 4

5.0 DESIGN F'EATURES 5.1 Site and Facility Description Specifications The site shall be the reactor lacillit' as dcscribcd below.

The reactor facility shall be a restricted acce_-s area consisting of a main area, two associated laboratory areas, and a control room on a single level in the basement of Rowland Hall, on the University ofCalil brnia IrvinC Camlp)is. [lIC minimumLiCee air volume of the reactor area including the two associated ,aboZratorics ,hall be 23.000 cubic leet. Normal entry to these areas shall be restricted to a single door\I:' fromin the control room. Large doors shall be provided to the adjacent loading clock to provide emergency egress and/or access for incoming or outgoing large items. lull visibility shall bc provided between the control room and the reactor area.

The reactor shall be housed inI a closed aLre designed to restrict leakage.

Basis. The extent of the site and facilit; is spccilfed to define the controlled access area and the means of access. The closed area is designated to assist in mitigation of potential radioactive releases.

5.2. Reactor Coolant System Specifications.

a. The reactor core shall be cooled by natural convection water flow.

b. All piping and other equipment f6r pool water systems shall be above normal pool level.

Inlet and outlet pipes that lead to the heat exchanger or demineralizer shall be equipped With siphon breaks not less than 14 Il'et above the upper core grid plate, unless those pipes end more than 14 feet above the upper core grid plate.

c. A pool water level indication is provided at the control console with an alarm at the control console and an alarm to a central monitoring station.

d. A pool water temperature indication shall be provided at the control console.

e. A pool water conductivity, m11eaSurement instrument shall be provided in the reactor room.

f. A method for pH-I water measurement shall be available in the reactor room.

g. Gamma and beta radiation spectrometry equipment shall be provided for water sample radioactivity assay.

Basis. Pool water quantity and quality is controlled so as to limit radiation and/or radioactivity release, and corrosion of components. Information is necessary to provide staff with indications of change in pool water characteristics.

UCI Techmical Specifications page 25

5.3. Reactor Core and Fuel 5.3.1 Reactor Core.

Specilications.

a. The core assembly shall consist of'fRIGA' standard 8.5/20 stainless steel clad fuel elements.

b. The core fuel shall be kept in a close-packed array in core lattice positions except for control rods, single- or three-elemennt or seven-element positions occupied by in-core experiments, irradiation lbacilities tincluding transfer systern terrnini), graphite dummy elements, and a central dry tube.

c. Rellection of neutrons shall bc provided by combinations of graphite and water, with the graphite in sealed containnment with aluminum cladding, either in the form of rods occupying grid positions, or in a larer reilector structure surrounding the core.

d. An An-Bc neutron source shall be providcd in one of two specific locations provided in the Upper grid plate to provide start-up neutrons. It may be removed for maintenance purposes.

Basis. Standard TRIGA'<. fuel and reactor core design has a long and successful history of use.

Model calculations in the SAR as supplemented by letter dated .lune 7"' 2011, indicate acceptable neutronic and thermal hydraulic conditions for the core design under extended use and bum-up. The Am-Be source is in a sealed capsule andl has a long uisel1ul life.

5.3.2. Control Rods.

Speci ficat ions.

a. The SHIM and REG rods shall be motor driven with scram capability and solid boron compounds in a poison section, with fuel followers of standard TRIGAw fuel meeting the same specifications as in Section 5.3.3.

b. Thc ATR transient rods shall be motor and pneumatically driven, have scram capability, and contain solid boron compounds in a poison section. The ATR shall have an adjustable upper travel limit to provide variable pulse insertion capability. The FTR transient rod shall be pneumatically driven and have scram capability, and contain solid boron compounds in a poison section. The ATR and FTR shall incorporate air filled followers.

Basis. These control rods have been shown by model calculations and a history of use to be effective Ior assuring prompt shut-down and control of the reactor.

