ML101450410

Possession Only License for the University of Arizona Research Reactor

ML101450410
Person / Time
Site:	05000113
Issue date:	05/20/2010
From:	Williams J Univ of Arizona
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML101450410 (79)

Text

THE UNIVERSITY OF Nuclear Reactor Laboratory John G. Williams, Director Engineering Building (20)

P. O. Box 210020 Tucson, Arizona 85721-0020 ARIZONAG e-mail: jgw~engr.arizona.edu voice: (520) 621-9729 FAX: (520) 621-8096 TUCSON ARIZONA May 20, 2010 U.S. Nuclear Regulatory Commission 10 CFR 50 ATTN: Document Control Desk Washington, DC 20555-0001

Subject:

Possession Only License for the University of Arizona Research Reactor, Facility License No. R-52, Docket No. 50-113 This letter requests a 'possession only' revision to our current operating license and submits revised Technical Specifications. Please delete the words "use, and operate" from the following part of our license:

"Pursuant to Section 104c of the Act and 10 CFR 50 "Domestic Licensing of Production and Utilization Facilities," to possess, useand eperase the facility at the designated location in Tucson, Arizona, in accordance with the procedures and limitations set forth in this license."

The University of Arizona's current reactor operating license expires on May 22, 2010. On or before midnight on May 22 we will:

" Cease reactor operations,

" Partially unload fuel from Arizona Research Reactor so that it contains insufficient fissile material present in the reactor to attain criticality under optimum available conditions of moderation and reflection,

" Maintain the reactor in a "secured" condition per the definition of Reactor Secured part (a),

" Continue our possession of the nuclear fuel,

• Maintain our surveillance activities, and

" Maintain the facility, including the storage, control and maintenance of the spent fuel, in a safe condition until the defueling is completed.

By prior agreement, the DOE through its Reactor Fuel Assistance Program will assist in defueling our nuclear reactor following the end of operations.

I declare under penalty of perjury that the foregoing is true and correct. Executed on May 20, 2010.

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V Zý*ýJohn G. Williams, Director University of Arizona Research Reactor Attachments Amendment 19 Technical Specifications, University of Arizona Research Reactor A Q-)iý,

Amendment 19 Technical Specifications, University of Arizona Research Reactor-annotated

Possession Only License for the University of Arizona Research Reactor, Facility License No.

-R-52, Docket No. 50-113 dated May 20, 2010 Copies to:

Linh Tran, NRC/NRR/DPR/PRLB Mike Morlang, NRC/NRR/DPRIPROB Patrick Issac, NRC/NRR/DPR/PROB U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 U.S. NRC Region IV Texas Health Resources Tower 612 East Lamar Blvd.

Arlington, TX 76011-4005 Dr. Leslie Tolbert Vice President for Research University of Arizona P.O. Box 210066 Tucson, AZ 85721-0066 Acting Director Arizona Research Laboratories University of Arizona Gould-Simpson Bldg. 1011 P.O. Box 210077 Tucson, AZ 85721-0077 Daniel Silvain, Director Radiation Control Office University of Arizona P.O. Box 245101 Tucson, AZ 85724-5 101

Technical Specifications, Amendment No. 19 TECHNICAL SPECIFICATIONS I FOR THE UNIVERSITY OF ARIZONA TRIGA RESEARCH REACTOR FACILITY LICENSE R-52 Amendment 19 This document includes the Technical Specifications and the bases for the Technical Specifications.

The bases provide the technical support for the individual Technical Specifications and are included for information purposes only. The bases are not part of the Technical Specifications and they do not constitute limitations or requirements to which the licensee must adhere.

Technical Specifications, Amendment No. 19 INDEX Page number 1.0 DEFINITIONS 3 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 7 2.1 Safety Limit - Fuel Temperature 7 3.0 LIMITING CONDITIONS FOR OPERATION AND L[MITING DECOMMISSIONING CONDITIONS 8 3.1 Reactivity Limits 8 3.2 Reactor Instrumentation 9 3.3 Ventilation System 10 4.0 SURVEILLANCE REQUIREMENTS 11 4.1 Fuel 11 4.2 Control Rods 12 4.3 Radiation Monitoring Equipment 13 4.4 Maintenance 14 4.5 Pool Water Conductivity 1.5 5.0 DESIGN FEATURES 16 5.1 Reactor Fuel 16 5.2 Reactor Building 17 5.3 Fuel Storage 18 6.0 ADMINISTRATIVE CONTROLS 19 6.1 Organization 19 6.2 Review 21 6.3 Operations 22

a. Operating Procedures 22

b. ALARA Program 6.4 Action to be Taken in the Event a Safety Limit is Exceeded 2 6.5 Action to be Taken in the Event of a Reportable Occurrence 24 6.6 Plant Operating Records 25 6.7 Reporting Requirements 26 6.8 Review of Experiments 29 7.0 DECOMMISSIONING PLAN 31 7.1 Incorporation of the Decommissioning Plan 31 7.2 Changes to the Decommissioning Plan 31 7.3 Characterization Report 31 7.4 Final Status Survey Plan 3 7.5 Release Criteria 32 University of Arizona Research Reactor

Technical Specifications, Amendment No. 19 1.0 DEFINITIONS Channel - A channel is a combination of sensors, electronic circuits, and output devices connected by the appropriate communications network in order to measure and display the value of a parameter.

Channel Calibration - A channel calibration is an adjustment of a 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 include a Channel Test.

Channel Check - A channel check is a qualitative verification of acceptable performance by observation of channel behavior. The verification shall include comparison of the channel output with previous readings or performance or with other independent channels or systems measuring the same variable, whenever possible.

Channel Test - A channel test is the introduction of a signal into the channel for verification that it is operable.

Cold Critical - The reactor is in the cold critical condition when it is critical with the fuel and bulk water temperatures the same (-20'C).

Decommissioning Activities - Decommissioning activities are the physical dismantlement or permanent removal from service of systems and components described in the SAR.

Decommissioning activities, however, do not include the removal of fuel.

Experiment - An experiment is any device or material, not normally part of the reactor, which is introduced into the reactor for the purpose of exposure to radiation, or any operation which is designed to investigate non-routine reactor characteristics.

Experimental Facilities - Experimental facilities are the thermal column, pneumatic transfer systems, central thimble, rotary specimen rack, beam tube, and the in-core facilities.

Limiting Conditions for Operation - Limiting Conditions for Operation (LCO) are administratively established constraints on equipment and operational characteristics which shall be adhered to during operation of the reactor.

Limiting Decommissioning Conditions - Limiting Decommissioning Conditions (LDC) are administratively established constraints on equipment and operational characteristics which shall be adhered to during decommissioning activities.

Limiting Safety System Setting (LSSS) - The LSSS is the actuating level for automatic protective devices related to those variables having significant safety functions.

Manual Mode - The reactor is in the manual mode when the reactor mode selection switch is in the manual or automatic position. In this mode, reactor power is held constant or is changed on periods of approximately one second or longer.

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Technical Specifications, Amendment No. 19 Measured Value - The Measured Value is the value of a parameter as it appears on the output of a channel.

Movable Experiment - An experiment is movable when it is intended that all or part of the experiment may bemoved in or near the core or into and out of the reactor while the reactor is operating.

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

Operating - Operating means a component or system is performing its intended function.

Pulse Mode - The reactor is in the pulse mode when the reactor mode selection switch is in the pulse position. In this mode, reactor power may be increased on periods less than one second by motion of the transient control rod.

Reactivity Worth of an Experiment - The reactivity worth of an experiment is the maximum value of the reactivity change that would occur as a result of planned changes or credible malfunctions that alter experiment position or configuration.

Reactor Committee - The group of persons at the University who are assigned responsibility for review and audit of facility operation and review of changes and experiments in accordance with 10 CFR 50.59.

Reactor Operating - The reactor is operating whenever it is not secured or shutdown.

Reactor Safety Systems - Reactor Safety Systems are those systems, including associated input channels, which are designed to initiate automatic reactor protection or to provide information for initiation of manual protective action.

Reactor Secured - The reactor is secured when:

a. It contains insufficient fissile material or moderator present in the reactor, adjacent experiments or control rods, to attain criticality under optimum available conditions of moderation and reflection, or

b. 1. The minimum number of neutron absorbing control rods are fully inserted or other safety devices are in shutdown position, as required by technical specifications, and

2. The console key switch is in the off position and the key is removed from the lock, and

3. No work is in progress involving core fuel, core structure, installed control rods, or control rod drives unless they are physically decoupled from the control rods, and

4. No experiments in or near the reactor are being moved or serviced that have, on movement, a reactivity worth of one dollar or more.

Reactor Shutdown - The reactor is in a shutdown condition when sufficient control rods are inserted to assure that it is subcritical by at least $1.00 of reactivity.

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Technical Specifications, Amendment No. 19 Reportable Occurrence - A Reportable Occurrence is any of the following which occurs during reactor operation:

a. Operation with actual safety-system settings for required systems less conservative than the limiting safety-system settings specified in Technical Specification 2.2.

b. Operation in violation of limiting conditions for operation established in the Technical Specifications.

c. A reactor safety system component malfunction which renders or could render the reactor safety system incapable of performing its intended safety function unless the malfunction or condition is discovered during maintenance tests or periods of reactor shutdown.

d. Any unanticipated or uncontrolled change in reactivity greater than one dollar.

e. Abnormal and significant degradation in reactor fuel, cladding, or coolant boundary which could result in exceeding of prescribed radiation exposure or release limits.

f. An observed inadequacy in the implementation of either administrative or procedural controls which could result in operation of the reactor outside the limiting conditions for operation.

g. Release of radioactivity from the site above limits specified in 10CFR20.

Control Rod - 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 losses. A control rod may be coupled to its drive unit allowing it to perform a safety function when the coupling is disengaged.

Transient Rod - The transient rod is a control rod with scram capabilities that is capable of providing rapid reactivity insertion to produce a pulse.

Safety Limit - A Safety Limit is a limit on an important process variable which is found to be necessary to reasonably protect the integrity of certain of the physical barriers which guard against the uncontrolled release of radioactivity. The principal physical barrier is the fuel element cladding.

Secured Experiment - A Secured Experiment is any experiment, experimental facility, 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 the result of credible malfunctions.

Shall, Should, and May - The word "shall" is used to denote a requirement, the word "should" denotes a recommendation, and the word "may" denotes permission, neither a requirement nor a recommendation.

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Technical Specifications, Amendment No. 19 Shutdown Margin - Shutdown Margin is the reactivity existing when the most reactive control rod is fully withdrawn from the core and the other control rods are fully inserted into the core.