UCI Technical Specilications page 26

5.3.3. Reactor Fuel.

Specifications. Standard TRIGA ' Fuel elements shall have the following characteristics:

a. The total uranium content shall be nominally 8.5 % by weight, enriched to less than 20%

235U.

b. The hydrogen to zirconium atom rutiu in the zirconium hydride shall be a norninal 1.65 hydrogen atomns to 1.0 zirconium atom.

c. The cladding shall be 304 stainless steel, nominally 0.020 inches thick.

d. An upper fitting with Clngravcd uniLue serial numbers shall be designed to fit a latching tool for CUel movement.

Basis. "'RIGA'L fuel elements meeting these manufLcturer's specifications have a long history of successful use with minimal failures. Minor deviations about these levels due to manufacturing variations are not to be considered violations oF" this speci lication.

5.4. Fuel Storage Specifications.

a. All fuel elements shall bc stored in a geometrical array where the kerf is less than 0.80 for all conditions of moderation and reflection.

b. Irradiated fuel elements and fueled devices shall be stored in an array which will permit sullicient natural convection cooling by water or air such that the fuel element or fueled device temperature will not exceed 8U0 C.

c. Fuel showing evidence ofdanmage (see .S 3.1.6) shall be stored separately from fuel not suspected to be damaged, and shall be checked for fission product leakage.

Basis. These specifications establish a sufficient reactivity margin to guard against accidental criticality ofelements in storage, and that heat dissipation does not create excess corrosion or other problems. iDamaged fuel is more likely to have or develop fission product leakage and so must be monitored and kept separately.

UCI Technical Specifications page 27

5.5. Ventilation System Specifications.

a. The ventilation system shall operate in either normal or emergency mode. The ventilation system shall consist of ducts, blowers, dampers, flow and pressure measurement devices, and exhaust points above the rool of Rowland Hall.

b. During normal operations, the \ entilation system shall be capable of exhausting air or other gases From the reactor area at a rate ol14000 cfrm.

c. During normal operation the ventilation system shall be capable of maintaining a minimum of 0.10 inches of water pressure differential between the reactor area and the control room, and between the reactor area and the outside air.

d. During emergency situations involving release of radioactive materials into the air, an emergency exhaust with a HIEPA filter shall be provided to exhaust a minimum of 240 cfm froim the reactor area.

e. Shutdown of the normal reactor area exhaust system and start-up of the emergency exhaust system shall be initiated by a high radioactive particulate count rate alarm signal originating in the reactor room, or a manual switch in the control room.

1'. During all modes of operation. the ventilation system shall exhaust at a minimum height of 90 feet above ground level.

Basis T'he ventilation system assists in mitigating the effects of radioactive releases to the environment by providing dilution and control of such releases either during normal or emer.*,_,cic circumstances.

UCI Technical Specifications page 28

6 0 ADMINISIIRA'IVI-U\'UN I RUI-.L-6.1 Organ ization and StructuIv.

6.1. .1 Structute.

Tlhe reactior ,tilit isS lou.,, I tic ",.,,.i J . ,. cices o0 ti.,. University of Calilbrnia, Irvine. ilie react"or is rciatodl 10 t1e n 1\ r, ," posiCi ns shown in the organization chart, l"igUre I.

6.1.2 Rcspon-,,ibilitics.

a. 'Ih liensee of"thel racto.Cr . the l-', I u 0,) \ c , ,Il the Uni\,: rSit\ of California, which has deleigatoe L thority I'br ,i.se ntti, I d c- x'CLIi\ C Vice "i Chancellor and Provost of the L'ni\ crsityof Calil'u ornia. Ir\ inc

b. The r'Cactorl" facili tv is LILdLr the 1' u.L10idou I Kcic1or Di rector x lio shall be a tenure member of the Uinivcsi tN ol'Caii lbtriz, I-ViI,. It,_ic ..,. L )i recto)r ski I re)OItt to the Chair of the Chemistry departn ic, . who, in turn -hall v-. ,..' I, t c t),'cn of'the School of Physical Sciences.