Time Interval - The average over any extended period for each surveillance time item shall be the normal surveillance time; e.g., for a two-year interval, the average shall not exceed two years.

a. Biennially - at two-year intervals (interval not to exceed 30 months)

b. Annually - at one-year intervals (interval not to exceed 15 months)

c. Semiannually - at 6-month intervals (interval not to exceed seven and one-half months)

d. Quarterly - at 3-month intervals (interval not to exceed four months)

e. Monthly - at one-month intervals (interval not to exceed six weeks)

f. Weekly - at seven-day intervals (interval not to exceed ten days)

g. Daily - (must be done during the calendar day)

Any extension of these intervals shall be occasional and for a valid reason shall not affect the average as defined.

Untried Experiment - An untried experiment is any experiment not previously performed in this reactor.

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Technical Specifications, Amendment No. 19 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 Safety Limit - Fuel Temperature Applicability This specification applies to the reactor fuel temperature Obiective The objective is to define a fuel temperature below which it can be predicted with confidence that no damage to the fuel elements will occur.

Specification The temperature of the fuel shall not exceed 1000°C under any conditions of operation.

Basis The recommended limiting design basis parameter for TRIGA fuel is the fuel temperature. A fuel temperature safety limit of 11 50'C for stainless-steel-clad U-ZrH 1.65 TRIGA fuel is recommended as a design value to preclude the loss of clad integrity when the clad temperature is below 500'C (Simnad, GA Report E-1 17-833, The U-Zr H Alloy: Its Properties and Use in TRIGA Fuel, Feb.

1980, p. 4-1). The criterion for assuring the integrity of a TRIGA fuel element at the University of Arizona is that the fuel temperature be maintained below 1000°C, which is well below the recommended value. It has been shown by analysis and by measurements on other TRIGA reactors that a power level of 1000 kW corresponds to a peak fuel temperature of approximately 400'C.

Pulsing with a reactivity input of $3.25 will give a peak fuel temperature of approximately 460'C.

The LSSS become inapplicable, once reactor operations have permanently ceased. Delete this section.

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Technical Specifications, Amendment No. 19 3.0 LIMITING CONDITIONS FOR OPERATION AND LIMITING DECOMMISSIONING CONDITIONS 3.1 Reactivity Limits Applicability These specifications apply to the reactivity condition of the reactor.

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

Specifications The reactor shall not be operated.

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Technical Specifications, Amendment No. 19 3.2 Reactor Instrumentation Applicability This specification applies to the information which must be available during fuel movement and during decommissioning activities.

Objective The objective is to require that sufficient information is available to the operator to assure safe movement of fuel and decommissioning.

Specification Reactor fuel shall not be moved and decommissioning activities shall not be conducted unless the measuring channels described in the following table are operable and theinformation is available in the control room:

MINIMUM MEASU~RING CHANNEL NUMBER ACTiIVIT~Y IN WHICH OPERABLEE REQU. IRED wide-range log power level 1 fuel movement (startup count rate) reactor period 1 fuel movement fuel movement and area radiation monitors 2 decommissioning activities rradiation fuel movement and particulate air 1tdecommissioning activities reactor water activity monitor 1 fuel movement Bases The wide range log power and reactor period channels assure that indications of subcritical reactor power level changes are available during fuel movement.

The radiation monitors provide information to operating personnel of radiation above a preset level so that there will be sufficient time to evacuate the facility or take action to prevent the release of radioactivity to the surroundings.

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Technical Specifications, Amendment No. 19 3.3 Ventilation System Applicability This specification applies to the operation of the reactor facility ventilation system.

Obiective The objective is to assure that the ventilation system is in operation to mitigate the consequences of the possible release of radioactive materials.

Specification Fuel shall not be moved and decommissioning activities shall not be conducted unless the facility ventilation system is operable with a minimum air withdrawal rate of 500 cfm.

Basis It is shown in The Safety Analysis Report that operation of the ventilation system reduces doses in the reactor facility in the event of a TRIGA fuel element failure.

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Technical Specifications, Amendment No. 19 4.0 SURVEILLANCE REQUIREMENTS 4.1 Fuel Applicability This specification applies to the surveillance requirements for the fuel elements.

Objective The objective is to assure that the dimensions of the fuel elements remain within acceptable limits.

Specifications

a. All fuel elements shall be removed from the core and visually inspected for evidence of deterioration of cladding, (including at least corrosion, erosion, wear, cracking, and weld integrity) at least once every five years.

b. A fuel element indicating an elongation greater than 1/4 inch over its original length or a lateral bending greater than 1/16 inch over its original bending shall be considered to be damaged and shall be recorded as such in the fuel inventory logs.

Basis The most severe stresses induced in the fuel elements result from pulse operation with high reactivity input, during which differential expansion between the fuel and the cladding occurs and the pressure of the gases within the elements increases sharply. The above limits on the allowable distortion of a fuel element correspond to strains that are considerably lower than the strain expected to cause rupture of a fuel element.

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Technical Specifications, Amendment No. 19 4.2 Control Rods Applicability This specification applies to the surveillance requirements for the control rods.

Objective The objective is to assure the integrity of the fuel-followed control rods.

Specification

a. The fuel-followed control rods shall be visually inspected for deterioration biennially.

Basis The visual inspection of the fuel-followed control rods is made to determine whether the control rods are preserving the integrity of fuel.

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Technical Specifications, Amendment No. 19 4.3 Radiation Monitoring Equipment Applicability This specification applies to the radiation monitoring equipment required by Section 3.2 of these specifications.

Objective The objective is to assure that the radiation monitoring equipment is operating and to verify the appropriate alarm settings.

Specification

a. The alarm set points for the radiation monitoring instrumentation shall be verified prior to fuel movement or conduct of decommissioning activities, on each day when they are performed.

b. The radiation monitoring equipment shall be calibrated annually.

Basis Verification of the alarm set points of radiation monitoring instrumentation will assure that sufficient information to provide protection against radiation exposure is available.

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Technical Specifications, Amendment No. 19 4.4 Maintenance Applicability This specification applies to the surveillance requirements following maintenance of a control or safety system.

Obiective The objective is to assure that a system is operable before being used after maintenance has been performed.

Specification

a. Following maintenance or modification of a control or safety system or component, it shall be verified that the system is operable prior to its return to service. A system shall not be considered operable-until after it is successfully tested.

b. Any additions, modifications, or maintenance to the ventilation system, the core and its associated support structure, the pool or its penetrations, the pool coolant system, the rod drive mechanism, or the reactor safety system shall be made and tested in accordance with the specifications to which the systems were originally designed and fabricated or to specifications approved by the Reactor Committee.

c. A licensed reactor operator shall be present during maintenance of the reactor control and safety system.

Basis This specification relates to changes in reactor systems which could directly affect the safety of the reactor. Changes or replacements to these. systems which meet the original design specifications are considered to meet the presently accepted operating criteria.

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Teclmical Specifications, Amendment No. 19 4.5 Pool Water Conductivity Applicability This specific action applies to surveillance of pool water conductivity.

Objective The objective is to assure that pool water mineral content is maintained at an acceptable level.

Specification The conductivity of bulk coolant water shall be verified to be within specified limits at least monthly.

Basis Based on experience, in which pool water conductivity changes slowly with time, observation at these intervals provides acceptable surveillance of conductivity to assure that accelerated fuel clad corrosion does not occur.

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Technical Specifications, Amendment No. 19 5.0 DESIGN FEATURES 5.1 Reactor Fuel Applicability This specification applies to the fuel elements stored in the reactor pool.

Objective The objective is to assure that the fuel elements are of such a design and fabricated in such a manner as to permit their use with a high degree of reliability with respect to their mechanical integrity.

Specifications

a. Standard Fuel Element: The standard fuel element shall be of the TRIGA type and shall contain uranium-zirconium hydride, clad in 0.020 inch of 304 stainless steel. It shall contain a maximum of 9.0 weight percent uranium which has a maximum enrichment less than 20 percent. There shall be 1.55 to 1.80 hydrogen atoms to 1.0 zirconium atom.

b. Loading: With the exception of one fuel-followed control element (the "regulating rod") no fuel elements shall be placed within the B- or C- rings of the core.

Basis This type of fuel element has a long history of successful use in TRIGA reactors.

Specification b ensures that the fuel stored within the core structure cannot attain a value of keff greater than 0.9.

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Technical Specifications, Amendment No. 19 5.2 Reactor Building and Decommissioning Site Applicability This specification applies to the facility which houses the reactor and the residual facility and site to which the Decommissioning Plan applies.

Objective The objective is to assure that provisions are made to restrict the radioactivity released into the environment.

Specifications

a. The reactor shall be housed in a closed room of a facility designed to restrict leakage.

b. The free volume of the reactor room shall be at least 6,000 cubic feet.

c. All air or other gases exhausted from the reactor room during decommissioning activities shall be released at a minimum of 12 feet above ground level.

d. The reactor facility shall be equipped with a ventilation system capable of exhausting air or other gases from the reactor room from a stack at a minimum of 50 feet above ground level under emergency conditions.

e. During decommissioning activities within the reactor room, openings to the room other than those designed for exhaust air and gases shall be closed except for required access and when materials prepared for shipment are being removed.

f. During decommissioning activities outside the reactor room, components that are to be removed shall be enclosed in a manner designed to restrict leakage and to restrict access, before being dismantled.

Basis In order that the movement of air can be controlled, the facility contains no windows that can be opened. Under emergency conditions the room air is exhausted through a filter and discharged, through a stack at a minimum of 50 feet above ground to provide dilution.

Specification f. applies only to equipment described in the SAR which is outside the reactor room:

parts of the water purification system and the cooling system. All other decommissioning activities will be confined to the footprint described in SAR section IVa, designated as a controlled access area.

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Technical Specifications, Amendment No. 19 5.3 Fuel Storage Applicability This specification applies to the storage of reactor fuel at times when it is not in the reactor core.

Objective The objective is to assure that fuel which is being stored will not become supercritical and will not reach unsafe temperatures.

Specifications

a. All fuel elements shall be stored in a geometrical array where the value of keff is less than 0.9 for all conditions of moderation and reflection using light water.

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 800'C.

Basis Specification 5.3a assures that unplanned criticality will not occur in fuel storage racks.

Specification 5.3b is based on a fuel temperature limit of 950'C to assure fuel clad integrity when the clad temperatures can equal the fuel temperature (Simnad, G. A. Report E- 117-833, February 1980, p.4-1)

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Technical Specifications, Amendment No. 19 6.0 ADMINISTRATIVE CONTROLS 6.1 Organization

a. The reactor facility shall be maintained by the Nuclear Reactor Laboratory (NRL) at the University of Arizona. The Nuclear Reactor Laboratory Director shall report to the Vice President for Research and Graduate Studies at the University of Arizona as shown in the diagram below.

b. The reactor facility shall be under the supervision of a licensed' senior operator for the reactor. He shall be responsible for assuring that all operations are conducted in a safe manner and within the limits prescribed by applicable federal regulations, by the flacility license, and by the provisions of the Reactor Committee.

c. There shall be a Health Physicist responsible for assuring the safety of reactor operations from the standpoint of radiation protection.

d. An NRC-licensed operator must be present in the control room when the key switch is on.

An operator and one other person authorized by the Reactor Supervisor must be present in the Reactor Laboratory whenever the reactor is not shut down.

The above organizational chart from our Decommissioning Plan replaces the organizational chart below when decommissioning activities commence. Until then, the following chart remains applicable.

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Technical Specifications, Amendment No. 19 University of Arizona Research Reactor Page 20

Technical Specifications, Amendment No. 19 6.2 Review

a. There shall be a Reactor Committee which shall review reactor operations and decommissioning activities to assure that the facility is maintained in a manner consistent with public safety and within the terms of the facility license.

b. The responsibility of the Committee includes, but is not limited to, the following:

1. Review and approval of experiments utilizing the reactor facilities;

2. Review and approval of all proposed changes to the facility, procedures, and Technical Specifications;

3. Determination of whether a proposed change, test, or experiment would constitute a license amendment pursuant to 10 CFR 50.59(c)(2) as outlined in UARR 165;

4. Review and approval of all proposed changes to the Decommissioning Plan, provided such changes meet the specifications listed in 7.2

5. Review of the operation and operational records of the facility;

6. Review of abnormal performance of plant equipment and operating anomalies; and

7. Review of unusual or abnormal occurrences and incidents which are reportable under 10 CFR 20 and 10 CFR 50.

8. Review and audit of the retraining and requalification program for the operating staff.

9. Biennial audit of the Emergency Plan.

c. The Committee shall be composed of at least five members, and shall include a health physicist and members competent in the field of reactor operations, radiation science, or reactor engineering. The membership of the Committee shall be such as to maintain a high level degree of technical proficiency.

d. The Committee shall establish a written charter defining such matters as the authority of the Committee, review and audit functions, and other such administrative provisions as are required for effective functioning of the Committee. Minutes of all meetings of the Committee shall be kept and submitted to committee members and to the Vice President for Research and Graduate Studies in a timely manner.

e. A quorum of the Committee shall consist of not less than three members of the Committee and shall include the chairman or his designee.

f. The Committee shall meet at least quarterly.

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Technical Specifications, Amendment No. 19 6.3 Operations

a. Operating Procedures Written procedures, reviewed and approved by the Reactor Committee, shall be in effect and followed for the following items. The procedures shall be adequate to assure the safeLy of tile reactor, but should not preclude the use of independent judgment and action should the situation require such.

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

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

3. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms, suspected primary coolant system leaks, and abnormal reactivity changes.

4. Emergency conditions involving potential or actual release of radioactivity, including provisions for evacuation, re-entry, recovery, and medical support.

5. Maintenance procedures which could have an effect on reactor safety.

6. Periodic surveillance of reactor instrumentation and safety system, area monitors and continuous air monitors.

7. Decommissioning activities Substantive changes to the above procedures shall be made only with the approval of the Reactor Committee. Temporary changes to the procedures that do not change their original intent may be made with the approval of the Reactor Laboratory Director. All such temporary changes to procedures shall be documented and subsequently reviewed by the Reactor Committee.

b. ALARA Program A program shall be established to assure that radiation exposures and releases are kept as low as reasonably achievable.

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Technical Specifications, Amendment No. 19 6.4 Action to be Taken in the Event a Safety Limit is Exceeded In the event a safety limit is exceeded, or thought to have been exceeded:

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

b. An immediate report of the occurrence shall be made to the Chairman of the Reactor Committee and reports shall be made to the NRC in accordance with Section 6.7 of these specifications.

c. A report shall be made which shall include an analysis of the causes and extent of possible resultant damage, efficiency of corrective action, and recommendations for measures to prevent or reduce the probability of recurrence. This report shall be submitted to the Reactor Committee for review, and a similar report submitted to the NRC when authorization to resume operation of the reactor is requested.

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Technical Specifications, Amendment No. 19 6.5 Action to be Taken in the Event of a Reportable Occurrence In the event of a Reportable Occurrence, the following action shall be taken:

a. The Reactor Laboratory Director shall be notified and corrective action taken prior to resumption of the operation involved.

b. A report shall be made which shall include an analysis of the cause of the occurrence, efficacy of corrective action and recommendations for measures to prevent or reduce the probability of reoccurrence. This report shall be submitted to the Reactor Committee for review.

c. A report shall be submitted to the NRC in accordance with Section 6.7 of these specifications.

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Teclmical Specifications, Amendment No. 19 6.6 Plant Operating Records In addition to the requirements of applicable regulations, and in no way substituting therefore, records and logs of the following items shall be prepared and retained for a period of at least 5 years (except as otherwise specified in the Commission's regulations);

a. Normal plant operation (but not including supporting documents such as checklists, and recorder charts, which shall be maintained for a period of at least one year);

b. Principal maintenance activities;

c. Reportable Occurrences;

d. Equipment and component surveillance activities required by the Technical Specification;

e. Experiments performed with the reactor; Logs and records of the following items shall be prepared and retained for the life of the facility.

f. Gaseous and liquid radioactive effluents released to the environs;

g. Off-site environmental monitoring surveys;

h. Fuel inventories and transfers;

i. Facility radiation and contamination surveys;

j. Radiation exposures for all personnel;

k. Updated, corrected, and as-built drawings of the facility; and

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Technical Specifications, Amendment No. 19 6.7 Reporting Requirements In addition to the requirements of applicable regulations, and in no way substituting therefore, reports shall be made to the NRC as follows:

a. A report within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and telegraph or telefax (FAX) to the responsible NRC organization as listed in the Emergency Kit and posted as deemed necessary by the Reactor Committee of:

1. Any accidental off-site release of radioactivity above limits permitted by 10 CFR 20, whether or not the release resulted in property damage, personal injury, or exposure;

2. Any violation of a Safety Limit; and

3. Any reportable occurrences as defined in Section 1.0 (Reportable Occurrence) of these specifications in writing.

b. A written report within ten days to the U. S. Nuclear Regulatory Commission, Attn:

Document Control Desk, Washington D.C. 20555, with a copy to the responsible NRC facility inspector of:

1. Any significant variation of measured values from a corresponding predicted value of previously measured value of safety-connected operating characteristics occurring during operation of the reactor;

2. Incidents or conditions relating to operation of the facility which prevented or could have prevented the performance of engineered safety features as described in these specifications;

3. Any reportable occurrences as defined in Section 1.0 of these specifications; and

4. Any violation of a Safety Limit.

5. Any accidental off-site release of radioactivity above limits permitted by 10 CFR 20, whether or not the release resulted in property damage, personal injury, or exposure.

c. A written report within 30 days to the U.S. Nuclear Regulatory Commission, Attn:

Document Control Desk, Washington D.C. 20555, with a copy to the responsible NRC facility inspector of:

1. Any substantial variance from performance specifications contained in these specifications or in the Safety Analysis Report;

2. Any significant change in the transient or accident analysis as described in the Safety Analysis Report; University of Arizona Research Reactor Page 26

Technical Specifications, Amendment -No. t9

3. Any changes in facility organization; and

4. Any observed inadequacies in the implementation of administrative or procedural controls.

d. A written report within 60 days after completion of startup testing of the reactor to the U. S.

Nuclear Regulatory Commission, Attn: Document Control Desk, Washington D.C. 20555, with a copy to the responsible NRC facility inspector of:

1. An evaluation of facility performance to date in comparison with design predictions and specifications; and

2. A reassessment of the safety analysis submitted with the license application in light of measured operating characteristics when such measurements indicate that there may be substantial variance from prior analysis.

e. A written annual report within 60 days following the 30th of June each year to the U.S.

Nuclear Regulatory Commission, Attn: Document Control Desk, Washington D. C. 20555, with a copy to the responsible NRC facility inspector of:

1. A brief narrative summary of (1) operating experience (including experiments performed), (2) changes in facility design, performance characteristics, and operating procedures related to reactor safety and occurring during the reporting period, and (3) results of surveillance tests and inspections;

2. Tabulation of the energy output (in megawatt days) of the reactor, amount of pulse operation, hours reactor was critical, and the cumulative total energy output since initial criticality;

3. The number of emergency shutdowns and inadvertent scrams, including reasons therefore;

4. Discussion of the major maintenance operations performed during the period, including the effect, if any, on the safety of the operation of the reactor, and the reasons for any corrective maintenance required;

5. A brief description including a summary of the safety evaluations of changes in the facility or in procedures and of tests and experiments carried out pursuant to Section 50.59 of 10 CFR Part 50;

6. A summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective control of the licensee as measured at or prior to the point of such release or discharge; University of Arizona Research Reactor Pagc 27

Technical Specifications, Amendment No. 19 Liquid Waste (summarized on a monthly basis)

(a) Radioactivity discharged during the reporting period.

(1) Total radioactivity released (in curies).

(2) The limiting concentrations (10CFR20, Appendix B) used and the isotopic composition if greater than 1 x 10- 7 microcuries/cc for fission and activation products.

(3) Total radioactivity (in curies), released by nuclide, during the reporting period, based on representative isotopic analysis.

(4) Average concentration at point of release (in microcuries /cc) during the reporting period.

(b) Total volume (in gallons) of effluent water (including diluent) during periods of release.

Gaseous Waste (summarized on a monthly basis)

(a) Radioactivity discharged during the reporting period (in curies) for:

(1) Gases.

(2) Particulates with half lives greater than eight days.

(b) The limiting concentrations (10CFR20, Appendix B) used and the estimated activity (in curies) discharged during the reporting period, by nuclide, for all gases and particulates based on representative isotopic analysis.

Solid Waste (a) The total amount of solid waste packaged (in cubic feet).

(b) The total activity involved (in curies).

(c) The dates of transfer or shipment and disposition

7. A summary of radiation exposures received by facility personnel and visitors, including dates and time of significant exposures, and a summary of the results of radiation and contamination surveys performed within the facility; and

8. A description of any environmental surveys performed outside the facility.

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Technical Specifications, Amendment No. 19 6.8 Review of Experiments

a. All proposed new experiments utilizing the reactor shall be evaluated by the experimenter and the Reactor Committee. The evaluation shall be reviewed by a licensed Senior Operator of the facility (and the Health Physicist when appropriate) to assure compliance with the provisions of the utilization license, the Technical Specifications, 10 CFR 20, and the requirements of 10 CFR 50.59. If, in his judgment, the experiment meets with the above provisions and does not constitute a threat to the integrity of the reactor, he shall submit it to the Reactor Supervisor for scheduling or to the Reactor Committee -forfinal approval as indicated in Section 6.2 above. When pertinent, the evaluation shall include:

1. The reactivity worth of the experiment;

2. The integrity of the experiment, including the effects of changes in temperature, pressure, or chemical composition;

3. Any physical or chemical interaction that could occur with the reactor components; and

4. Any radiation hazard that may result from the activation of materials or from external beams.

5. A determination that for the maximum planned or inadvertent pulse, no credible mechanism exists which could cause the experiment to fail.

b. Prior to performing an experiment not previously performed in the reactor, it shall be reviewed and approved in writing by the Reactor Committee. This review shall consider the following information:

1. The purpose of the experiment;

2. A procedure for the performance of the experiment; and

3. The evaluation approved by a licensed Senior Operator.

c. For the irradiation of materials, the applicant shall submit an "Irradiation Request" to the Reactor Supervisor. This request shall contain information on the target material including the amount, chemical form, and packaging. For routine irradiations (which do not contain known explosive materials and which do not constitute a significant threat to the integrity of the reactor or to the safety of individuals) the approval for the Reactor Committee may be made by the Reactor Supervisor.