C. Operations shall be SuLp c;',, d 1I.. AC,

.,1 ,1 ",'i cr\ iýul \\ lho hIold a valid senior operator's license 1or he llcilit\, liIs pI,,iti ,i .i .; .vsi for SS , ni that all operations are COn~dUCt III aS l LOC inU 111t11IIICI' c ',I I hII til l i c-: .scribo~ bN tLk 'la-ility license, the provisions of the Rctr pration. ('onnmi Lice Li*i.J Uc ip*l)\ isions of th,. UCI Radiation Safety Committee.

d. Reactor operators shall be lespi.n-,i , T, o '0 ( th*e tcictor and performting needed I'in iMIuItnicLiKIc L.aid uSLi\CeilIic. iIICC 1 , .h, L I iO ,_c1 sal'civ and necessary supervision of experinteIlters. Selnior reactor ore1r: t- , iIsui duties 1`or" supervision of operators as reqLuired by the US NuLIcIeir kegula'1 ,o1L iiFiiii -on in Part 55 o1' 10 CFR, and Section 6.1.3. of these technical spicci ,.CliiOns.

[.

There skall be a UL'I R1.6ILitu ion 5 l'C, .c." , RSO)i ) sponsible for the safety of operations fI'oiu the standpoint of r.udiLtiioi pi ,tco i-, i,-,i ion re.:po0rts to thie Office of Environmental Hleaillth and Safety witch is II orMu/i/ i!.. lic teitdent ulithe rc.t.oLor operations organization as shown in Figure I. An Independeiit c: ill p,- \\ ide 1iJU.i[ation SilCety Committee (RSC) is responsible for estLIbi i shmen t MLld rc\ t. .i ZtI i policies invo\ ing radiation and radioactivity.

RoutiLnC radiological salctv rLjlutirecntles Wi Ilin the reIctor baci it\ shall be carried out by reactor operators Lind/or individual I o\\hom alixperiineitier,,

l shall be required, by UCI regulations, to have recI Ved training in Radologic Lii sctlL',\ and be auL1thorized llor radiation use by the UCI Radiation Safety Officer.

In the e\nt m ol'bsceicc. or dLit4F I t o0i pipoillulentiei to specil'c positions, temporary duties and responsibilities mat be ccirried ()it bh\ I-ic,pcron text higher or lower in line in the organization cChart. pru ided the i; ', imiue, it ., nc basic quali Lications bor both positions.

UCI Technical Specifications pagC '9

c 1.gUCI RecuL01 01ur(ii ZIniztonl C'hart C(hanccllor L'\CL,'\ e \ ice Chancellor and Provost Vice Chancc,,or) 1)eaii, School of' Administration I P~hysical Sciences and Business Services Associate \'Ice Chancellor, Ai3' Director, Environmenta l lealth and SafeI'C DepUtly Director, EH-l&S SeCIior OperItors &

I Oi)erators (Level 4)

I - -

I-xperhueniters anid Laib Assistants UCI Technical Specifications page 10

6.1.3 Stafting.

a. The ninimum staflfng when the reCactor i- not SceLIFd shall include:

1. a licensed operator with direct acce,*s to tic reactor controls:

2. a second designated individual presen1t \\ oliand Hall able to carry out prescribed Rtuhin instructions and w,,ith the ability to check on tie sa'ety of the licensed operator and to act in the event of emerigencv: ald

3. a licensed Senior Uperator (S;IM ) read i\k\ iiklble on call. Readily available on call means:

1) lias been specilIcalN designated. aLic thie desiCiation known to the operator on duty: and

2) can be rapidly contacted b\ phone b\ th*e 0k.ratur on duty: and

3) is capable of getting to the reactor It\ x ithin 30 minutes Waciunder normal conditions.

b. A list of reactor facility personnel and other persons riesponsible for radiological safety and security on campus shall be kept in the reactor control room lor use by an operator or experimenter. The list shall inclIde telepIehu numibers of the Reactor Director, the Reactor Supervisor, the Radiation SaIct\ Off'icer anId ethe'r back-up radiological safety personnel, reactor operators, senior reactor operator,,. and personnel with responsibilities for maintenance in Rowland Hall.