University of Arizona Research Reactor Pagc 29

Technical Specifications, Amendment No. 19

d. In evaluating experiments, the following assumptions should be used for the purpose of determining whether failure of the experiment would cause the appropriate limits of 10 CFR 20 to be exceeded:

1. If the possibility exists that airborne concentrations of radioactive gases or aerosols may be released within the facility, 100 percent of the gases or aerosols will escape;

2. If the effluent exhausts through a filter installation designed for greater than 99 percent efficiency for 0.3 micron particles, 10% of the particulates will escape; and

3. For a material whose boiling point is above 130'F and where vapors formed by boiling this material could escape only through a column of water above the core, 10% of these vapors will escape.

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Technical Specifications, Ainendment No. 19 7.0 DECOMMISSIONING PLAN 7.1 Incorporation of the Decommissioning Plan The license is amended to approve the Decommissioning Plan described in the licensee's application dated May 22, 2009, as supplemented by the licensee's letter of March 26, 2010, and authorizes inclusion of the Decommissioning Plan as a supplement to the Safety Analysis Report pursuant to 10 CFR 50.82(b)(5).

7.2 Changes to the Decommissioning Plan The licensee may make changes to the decommissioning plan without prior approval provided the proposed changes do not:

(i) Require Commission approval pursuant to 10 CFR 50.59; (ii) Use a statistical test other than the Sign test or Wilcoxon Rank Sum test for evaluation of the final status survey; (iii) Increase the radioactivity level, relative to the applicable derived concentration guideline level, at which an investigation occurs; (iv) Reduce the coverage requirements for scan measurements; (v) Decrease an area classification (i.e., impacted to unimpacted; Class 1 to Class 2; Class 2 to Class 3; or Class 1 to Class 3);

(vi) Increase the Type I decision error; (vii) Increase the derived concentration guideline levels and related minimum detectable concentrations (for both scan and fixed measurement methods); and (viii) Result in significant environmental impacts not previously reviewed.

7.3 Characterization Report A completed radiological characterization report shall be submitted to NRC review and approval prior to initiating decommissioning activities. The characterization report will include information required in NUREG- 1575, Sections 2.4 and 5.3; and NUREG- 1757, Volume 2, Section 4.2) to allow NRC staff to verify that the University has adequately characterized the radiological condition of the site.

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Technical Specifications, Amendment No. 19 7.4 Final Status Survey Plan The University shall provide NRC with a Final Status Survey Plan prior to conduct of license termination surveys. The Plan will be developed in accordance requirements in NUREG 1575 (MARSSIM); NUREG-1537, Part 1, Appendix 17.1, Section A; and NUREG-1757, Volume 2, Chapter 4.

7.5 Release Criteria The University shall use the release criteria specified in the Decommissioning Plan and as amended in the letter dated March 26, 2010. The University shall submit a revised license condition for review and approval by the NRC if alternative release criteria are developed for release of the NRL.

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Technical Specifications, Amendment No. 19 TECHNICAL SPECIFICATIONS FOR THE UNIVERSITY OF ARIZONA TRIGA RESEARCH REACTOR FACILITY LICENSE R-52 Amendment 19 This document includes the Technical Specifications and the bases for the Technical Specifications.

The bases provide the technical support for the individual Technical Specifications and are included for information purposes only. The bases are not part of the Technical Specifications and they do not constitute limitations or requirements to which the licensee must adhere.

Technical Specifications, Amendment No. 19 INDEX Page number 1.0 DEFINITIONS 3 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 8 2.1 Safety Limit - Fuel Temperature8 3.0 LIMITING CONDITIONS FOR OPERATION AND LIMITING DECOMMISSIONING CONDITIONS 11 3.1 Reactivity Limits 't 3.4 Reactor Instrumentation 14 3.6 Ventilation System' 18 4.0 SURVEILLANCE REQUIREMENTS 20 4.1 Fuel 20 4.2 Control Rods 21 4.3 Radiation Monitoring Equipment 231 4.4 Maintenance 24 4.5 Pool Water Conductivity 25 5.0 DESIGN FEATURES 26 5.1 Reactor Fuel 26 5.2 Reactor Building 27 5.3 Fuel Storage 28 6.0 ADMINISTRATIVE CONTROLS 29 6.1 Organization 29 6.2 Review 31 6.3 Operations 3

a. Operating Procedures 33

b. ALARA Program 33 6.4 Action to be Taken in the Evenit a Safety Limit is Exceeded 334 6.5 Action to be Taken in the Event of a Reportable Occurrence 335 6.6 Plant Operating Records 336 6.7 Reporting Requirements 37 6.8 Review of Experiments 42 7.0 DECOMMISSIONING PLAN 44 7.1 Incorporation of the Decommissioning Plan 44 7.2 Changes to the Decommissioning Plan 44 7.3 Characterization Report 45 7.4 Final Status Survey Plan 45 7.5 Release Criteria 45 University of Arizona Research Reactor

Technical Specifications, Amendment No. 19 1.0 DEFINITIONS Channel - A channel is a combination of sensors, electronic circuits, and DEFINITIONS output devices connected by the appropriate communications network in remain unaffected, order to measure and display the value of a parameter. with the addition of Channel Calibration - A channel calibration is an adjustment of a channel Decommissioning such that its output corresponds with acceptable accuracy to known values of Activities and the parameter which the channel measures. Calibration shall encompass the Limiting entire channel, including equipment, actuation, alarm, or trip and shall Decommissioning include a Channel Test. Conditions.

Channel Check - A channel check is a qualitative verification of acceptable performance by observation of channel behavior. The verification shall include comparison of the channel output with previous readings or performance or with other independent channels or systems measuring the same variable, whenever possible.

Channel Test - A channel test is the introduction of a signal into the channel for verification that it is operable.

Cold Critical - The reactor is in the cold critical condition when it is critical with the fuel and bulk water temperatures the same (-20'C).

Decommissioning Activities - Decommissioning activities are the physical dismantlement or permanent removal from service of systems and components described in the SAR. Decommissioning activities, however, do not include the removal of fuel.

Experiment - An experiment is any device or material, not normally part of the reactor, which is introduced into the reactor for the purpose of exposure to radiation, or any operation which is designed to investigate non-routine reactor characteristics.

Experimental Facilities - Experimental facilities are the thermal column, pneumatic transfer systems, central thimble, rotary specimen rack, beam tube, and the in-core facilities.

Limiting Conditions for Operation - Limiting Conditions for Operation (LCO) are administratively established constraints on equipment and operational characteristics which shall be adhered to during operation of the reactor.

Limiting Decommissioning Conditions - Limiting Decommissioning Conditions (LDC) are administratively established constraints on equipment and operational characteristics which shall be adhered to during decominssioninL activities.

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Technical Specifications, Amendment No' 19 Limiting Safety System Setting (LS SS) - The LS SS is the actuating level for DEFINITIONS automatic protective devices related to those variables having significant remain unaffected, safety functions. with the addition of Manual Mode - The reactor is in the manual mode when the reactor mode Decommissioning selection switch is in the manual or automatic position. In this mode, reactor Activities and power is held constant or is changed on periods of approximately one second Limiting or longer. Decommissioni g Conditions.

Measured Value - The Measured Value is the value of a parameter as it appears on the output of a channel.

Movable Experiment - An experiment is movable when 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.

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

Operating - Operating means a component or system is performing its intended function.

Pulse Mode - The reactor is in the pulse mode when the reactor mode selection switch is in the pulse position. In this mode, reactor power may be increased on periods less than one second by motion of the transient control rod.

Reactivity Worth of an Experiment - The reactivity worth of an experiment is the maximum value of the reactivity change that would occur as a result of planned changes or credible malfunctions that alter experiment position or configuration.

Reactor Committee - The group of persons at the University who are assigned responsibility for review and audit of facility operation and review of changes and experiments in accordance with 10 CFR 50.59.

Reactor Operating - The reactor is operating whenever it is not secured or shutdown.

Reactor Safety Systems -Reactor Safety Systems are those systems, including associated input channels, which are designed to initiate automatic reactor protection or to provide information for initiation of manual protective action.

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Technical Specifications, Amendment No. 19 Reactor Secured - The reactor is secured when: DEFINITIONS remain unaffected,

a. It contains insufficient fissile material or moderator present in the with the addition reactor, adjacent experiments or control rods, to attain criticality of under optimum available conditions of moderation and reflection, or Decommissioning Activities and

b. 1. The minimum number of neutron absorbing control rods are Limiting fully inserted or other safety devices are in shutdown position, Decommissioning as required by technical specifications, and Conditions.

2. The console key switch is in the off position and the key is removed from the lock, and

3. No work is in progress involving core fuel, core structure, installed control rods, or control rod drives unless they are physically decoupled from the control rods, and

4. No experiments in or near the reactor are being moved or serviced that have, on movement, a reactivity worth of one dollar or more.

Reactor Shutdown - The reactor is in a shutdown condition when sufficient control rods are inserted to assure that it is subcritical by at least $1.00 of reactivity.

Reportable Occurrence - A Reportable Occurrence is any of the following which occurs during reactor operation:

a. Operation with actual safety-system settings for required systems less conservative than the limiting safety-system settings specified in Technical Specification 2.2.

b. Operation in violation of limiting conditions for operation established in the Technical Specifications.

c. A reactor safety system component malfunction which renders or could render the reactor safety system incapable of performing its intended safety function unless the malfunction or condition is discovered during maintenance tests or periods of reactor shutdown.

d. Any unanticipated or uncontrolled change in reactivity greater than one dollar.

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Technical Specifications, Amendment No. 19

e. Abnormal and significant degradation in reactor fuel, cladding, or DEFINITIONS coolant boundary which could result in exceeding of prescribed radiation remain unaffected, exposure or release limits. with the addition of

f. An observed inadequacy in the implementation of either Decommissioning administrative or procedural controls which could result in Activities and operation of the reactor outside the limiting conditions for Limiting operation. Decommissioning Conditions.

g. Release of radioactivity from the site above limits specified in 10CFR20.

Control Rod - 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 losses. A control rod may be coupled to its drive unit allowing it to perform a safety function when the coupling is disengaged.

Transient Rod - The transient rod is a control rod with scram capabilities that is capable of providing rapid reactivity insertion to produce a pulse.

Safety Limit - A Safety Limit is a limit on an important process variable which is found to be necessary to reasonably protect the integrity of certain of the physical barriers which guard against the uncontrolled release of radioactivity. The principal physical barrier is the fuel element cladding.

Secured Experiment - A Secured Experiment is any experiment, experimental facility, 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 the result of credible malfunctions.

Shall, Should, and May - The word "shall" is used to denote a requirement, the word "should" denotes a recommendation, and the word "may" denotes permission, neither a requirement nor a recommendation.

Shutdown Margin - Shutdown Margin is the reactivity existing when the most reactive control rod is fully withdrawn from the core and the other control rods are fully inserted into the core.

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Technical Specifications, Amendment No. 19 Time Interval - The average over any extended period for each surveillance DEFINITIONS time item shall be the normal surveillance time; e.g., for a two-year interval, remain unaffected, the average shall not exceed two years. with the addition of

a. Biennially - at two-year intervals (interval not to exceed 30 months) Decommissioning Activities and

b. Annually - at one-year intervals (interval not to exceed 15 months) Limiting Decommissioning

c. Semiannually - at 6-month intervals (interval not to exceed seven Conditions.

and one-half months)

d. Quarterly - at 3-month intervals (interval not to exceed four months)

e. Monthly - at one-month intervals (interval not to exceed six weeks)

f. Weekly - at seven-day intervals (interval not to exceed ten days)

g. Daily - (must be done during the calendar day)

Any extension of these intervals shall be occasional and for a valid reason shall not affect the average as defined.

Untried Experiment - An untried experiment is any experiment not previously performed in this reactor.

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Technical Specifications, Amendment No. 19 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS The SAFETY.

LIMIT remains 2.1 Safety Limit - Fuel Temperature unaffected by our cessation of Applicability operations.

This specification applies to the reactor fuel temperature Objective The objective is to define a fuel temperature below which it can be predicted with confidence that no damage to the fuel elements will occur.

Specification The temperature of the fuel shall not exceed 1000 0 C under any conditions of operation.

Basis The recommended limiting design basis parameter for TRIGA fuel is the fuel temperature. A fuel temperature safety limit of 11 50°C for stainless-steel-clad U-ZrH1 . 65 TRIGA fuel is recommended as a design value to preclude the loss of clad integrity when the clad temperature is below 500'C (Sinmad, GA Report E- 117-833, The U-Zr H Alloy: Its Properties and Use in TRIGA Fuel, Feb. 1980, p. 4-1). The criterion for assuring the integrity of a TRIGA fuel element at the University of Arizona is that the fuel temperature be maintained below 1000°C, which is well below the recommended value. It has been shown by analysis and by measurements on other TRIGA reactors that a power level of 1000 kW corresponds to a peak fuel temperature of approximately 400'C. Pulsing with a reactivity input of $3.25 will give a peak fuel temperature of approximately 460'C.

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Technical Specifications, Amendment No. 19 2.2 Limiting Safc, System Setting Steady State Reactor Power-Lve The LSSS become inapplicable, once reactor operations This specification applies to the reactor power level safety system settingfo have permanently steady, state operation-. ceased. Delete this section.

The objective is to assure that the Safety Limit is not exceeded The setting for-the power level scr-am~ in stea~dy state operation shall be no greater-than 110 kW.

B-asi-s Calculation-s -and maue nt how that at 110 k3A, the peak ftiel temper-ature in the cokte will1- be.less than appr-oximately 150 [9C which is well below the safety criter-ion of 1000 9 G and provides an ample safety mar-gint accommodate error-s in measurement and anticipated operational transiens University of Arizona Research Reactor Page 9

Technical Specifications, Amendment No. 19 2.3 Limiting Safety, System Setting Pulse Mode Reactor PowerF Lel The LSSS become inapplicable, once reactor operations This specificatioen applies to the r-eactor-power-level safeý, system setlingfo have permanently pulse mode operation. ceased. Delete this section.

The obje-tive is to assure that the fuel temperature specified by the Safety Limit is not exceeded in pulse mode oper.ation.

Th setin fo th pea poer leve sr-am in* pulse mod ope-e shall b no g*eater than 1100 MW.*/

Basis Calculations and measurements show that at a peak power- of 1100 MWLin pulse mode operation, the peak fuel temperatur-e int the core will be less ta error s in measurfemnents and anticipated operational tranasiens University of Arizona Research Reactor Page 10

Technical Specifications, Amendment No. 19 3.0 LIMITING CONDITIONS FOR OPERATION AND LIMITING DECOMMISSIONING CONDITIONS Change the LCO 3.1 Reactivity Limits Reactivity Limits Specifications to Applicability "The reactor shall These specifications apply to the reactivity condition of the reactor-,and-the not be operated,"

reactivity worths of eontrol rods and experiments, and apply for-all mod and delete the r -eactor

.pera. remainder, of this section.

Objective The objective is to assure that the reactor ean-shall be shut down at all times and to assure that the safety limit will not be exceeded.

Specifications The reactor shall not be operated. unless the fol!-ino4g conditions exist:

la. The shutdown margin feferfed to the cold xenon free condition is greae than $0.50 with the highest wo-th rod filly wih.drawn... and ..,n with the highest worth non secured experiment in its most positive reactivity state.

b. Any experiment with a.reactivity w;orth greater than $1.00 is secure as to prevent unplanned r-eactivity removal from o~r insertiont int~o the r-eactor;

e. The reactivity, available to be inseited by the pulse rod is determffined an is limited by a mechanical block to a maximum of $2.50.

d. The reactivity wofth of an individual experimaent is not more than $3.00-

e. The total of the absolute values of the reactivity worth of all experiments in the re-actor- is less than $5.00; fl. A ramp or oscillating rod placed in the reactor- cannot add mor-e tha

$10 o -aetivi44y

g. The drop timne of each standard control rod from the ful ly withdrawi, position to 90 perceent of full reactivity insertion is less than one second;an

k. The neutron count rate on the startutp channe! is greater than one count per-seeond.

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Technical Specifications, Amendment No. 19 3.2 High Power- Operation The HIGH POWER This-speeifieatiion applies to operation of the reacteir at highi steady sta e* OPERATION powen~ section becomes inapplicable, onee

-feac4ofonce The objective is to prev.ent in-ad-veil~ent pulse oper-ation of the reactor-while it reactor operations is at a high power level. have permanently ceased. Delete this section.

The reactor shall not be operated in the steady state mode at power- level above 10 kW unless, ,,nditions in addition to the of. Section 3..1, the t,*,s*,

rod is fuilly withdra'v,% to the limnit of its limiting switch.

Basis This splecification is intended to pr-event inadveep p~tpuLe operation whenh fuiel temperature is above 502C (eoc~esponding to a power- level of 10 kW)-as mneasurfed in the B r-ing. See Specification 3.3b-.

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Technical Specifications, Amendment No. 19 3.3 Pulse Operation The PULSE Apylieab OPERATION eseJ gne eaJ%%J t ons*V, apply to operation of the reactor in the pulise mfode section becomes inapplicable, onee

-reaetronce The objectiVe is to preVenlt the fUel teffpe rature safety limfi-t f*rom. bin reactor operations exceeded during pulse mode operation. have permanently ceased. Delete Spe............ this section.

The rea.tor shall not be operated in the pulse mode unless, in addition to the requir-ements of Section 3.1, the following eonditions exist:

Q The transient rod is set such that the r-eactivity worth upon withdr-awali n-tgreater than $2.50; antfd

b. The temperatttfe of the futel imimediately prior-to the pulse is essentiall-y inqilibriuim with the bulk water- temperature. This is eentioelled, limiting the reactor power pr-ior to pulsing.

Basis The specification 3.3a will maintain the maxEimum temperatur-e of the fe after a pulse below 4002C above the bulk peol temperaturfe, and thus wl below the 10002C fuel safety criterion.

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Technical Specifications, Amendment No. 19 3.214 Reactor Instrumentation Applicability This specification applies to the information which must be available-tothe The REACTOR reactor. operator- during reator. opeatio during fuel movement and during INSTRUMENTA decommissioning activities. TION section is modified for Objective conditions after The objective is to require that sufficient information is available to the operations have operator to assure safe .per.ation of the reaetormovement of ful and permanently decommissioning. ceased. The wide-range log Specification power level The r.eactr shall not be oper.atedReactor fuel shall not be moved- and (startup count decommissioning activities shall not be conducted unless the measuring rate) meter and channels described in the following table are operable and the information is the reactor period available in the control room: meter remain operable with the 7 ~MINIM4fJM OpihAifý h MOD reactor "secured" MEASURING CHIANNEL NUMBER. ACTIViTY IN WHICH and with the

_....... ........ OPERABLE REQUIRED console power "off." Delete the reactor-power-level (linear) 4- steadyý_ aý,

wide-range log power level 1 steady stateffuel channels other (startup count rate) movement than these two reactor period 1 stead), fuel indicators and the movement radiation monitors.

reactor- power- level (high 4 us nd Fang-e) __

rveator-tankE water-temperature 4- all-med-es all-medesfue* l movement area radiation monitors 2 and decommissioning activities fuel movement and ning particulate air radiation fudecomm monitor Idecommissioning activitiesall-modes reactor water activity monitor 1 all-medesfuel movement Bases The wide range log power and reactor period channels neutron detectors assure that indications measurements of-the subcritical reactor power level changes are adequately cover.ed at both low and high rangesava abe uring fuel movement.

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Technical Specifications, Amendment No. 19 The radiation monitors provide information to operating personnel of The REACTOR radiation above a preset level so that there will be sufficient time to evacuate INSTRUMENTA the facility or take action to prevent the release of radioactivity to the TION section is surroundings. modified for conditions after operations have permanently ceased. The wide-'

range log power level (startup count rate) nieter and the r-eactor period meter remain operable with the reactor "secured" and with the console power '"off.'

Delete the channels other than these two indicators and the radiation monitors.

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Technical Specifications, Amendment No. 19 A . . . .. .. . . . . . . . . . . . ..

The REACTOR SAFETY Thi; speeification applies to the reactor safeý' system channels and SYSTEM section inmefloeks. becomes inapplicable, once reactor operations The objective is to r-equire the minimum number- of reactor safeoty syste have permanently chamiels ... d inter-locks that must be operable in order to assue-that. he-sp..,t, ceased. Delete limits and the LCO's are not exceed. this section.

The reactcr shall not be operated tmless the safety system chanels a interocks descr-ibed in the following tables are operable.