c. lxpecrimentcrs Lisilng the I'Cilit shall bC ,:cvriilcd h\ tile UCI Radiation Safety program as trained and authorized to use radioacti\ C lnia:triat, lhe training shall include both general radiological training, including feiatures of the ALAlRlA pilmurani aLnd specialized training in procedures for using reactor auxiliary experimental CILu pment (such as transfer systems), carrying out necessary surveys and record-kecping ncccs-alr lor proper handling of radioactive materials within the reactor facility. lixperinCiItcrs So trained and authorized are responsible for their own personal and samIple/apparatus monitoring.

d. The following events require the presence inIthc facility ofa licensed Senior Reactor Operator.

L.Initial start-up and approach to power and final daily shutdown.

b. Fuel or control-rod IrlocationIs withil tLhe '_"r region.

c. Insertion, removal, or relocatioln e\pCeimCnt výorth more than $1.00.

Canl\

d. Restaut following any tnpianned 01ciuie lecd Cled shutdown, or signidicant power reduction.

6.1.4 Selection and Training of Personnel.

The selection, training, and requalification o f o0perations personnel shall meet the requirements of ANSI/ANS-15.4 - 2007.

6.2 Review and audit A Reactor Operations Committee (ROU) shall rev'iwcw reactor operations to assure that the facility is operated in a manner consistent with public and within the terms of the facility license.

Laint\

Review and audit ofradiological salf'et at the Ilicility shall be carried out by the UCI Radiation Sa1lety Committee (RS(_').

6.2.1 ROC Comnposition and QualifIcations The ROC shall have at least five voting memnbers, Lit least one of whom shall be a health physicist designated by the Office of Environmnental I lealth and Safety of the University. The Committee as a whole shall be knowledgeable in nuclear science and issties related to reactor and/or radiological UCI Technical Specifications page 3I1

salety. The membership shall inClLide at least t\\ u nembers who are not associated with the Department of Chemistry. Approved altiernates maN, serve in the absence of regular members.

Members and alternates and a chairperson for the L.ommittee shall be appointed by the Chair of the UC Irvine Department of Chemistry ,Lc,,el I) ur higher authority. The Reactor Director and ReCactor Supervisor shall be non-votine mIembers o1 the committee.

6.2.21ROC Charter and rules The lollowing responsibilities constitute the charter of the ROC.

a. Meeting at least annually, with provision for additional meetings when circumstances warrant to assure safety at the aIcility.

b. A quorum shall consist oftot less than a mLajori v of the voting members and shall include the chairperson or his/her designee.

c. Review and audit of facility stalfland opeCrations as indicated in sections 6.2.3 and 6.2.4.

d. D)esignation of individuals to pertorm audits of Iacility operations and records.

e. Preparation, approval, and dissemination oL minutes of meetings.

f Preparation and dissemination of findings anLd other reports as needed to assure safe operations of the reactor.

g. Approval of individuals for the supervision and operation of the reactor.

6.2.3 ROC Review function The following review functions shall be the responsibility of the ROC.

a. Review and approval of all proposed changes to the facility, its license, procedures, ROC charter, and Technical Specifications, including those made under provisions of 10 CFR 50.59, and the determinations leading to decisions relating to 10 CFR 50.59 approvals.

b. Revie\ý and approval of new or changed proceduares, experiments, components, or instrumentation having safety signilicancC.

c. Review of the quality assurance program implemcntation applicable to the reactor components.

d. Review of new experiments or changes in experiments that could have reactivity or safety significance.

e. Review of violations of technical specifications, license, or violations of procedures or instructions having safety significance.

f. Review of operating abnormalities that have safety significance.

g. Review of actions and reports listed in Sctions 6.6.1, 6.6.2, or 6.7.2.

UCI Technical Specifications page 32

h. Review of audit reports. including reports from the UCI Radiation Safety Officer, regarding the radiation protection program.

6.2.4 ROC Audit function The ROC shall perform audits or review audits perlfmed by designated individuals on its behalf at least annually. The audit shall include. but not be limited to. the following items.

a. Facility operations for conlormance to the technical specifications and upplicable license or other conditions.

b. Retraining and requalification of operators according to the Requalification Plan.

c. Ihe result of action taken to correct those dcleciencies that may occur ill the reactor facility equipment, systems, structures, procedures or methods of operation that affect reactor safety.

d. The flacility Emergency Plan (EP) and implementing procedures including written reports of any drills or exercises carried out.

6.3 Radiation Safety As delineated in section 6.1.2.e, the UCI Radiation Safety Officer (RSO) is responsible for implementation of the radiological safety program at the reactor facility in accordance with applicable federal and state of California standards and regulations. The program shall use the guidelines ofANSI/ANS 15.11- 2004.

The RSO shall be responsible lor an annual audit ul the radiation safety program.

6.4 Operating Procedures Written procedures, reviewed and approved by the ROC, shall be in effect and implemented for the lollowing items. The procedures shall be adeLLQuate to assure the safety of the reactor but not preclude the use of independent judgment and action should the situation require such.

a. Startup, operation, and shutdown of the reactor.

b. Installation or removal of fuel elements, control rods, experiments, and experimental facilities.

c. Maintenance of major components of systems that could have an effect on reactor safety.

d. Surveillance checks, calibrations and inspections required by the technical specifications or that could have an effect on reactor safety.

e. Personnel radiation protection, including provisions to maintain personnel exposures as low as reasonably achievable (ALARA).

f. Administrative controls for operations and maintenance, and for the conduct of irradiations or experiments that could affect reactor salety.

g. Implementation of required plans including Emergency (EP) and Physical Security (PSP) plans.

UCI Technical Specifications page 33

h. Shipping and/or transfer of radioactive materials.

Substantive changes to procedures shall be made only with the approval of the ROC. Temporary changes to procedures that do not change their original intent may be made by the Reactor Supervisor. All such temporary changes to procedures shall be documented and subsequently reviewed by the Reactor Director and the ROC. Substantive changes affecting radiological safety shall be made only with the approval of the RSO. Temporary, minor, changes in radiological safety procedures may be made by the Reactor Supervisor, but shall be reported to the RSO within 30 days.

6.5 Experiment Review and Approval Approved experiments shall be carried out in accordance with established and approved procedures.

Procedures for experiment review and approval shall include the following requirements.

a. All new experiments or class of'experiment shall be reviewed and approved by the ROC and approved in writing by the Reactor Director. The review shall include analysis by the RSO or other designated radiation safety personnel.

b. Substantive changes to existing experiments or classes shall be made only after review by the ROC and RSO or their designees. Minor changes that do not significantly alter the experiment may be approved by a senior reactor operator (SRO),and shall be submitted to the ROC for review at its next scheduled meeting.

6.6 ReUuired Actions 6.6.1 Actions To Be Taken In Case of a Safety Limit Violation.

In the event the safety limit on fuel temperature is exceeded:

a. the reactor shall be shut down and reactor operation shall not be resumed until authorized by the NRC;

b. the event shall be reported immediately to the Reactor Director, the ROC chairperson, and the RSO;

c. the event shall be reported to the NRC Operations Center within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and followed by a written report sent within 14 days to the NRC Document Control Desk; and

d. a report, and any applicable follow-up report, shall be prepared and reviewed by the ROC, for submission to NRC, describing:

1) applicable circumstances leading to the violation including, where known, the cause and contributing factors;

2) effects of the violation upon reactor facility components, systems, or structures, and on the health and safety of personnel and the public; and

3) corrective action to prevent recurrence.

UCI Technical Specifications page 34

6.6.2 Actions to be Taken in the Case of Events other than a Safety Limit Violation.

In the event that an occurrence of the type identified in section 6.7.2, other than exceeding the safety limit on fuel temperature:

a. the reactor shall be secured and the Reactor Director and Supervisor notified;

b. operation shall not be resumed until authorized by the Reactor Director: and

c. the occurrence shall be reported to NRC as required in Section 6.7.2 of these specifications, and reviewed by the ROC at their next meeting.