_ OPERAT4?4G, SAFETY SYrsTEMi MN4im-mtN O MARN 13ER FiU bNG i reactor powe-r -2 -am steady state no bv f-eaetef-pefied auil steady-state hA 4-e*11 _ _ _

k--1*,4 1 44 k-peak -feaetef-W ulemd noet-above power- 1400-Mw manual ¥/sef am seram a14-mede1 not less of--ate+/-

aboe oe-safety ehaffael switched to 2 ~ ma--oe timer a-ft eer

...... ... I pp-1-lse- , d 15 less-w power-failae I seram a!!-modes Console

_ _ _ _ _ _pov.'e University of Arizona Research Reactor Pagc 16

Technical Specifications, Amendment No. 19 The REACTOR SAFETY

'RAllT IG FPE4M I IfIIN ON

'('PER WIC FLcEo SYSTEM section prevent contrfol rod becomes startup coutm fate inapplicable, once Withdrawal W-hen etisa-p intedeeke netr-on countl ra'te- is reactor operations

_________________less than iper second ________

have permanently pr-event withdrawal oe ceased. Delete transient rod a transient r-od when it steady-ste this section.

i-ntei-leek lhok absor-ber anivil is maode

_________________S prevent simultaneous contr-ol rod- manual withdr-awal olf all-modes withdrawal_

prhibit iAeeek tocnrlrd

~ne~rntr~

t~ '~hit lnwn th 'w'iten prevent [Jr nhnrnil r-od ifnn~l unnf transient cirvrixi tr r-eacter power- 4 withdrawal when level interloc power is greatwer- than plei Bases The power-level scr-ams are proevided in all moedes of operato asroection against abnofmally high. fueltemer-aturfes and to assure that the reaco operation stays within the licensed limnits. The manual seram allews th.

oper-ater- dowii teshut te systeffi i an unsafe o- Ao-- oidtoie 4inc r~eactor-per-iou alarm aler-ts the operalor to potential Fapic transie..nt peo f that sufficient water-shielding is above the core during reactor operation-.

The inter-locks which pr-eNent the withdr-awal o~f the transient rod in the steady state mode. and wahien the power level is gr-eater than 10 PAL preven inadveftent pulse. The inter-leek to pr-event startup of the r-eactor- with ls thanl oneq,- neutron per second indicated on the startup ehannel assures that.

sufficient nieutr-ons are available to provide indication on the measuring ehannels.

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Technical Specifications, Amendment No. 19 3.3-33-6 Ventilation System The Applicability VENTILATION This specification applies to the operation of the reactor facility ventilation SYSTEM section system. applies to fuel movement and to Objective decommissioning The objective is to assure that the ventilation system is in operation to activities once our" mitigate the consequences of the possible release of radioactive materials reactor operations resulting from r.ea.tor. operation. have permanently ceased.

Specification The rea.tor shall not be operated.Fuel shall not be moved and deconmnissioning activities shall not be conducted unless the facility ventilation system is iioper.ati..operable with a minimum air withdrawal rate of 500 cfm. except for-pero*ds of time not to ex.eed two days . to eriti r-epair-s to the system. Dtffing such periods ofrei:

a. The reacter shall not be operated at po 'Wi W levels above 10 k3A and;

b. The rveator-shall not be operated with exper-iments in place whose faiur couild result in the release of r-adioactive gases or aer-osols.

Basis It is shown in The Safety Analysis Report that operation of the ventilation system reduces doses in the reactor facility due to argon 41, and also in the event of a TRIGA fuel element failure. The specifications go..erning limit the gener-ation of argon 41 and also r-educe the pr-obability of fui-el-element failure during such times, University of Arizona Research Reactor Page 18

Technical Specifications, Amendment No. 19 3.7 Experiments The EXPERIMENTS These specifications apply to experiments installed in the reactor and hs section becomes experimenal facilities. inapplicable, once reactor operations have permanently The obiective is to nr-evenat damage to the r-eactor- or- exc-essive rele-A se of ceased. Delete radioactive material

.of in th..... .ail.e.

an experimen.* this section.

The reactor shall not be oper-ated unule-ss the fol-lowing conditions exist:

a. fuieled exper-imenfts shall be limnited such that the total invenitory of iodine isotopes 13 1gwough 13+5 in the ep ein-ent ... is not greater than 1.5 mi.icie and the strontium 90 inventofy is not greater- than _5millicuries

b. experiments containing materials corrosive to reactor comiponents-,

compounds highly reactive with water, potentially explosv ematerialsR, o liquid fissionable materials shall1 be doubly encapsulated; an

e. known explosive materials shall not be irrfadiated in the r-eactor Min quaitities greater than 25 milligrams. in addition, the Fes~afe predt ee-44 the experiment container upon detonation of the explosive sh411all h:1ave bee, determined experimnentally, or- by calculations,-to be less than the designH pr-essure of the container-.

Basis The limits of Specification 3.7a prevent the dose in unrestricted area Calculations for-the SAR demonstrate that the ma.imum.rlease in the event of a fuiel elemflent ailr would not exceeed 6.5 millieur-ie ofiodine isotopes 131 thru-tgh 135. Speifications 3.7b and 3.7e a provided. .e to r-eduee-.

probability of damage to reactor- components resulting fr-omi experie*nt tfiiluf-e.

University of Arizona Research Reactor Page 19

Technical Specifications, Amendment No. 19 4.0 SURVEILLANCE REQUIREMENTS 4.1 Fuel Applicability No change to -theoverall This specification applies to the surveillance requirements for the FUEL fuel elements. SURVEILLANCE section except delete Objective Specifications (b) and The objective is to assure that the dimensions of the fuel elements (d) as we won't be remain within acceptable limits. pulsing or keeping fuel in the B- or C-rings.

Specifications

a. All fuel elements shall be removed from the core and visually inspected for evidence of deterioration of cladding, (including at least corrosion, erosion, wear, cracking, and weld integrity) at least once every five years.

b. The stanidard fuiel elements shall be meas red for length and U*

bend at intervals separated by not more t han 500 pulses of magnitude greater thani $2.00 of r-eactivity.

eb. A fuel element indicating an elongation greater than 1/4 inch over its original length or a lateral bending greater than 1/ 16 inch over its original bending shall be considered to be damaged and shall not be u.sed in the co-e for fut*her, operation be recorded as such in the fuel inventory logs.

d. Fuel elements in the B and C rings shall be m ,easued fr, possible distor-tion in the event that there is indication that the Limiting Safety System Settings mfay have beneeedd Basis The most severe stresses induced in the fuel elements result from pulse operation with high reactivity input, during which differential expansion between the fuel and the cladding occurs and the pressure of the gases within the elements increases sharply. The above limits on the allowable distortion of a fuel element correspond to strains that are considerably lower than the strain expected to cause rupture of a fuel element.

University of Arizona Research Reactor Page 20

Technical Specifications, Amendment No. 19 4.2 Control Rods We cannot Applicability- accomplish all This specification applies to the surveillance requirements for the control CONTROL ROD rods. SURVEILLANCE once our operating Objective license expires.

The objective is to assure the operau34W- integrity of the fuel-followed Keep only control rods. Specification (c) for fuel followed rods and delete the remainder of this section.

Specification

a. The reactivity waoth of ea.h eantfc 1 red shall be d~eter-pai"@ Cannot accomplish annually. reactivity worth determination.

b. Control rod drop times shall be dletermnined annually and after disassembly anad reassembly of control r~od dr-ives or-removal ot controel elements.

ea. The fuel-followed control rods shall be visually inspected for deterioration biennially.

d. On each day that pulse mode operation of the react.r is planned, -a functional per-formanee check of the transient (pul~se) rod system shall be peerfomed prior-to pulse moede ope-ration.

e. Semiamnually, the transient (pulse) red dr.ive cylinder and the .

associated air supply system shall be inspected, cleaned and lubricated as necessary.

fl. The maxi~mumn contol rod reactivity insei~ion rates shall be Cannot accomplish.

determined annually.

Basis The reactivity wou÷h of the con.treol rods is measu÷... to a.s t ,,e..

reuied shutdown mar-gin is available anld to provide a mnean's for-dtrining the r-eactivity weidhs of exper-iments inse-1ed in th-e PCoe The visual inspection of the fuel-followed control rods ad...... u.r..

of their drop times are is made to deteimine whether the control rods are capable of perfe*- ing their-functions proper-ypreserving the integrity of fuel.

University of Arizona Research Reactor Page 21

Technical Specifications, Amendment No. 19 4.3 Rcactor-Safety System Ajqlieaili~y 1"

• Al "11 We cannot

.JyIV 'A*JLL

"-n ftlJJ

- nhp Ltffit tnjl J-

• J fln r LL[* IOfl V pII-.n ALULJ

,.p~1-~vonc

] tLtJjA* 1J* ' .*tJlZ..k 13 Ir fI, LJI'. accomplish all measuring channels of the rea.t.r. safey system. REACTOR SAFETY SYS TENM SURVEILLANCE, The objective is to assure that the safety system will remain operable and which is not will pr-event the fuiel temeaue afety limfit fromf being exceeded. applicable once our operations cease.

Eliminate this entire

'A. A chaffnmel test of each of the r-eaetor- safety system ehamels required REACTOR SAFETY in the operating mode to be followed shall be per-fomed prior-to SYSTEM each day's oprtinorpior to each oper-ation exteending more tha SURVEILLANCE section.

b. A channel check of the power-level mneasurfing ehamiels required i~n the oper-ating mode to be followed shall be per-formed daily whenever-the r-eactor-is in operation-.

e. A channfel calibration by the ealar-imne~i method shall be performed Cannot accomplish for the reactor-power-level measuring channels annually.

The daily test anid ehanne! ehek, will assure !hat the sa-fety-ekaintek, 1A1A~ ticarlm drift Aftb'p P4igniipQl tPI L'a~r'4r University of Arizona Research Reactor Page 22

Technical Specifications, Amendment No. 19 4.34-4 Radiation Monitoring Equipment Applicability This specification applies to the radiation monitoring equipment required by Section 3.24 of these specifications. The RADIATION MONITORING Objective EQUIPMENT The objective is to assure that the radiation monitoring equipment is SURVEILLANCE operating and to verify the appropriate alarm settings. section applies to equipment required Specification during fuel

a. The alarm set points for the radiation monitoring instrumentation movement and shall be verified prior to eaehday's- r-unfuel movement or conduct of decommissioning decommissioning activities, on each day when they are performed. activities, after reactor operations

b. The radiation monitoring equipment shall be calibrated annually. have ceased.

Basis Verification of the alarm set points of radiation monitoring instrumentation will assure that sufficient information to provide protection against radiation exposure is available.

University of Arizona Research Reactor Page 23

Technical Specifications, Amendment No. 19 4.54 Maintenance Applicability The This specification applies to the surveillance requirements following SURVEILLANCE maintenance of a control or safety system. FOLLOWING MAINTENANCE Objective section remains The objective is to assure that a system is operable before being used unaffected once our after maintenance has been performed. operating license expires.

Specification

a. Following maintenance or modification of a cointrol or safety system or component, it shall be verified that the system is operable prior to its return to service. A system shall not be considered operable until after it is successfully tested.

b. Any additions, modifications, or maintenance to the ventilation system, the core and its associated support structure, the pool or its penetrations, the pool coolant system, the rod drive mechanism, or the reactor safety system shall be made and tested in accordance with the specifications to which the systems were originally designed and fabricated or to specifications approved by the Reactor Committee.

c. A licensed reactor operator shall be present during maintenance of the reactor control and safety system.

Basis This specification relates to changes in reactor systems which could directly affect the safety of the reactor. Changes or replacements to these systems which meet the original design specifications are considered to meet the presently accepted operating criteria.

University of Arizona Research Reactor Page 24

Technical Specifications, Amendment No. 19 4.65 Pool Water Conductivity Applicability This specific action applies to surveillance of pool water conductivity. The POOL WATER CONDUCTIVITY Objective SURVEILLANCE The objective is to assure that pool water mineral content is maintained section remains at an acceptable level. unaffected once our operating license Specification expires.

The conductivity of bulk coolant water shall be verified to be within specified limits at least monthly.

Basis Based on experience, in which pool water conductivity changes slowly with time, observation at these intervals provides acceptable surveillance of conductivity to assure that accelerated fuel clad corrosion does not occur.

University of Arizona Research Reactor Page 25

Technical Specifications, Amendment No. 19 5.0 DESIGN FEATURES 5.1 Reactor Fuel The REACTOR FUEL DESIGN Applicability FEATURES section This specification applies to the fuel elements used-stored in the reactor is modified to reflect eefepool. the use of core positions outside Objective rings B and C for fuel The objective is to assure that the fuel elements are of such a design and storage.

fabricated in such a manner as to permit their use with a high degree of reliability with respect to their mechanical integrity.

Specifications

a. Standard Fuel Element: The standard fuel element shall be of the TRIGA type and shall contain uranium-zirconium hydride, clad in 0.020 inch of 304 stainless steel. It shall contain a maximum of 9.0 weight percent uranium which has a maximum enrichment less than 20 percent. There shall be 1.55 to 1.80 hydrogen atoms to 1.0 zirconium atom.

b. Loading: With the exception of one fuel-followed control element (the "regulating rod") no fuel elements shall be placed within the B-or C- rings of the core. The elements shall be placed in a closely packed affay except for- exper-imental facilities or- for- positions o.cupied by control r.ods, elements fully loaded with graphite, a nieutr-on sta~up soufee, or single positions within the afnay filled with watef.

Basis This type of fuel element has a long history of successful use in TRIGA reactors.

Specification b ensures that the fuel stored within the core structure cannot attain a value of keff greater than 079-.0.9.

University of Arizona Research Reactor Page 26

Teclmical Specifications, Amendment No. 19 5.2 Reactor Building and Decommissioning Site Applicability This specification applies to the facility which houses the reactor and the residual facility and site to which the Decommissioning Plan applies. The REACTOR BUILDING Objective SPECIFICATIONS The objective is to assure that provisions are made to restrict the section is modified to radioactivity released into the environment. include the site to which the Specifications Decommissioning

a. The reactor shall be housed in a closed room of a facility designed Plan applies to restrict leakage.

b. The free volume of the reactor room shall be at least 6,000 cubic feet.

c. All air or other gases exhausted from the reactor room during reactor operation decommissioning activities shall be released at a minimum of 12 feet above ground level.

d. The reactor facility shall be equipped with a ventilation system capable of exhausting air or other gases from the reactor room from a stack at a minimum of 50 feet above ground level under emergency conditions.

e. During decommissioning activities within the reactor room, openings to the room other than those designed for exhaust air and gases shall be closed except for required access and when materials prepared for shipment are being removed.

f. During decommissioning activities outside the reactor room, components that are to be removed shall be enclosed in a manner designed to restrict leakage and to restrict access, before being dismantled.

Basis In order that the movement of air can be controlled, the facility contains no windows that can be opened. Under emergency conditions the room air is exhausted through a filter and discharged through a stack at a minimum of 50 feet above ground to provide dilution.

Specification f. applies only to equipment described in the SAR which is outside the reactor room: parts of the water purification system and the cooling system. All other decommissioning activities will be confined to the footprint described in SAR section IVa designate,*

. designated as a ee....*u*,a aecesscontrolled access area.

University of Arizona Research Reactor Page 27

Technical Specifications, Amendment No. 19 5.3 Fuel Storage Applicability This specification applies to the storage of reactor fuel at times when it is The FUEL not in the reactor core. STOPRAGE SPE1--CIFICATION S Obiective section remains The objective is to assure that fuel which is being stored will not become unaffected once our supercritical and will not reach unsafe temperatures. operating license expires.

Specifications

a. All fuel elements shall be stored in a geometrical array where the value of keff is less than 0.9 for all conditions of moderation and reflection using light water.

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 800'C.

Basis Specification 5.3a assures that unplanned criticality will not occur in fuel storage racks.

Specification 5.3b is based on a fuel temperature limit of 950'C to assure fuel clad integrity when the clad temperatures can equal the fuel temperature (Simnad, G. A. Report E- 117-83 3, February 1980, p.4 --1--)]l University of Arizona Research Reactor Page 28

Technical Specifications, Amendment No. 19 6.0 ADMINISTRATIVE CONTROLS 6.1 Organization The

a. The reactor facility shall be maintainedeper-ated by the Nuclear ADMINISTRATIVE Reactor Laboratory (NRL) at the University of Arizona. The CONTROLS Nuclear Reactor Laboratory Director shall report to the Vice ORGANIZATION President for Research and Graduate Studies at the University of section remains Arizona as shown in the diagram below. unaffected when our operations cease, but

b. The reactor facility shall be under the supervision of a licensed changes become senior operator for the reactor. He shall be responsible for applicable when we assuring that all operations are conducted in a safe manner and begin within the limits prescribed by applicable federal regulations, by decommissioning the facility license, and by the provisions of the Reactor activities.

Committee.

c. There shall be a Health Physicist responsible for assuring the safety of reactor operations from the standpoint of radiation protection.

d. An NRC-licensed operator must be present in the control room when the key switch is on. An operator and one other person authorized by the Reactor Supervisor must be present in the Reactor Laboratory whenever the reactor is not shut down.

University of Arizona Research Reactor Page 29

Technical Specifications, Amendment No. 19 The above organizational chart fi*om our Decommissioning Plan replaces the organizational chart below when decommissioning activities commence. Until then, the following chart remains applicable.

University of Arizona Research Reactor Page 30

Technical Specifications, Amendment No. 19 6.2 Review

a. There shall be a Reactor Committee which shall review reactor The REVIEW operations and decommissioning activities to assure that the facility section becomes is epeatd--maintained in a manner consistent with public safety and applicable to within the terms of the facility license. decommissioning activities once our

b. The responsibility of the Committee includes, but is not limited to, operations have the following: ceased.

1. Review and approval of experiments utilizing the reactor facilities;

2. Review and approval of all proposed changes to the facility, procedures, and Technical Specifications;

3. Determination of whether a proposed change, test, or experiment would constitute a license amendment pursuant to 10 CFR 50.59(c)(2) as outlined in UARR 165;

4. Review and approval of all proposed changes to the Decommissioning Plan, provided such changes meet the specitications listed in 7.2

5. -Review of-4heof the operation and operational records of the facility;

-56. Review of abnormal performance of plant equipment and operating anomalies; and

67. Review of unusual or abnormal occurrences and incidents which are reportable under 10 CFR 20 and 10 CFR 50.

-78. Review and audit of the retraining and requalification program for the operating staff.

99. Biennial audit of the Emergency Plan.

c. The Committee shall be composed of at least five members, and shall include a health physicist and members competent in the field of reactor operations, radiation science, or reactor engineering. The membership of the Committee shall be such as to maintain a high level degree of technical proficiency.

University of Arizona Research Reactor Page 31

Technical Specifications, Amendment No. 19

d. The Committee shall establish a written charter defining such matters as the authority of the Committee, review and audit The REVIEW functions, and other such administrative provisions as are required section becomes for effective functioning of the Committee. Minutes of all meetings applicable to of the Committee shall be kept and submitted to committee decommissioning members and to the Vice President for Research and Graduate activities once our Studies in a timely manner. operations have ceased.

e. A quorum of the Committee shall consist of not less than three members of the Committee and shall include the chairman or his designee.

f. The Committee shall meet at least quarterly.

University of Arizona Research Reactor Page 32

Technical Specifications, Amendment No. 19 6.3 Operations

a. Operating Procedures Written procedures, reviewed and approved by the Reactor Committee, The OPERATIONS shall be in effect and followed for the following items. The procedures section remains shall be adequate to assure the safety of the reactor, but should not unaffected once our preclude the use of independent judgment and action should the situation operations cease, require such. but become applicable also to

1. Startup, operation, and shutdown of the reactor. decommissioning activities.

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

3. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms, suspected primary coolant system leaks, and abnormal reactivity changes.

4. Emergency conditions involving potential or actual release of radioactivity, including provisions for evacuation, re-entry, recovery, and medical support.

5. Maintenance procedures which could have an effect on reactor safety.

6. Periodic surveillance of reactor instrumentation and safety system, area monitors and continuous air monitors.

7. I)ecornmissioning activities Substantive changes to the above procedures shall be made only with the approval of the Reactor Committee. Temporary changes to the procedures that do not change their original intent may be made with the approval of the Reactor Laboratory Director. All such temporary changes to procedures shall be documented and subsequently reviewed by the Reactor Committee.

b. ALARA Program A program shall be established to assure that radiation exposures and releases are kept as low as reasonably achievable.

University of Arizona Research Reactor Pagc 33

Teclnical Specifications, Amendment No. 19 6.4 Action to be Taken in the Event a Safety Limit is Exceeded In the event a safety limit is exceeded, or thought to have been exceeded:

The ACTION TO

a. The reactor shall be shut down and reactor operation shall not be BE TAKEN IN resumed until authorized by the NRC. THE EVENT A SAFETY LIMIT IS

b. An immediate report of the occurrence shall be made to the EXCEEDED Chairman of the Reactor Committee and reports shall be made to section remains the NRC in accordance with Section 6.7 of these specifications. unaffected.

c. A report shall be made which shall include an analysis of the causes and extent of possible resultant damage, efficiency of corrective action, and recommendations for measures to prevent or reduce the probability of recurrence. This report shall be submitted to the Reactor Committee for review, and a similar report submitted to the NRC when authorization to resume operation of the reactor is requested.

University of Arizona Research Reactor, Page 34

Technical Specifications, Amendment No. 19 6.5 Action to be Taken in the Event of a Reportable Occurrence In the event of a Reportable Occurrence, the following action shall be taken: The ACTION TO BE TAKEN IN

a. The Reactor Laboratory Director shall be notified and corrective THE EVENT OF A action taken prior to resumption of the operation involved. REPORTABLE OCCURRENCE

b. A report shall be made which shall include an analysis of the cause section remains of the occurrence, efficacy of corrective action and unaffected.

recommendations for measures to prevent or reduce the probability of reoccurrence. This report shall be submitted to the Reactor Committee for review.

c. A report shall be submitted to the NRC in accordance with Section 6.7 of these specifications.