6.7 Reports In addition to the requirements of applicable regulations, and in no way substituting for them, reports shall be made to the NRC as listed below. All written reports shall be directed to the Document Control Desk, USNRC, Washington, D. C. 20555.

6.7. 1. Annual Operating Report.

A routine annual report shall be submitted by the Reactor Director to NRC at the end of each 12-month period Ior operations 1or the preceding year's activities between July I"sthrough June 3 0 th.

The report shall Hincude:

a. a brief narrative summary of operating experience (including experiments performed) and a tabulation showing the energy generated by the reactor (in megawatt hours), the amount of pulse operation, and the number of hours the reactor was critical;

b. the number of unplanned shutdowns and inadvertent scrams, including the reasons therefore, and corrective actions taken (if'any) to reduce recurrence;

c. a tabulation of major preventive and corrective maintenance operations having safety significance:

d. a tabulation of major changes in the reactor fiacility and procedures, and tabulations of new experiments that are significantly different from those performed previously, including a summary of safety evaluations perflormed to assess that they' do not require prior NRC approval and are authorized by 10 CFR 50.59;

e. a summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective control of the facility as measured at or prior to 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, a statement to this effect is sufficient;

f. a summarized result of environmental surveys performed outside the facility; and

g. a summary of radiation exposures received by facility personnel and visitors, where such exposures are greater than 25% of that allowed.

UCI Technical Speci fications page 35

6.7.2 Special Reports.

a. A report shall be made not later than the following working day by telephone to the NRC Operations Center, and confirmed in writing, to be followed by a written report that describes the circumstances of the event within 14 days, of any of the following:

I ) violation ola salety limit (fuel temperature);

2) release of radioactivity from the site above allowed limits;

3) operation with actual safety sNstem settings for required systems less conservative than the limiting safety system settings in these speci lications;

4) operation in violation of limiting conditions for operation unless prompt remedial action is taken as permitted in section 3;

5) a required reactor saf'et\ system component malfunction that renders or could render the safety system incapable of perlbrming its intended safety function. If the malfunction or condition is caused by maintenance, then no report is required;

6) an unanticipated or uncontrolled change in reactivity greater than one dollar. Reactor trips resulting from known cause are excluded;

7) abnormal or significant degradation in reactor fuel or cladding, or both, coolant boundary, or confinement boundary (excluding minor leaks) where applicable: or

8) an observed inadequacy in implementation of administrative or procedural controls such that the inadequacy causes or could have caused the existence or development olfan unsafe condition with regard to reactor operations.

b. A report shall be made within 30 days (in writing) of:

I) permanent significant changes in facility organization; and

2) significant changes in the transient or accident analyses as described in the SAR.

UCI Technical Specifications page 36

6.8 Records In addition to the requirements of applicable regulations, and in no way substituting therefore, records and logs shall be prepared and retained for periods as described here. Records may be in a variety of formats.

6.8.1 Records to be retained for a period of at least 5 years or for the lifeC of"the component involved if less than 5 years.

a. normal reactor facility operation, but not including supporting documentation such as checklists, log sheets, etc., which shall be retained Ior one year-

b. principal maintenance activities,

c. reportable occurrences;

d. surveillance activities required by the Technical Specifications;

e. reactor facility radiation and contamination surveys; 1' experiments performed with the reactor;

g. fuel inventories, receipts and shipments:

h. approved changes in operating procedures; and

i. ROC records of meetings and audit reports.

6.8.2 Records to be retained for at least one certification cycle.

Records of retraining and requalification of licensed operators (and SRO's) shall be retained at all times the individual has duties as an operator or his or her license is renewed.

6.8.3 Records to be retained for the lifetime of the reactor facility.

The following records shall be retained Ior the li'etime of the facility. Applicable annual reports containing this information may also be used as records.

a. Gaseous and liquid radioactive effluents released to the environs.

b. Results of of-fsite environmental monitoring surveys.

c. Radiation exposures for all personnel that were monitored.

d. Drawings of the reactor facility and safety related components.

UCI Technical Specifications page 37