University of Arizona Research Reactor Page 35

Technical Specifications, Amendment No. 19 6.6 Plant Operating Records The PLANT OPERATING In addition to the requirements of applicable regulations, and in no way RECORDS section substituting therefertherefore, records and logs of the following items shall be become applicable prepared and retained for a period of at least 5 years (except as otherwise to decommissioning specified in the Commission's regulations); activities

a. Normal plant operation (but not including supporting documents such as checklists, and recorder charts, which shall be maintained for a period of at least one year);

b. Principal maintenance activities;

c. Reportable Occurrences;

d. Equipment and component surveillance activities required by the Technical Specification;

e. Experiments performed with the reactor; Logs and records of the following items shall be prepared and retained for the life of the facility.

f. Gaseous and liquid radioactive effluents released to the environs;

g. Off-site environmental monitoring surveys;

h. Fuel inventories and transfers;

i. Facility radiation and contamination surveys;

j. Radiation exposures for all personnel; and

k. Updated, corrected, and as-built drawings of the facility:_ and I. Decommissioninng activities University of Arizona Research Reactor Page 36

Technical Specifications, Amendment No. 19 6.7 Reporting Requirements In addition to the requirements of applicable regulations, and in no way The REPORTING I substituting the.efertherefore, reports shall be made to the NRC as follows: REQUIREMENTS section remains

a. A report within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone and telegraph or telefax unaffected.

(FAX) to the responsible NRC organization as listed in the Emergency Kit and posted as deemed necessary by the Reactor Committee of:

1. Any accidental off-site release of radioactivity above limits permitted by 10 CFR 20, whether or not the release resulted in property damage, personal injury, or exposure;

2. Any violation of a Safety Limit; and

3. Any reportable occurrences as defined in Section 1.0 (Reportable Occurrence) of these specifications in writing.

b. A written report within ten days to the U. S. Nuclear Regulatory Commission, Attn: Document Control Desk, Washington D.C.

20555, with a copy to the responsible NRC facility inspector of:

1. Any significant variation of measured values from a corresponding predicted value of previously measured value of safety-connected operating characteristics occurring during operation of the reactor;

2. Incidents or conditions relating to operation of the facility which prevented or could have prevented the performance of engineered safety features as described in these specifications;

3. Any reportable occurrences as defined in Section 1.0 of these specifications; and

4. Any violation of a Safety Limit.

5. Any accidental off-site release of radioactivity above limits permitted by 10 CFR 20, whether or not the release resulted in property damage, personal injury, or exposure.

University of Arizona Research Reactor Page 37

Technical Specifications, Amendment No. 19

c. A written report within 30 days to the U.S. Nuclear Regulatory The REPORTING Commission, Attn: Document Control Desk, Washington D.C. REQUIREMENTS 20555, witha copy to the responsible NRC facility inspector of: section remains unaffected.

1. Any substantial variance from performance specifications contained in these specifications or in the Safety Analysis Report;

2. Any significant change in the transient or accident analysis as described in the Safety Analysis Report;

3. Any changes in facility organization; and

4. Any observed inadequacies in the implementation of administrative or procedural controls.

d. A written report within 60 days after completion of startup testing of the reactor to the U. S. Nuclear Regulatory Commission, Attn:

Document Control Desk, Washington D.C. 20555, with a copy to the responsible NRC facility inspector of:

1. An evaluation of facility performance to date in comparison with design predictions and specifications; and

2. A reassessment of the safety analysis submitted with the license application in light of measured operating characteristics when such measurements indicate that there may be substantial variance from prior analysis.

e. A written annual report within 60 days following the 30th of June each year to the U.S. Nuclear Regulatory Commission, Attn:

Document Control Desk, Washington D. C. 20555, with a copy to the responsible NRC facility inspector of:

1. A brief narrative summary of (1) operating experience (including experiments performed), (2) changes in facility design, performance characteristics, and operating procedures related to reactor safety and occurring during the reporting period, and (3) results of surveillance tests and inspections; University of Arizona Research Reactor Page 38

Technical Specifications, Amendment No. 19

2. Tabulation of the energy output (in megawatt days) of the The REPORTING reactor, amount of pulse operation, hours reactor was critical, REQUIREMENTS and the cumulative total energy output since initial criticality; section remains unaffected.

3. The number of emergency shutdowns and inadvertent scrams, including reasons therefore;

4. Discussion of the major maintenance operations performed during the period, including the effect, if any, on the safety of the operation of the reactor, and the reasons for any corrective maintenance required;

5. A brief description including a summary of the safety evaluations of changes in the facility or in procedures and of tests and experiments carried out pursuant to Section 50.59 of 10 CFR Part 50; University of Arizona Research Reactor Page 39

Technical Specifications, Amendment No. 19

6. A summary of the nature and amount of radioactive effluents The REPORTING released or discharged-to the environs beyond the effective REQUIREMENTS control of the licensee as measured at or prior to the point of section remains such release or discharge; unaffected.

Liquid Waste (summarized on a monthly basis)

(a) Radioactivity discharged during the reporting period.

(1) Total radioactivity released (in curies).

(2) The limiting concentrations (10CFR20, Appendix B) used and the isotopic composition if greater than I x 10- 7 microcuries/cc for fission and activation products.

(3) Total radioactivity (in curies), released by nuclide, during the reporting period, based on representative isotopic analysis.

(4) Average concentration at point of release (in microcuries /cc) during the reporting period.

(b) Total volume (in gallons) of effluent water (including diluent) during periods of release.

Gaseous Waste (summarized on a monthly basis)

(a) Radioactivity discharged during the reporting period (in curies) for:

(1) Gases.

(2) Particulates with half lives greater than eight days.

(b) The limiting concentrations (10CFR20, Appendix B) used and the estimated activity (in curies) discharged during the reporting period, by nuclide, for all gases and particulates based on representative isotopic analysis.

University of Arizona Research Reactor Page 40

Technical Specifications, Amendment No. 19 Solid Waste The REPORTING (a) The total amount of solid waste packaged (in cubic feet). REQUIREMENTS section remains (b) The total activity involved (in curies). unaffected.

(c) The dates of transfer or shipment and disposition

7. A summary of radiation exposures received by facility personnel and visitors, including dates and time of significant exposures, and a summary of the results of radiation and contamination surveys performed within the facility; and

8. A description of any environmental surveys performed outside the facility.

University of Arizona Research Reactor Page 41

Technical Specifications, Amendment No. 19 6.8 Review of Experiments

a. All proposed new experiments utilizing the reactor shall be The REVILEW 1OF evaluated by the experimenter and the Reactor Committee. The EXPERIMENTS evaluation shall be reviewed by a licensed Senior Operator of the section remains facility (and the Health Physicist when appropriate) to assure unaffected.

compliance with the provisions of the utilization license, the Technical Specifications, 10 CFR 20, and the requirements of 10 CFR 50.59. If, in his judgment, the experiment meets with the above provisions and does not constitute a threat to the integrity of the reactor, he shall submit it to the Reactor Supervisor for scheduling or to the Reactor Committee for final approval as indicated in Section 6.2 above. When pertinent, the evaluation shall include:

1. The reactivity worth of the experiment;

2. The integrity of the experiment, including the effects of changes in temperature, pressure, or chemical composition;

3. Any physical or chemical interaction that could occur with the reactor components; and

4. Any radiation hazard that may result from the activation of materials or from external beams.

5. A determination that for the maximum planned or inadvertent pulse, no credible mechanism exists which could cause the experiment to fail.

b. Prior to performing an experiment not previously performed in the reactor, it shall be reviewed and approved in writing by the Reactor Committee. This review shall consider the following information:

1. The purpose of the experiment;

2. A procedure for the performance of the experiment; and

3. The evaluation approved by a licensed Senior Operator.

University of Arizona Research Reactor Page 42

Technical Specifications, Amendment No. 19

c. For the irradiation of materials, the applicant shall submit an The REVIEW OF "Irradiation Request" to the Reactor Supervisor. This request shall EXPERIMENTS contain information on the target material including the amount, section remains chemical form, and packaging. For routine irradiations (which do unaffected.

not contain known explosive materials and which do not constitute a significant threat to the integrity of the reactor or to the safety of individuals) the approval for the Reactor Committee may be made by the Reactor Supervisor.

d. In evaluating experiments, the following assumptions should be used for the purpose of determining whether failure of the experiment would cause the appropriate limits of 10 CFR 20 to be exceeded:

1. If the possibility exists that airborne concentrations of radioactive gases or aerosols may be released within the facility, 100 percent of the gases or aerosols will escape;

2. If the effluent exhausts through a filter installation designed for greater than 99 percent efficiency for 0.3 micron particles, 10%

of the particulates will escape; and

3. For a material whose boiling point is above 130 OF and where vapors formed by boiling this material could escape only through a column of water above the core, 10% of these vapors will escape.

University of Arizona Research Reactor Page 43

Technical Specifications, Amendment No. 19 7.0 DECOMMISSIONING PLAN 7.1 Incorporation of the Decommissioning Plan This is a new section The license is amended to approve the Decommissioning Plan described in the licensee's application dated May 22, 2009, as supplemented by the licensee's letter of March 26, 2010, and authorizes inclusion of the Decommissioning Plan as a supplement to the Safety Analysis Report pursuant to 10 CFR 50.82(b)(5).

7.2 Chanpres to the Decommissionin* Plan 7.2 hanges to the Decommissioning Plan The licensee may make changes to the decommissioning plan without prior approval provided the proposed changes do not:

(i) Require Commission approval pursuant to 10 CFR 50.59; (ii) Use a statistical test other than the Sign test or Wilcoxon Rank Sum test for evaluation of the final status survey; (iii) Increase the radioactivity level, relative to the applicable derived concentration guideline level, at which an investigation occurs; (iv) Reduce the coverage requirements for scan measurements; (v) Decrease an area classification (i.e., impacted to unimpacted; Class 1 to Class 2; Class 2 to Class 3; or Class 1 to Class 3);

(vi) Increase the Type I decision error; (vii) Increase the derived concentration guideline levels and related minimum detectable concentrations (for both scan and fixed measurement methods); and (viii) Result in significant environmental impacts not previously reviewed.

University of Arizona Research Reactor Page 44

Technical Specifications, Amendment No. 19 7.3 Characterization Report This is a new A completed radiological characterization report shall be submitted to NRC secution review and approval prior to initiating decommissioning activities. The characterization report will include information required in NUREG-1575, Sections 2.4 and 5.3; and NUREG-1757, Volume 2, Section 4.2) to allow NRC staff to verify that the University has adequately characterized the radiological condition of the site.

7.4 Final Status Survey Plan The University shall provide NRC with a F![inal Status Survey PNan prior to(

conduct of license termination surveys. The Plan will be devdtoped in accordance requirements in NUREG 1.575 (MARSSIM); NUREG-1]537. Part 1, Appendix 17.1. Section A; and NUREG-1757. Volume 2. Chapter 4.

7.5 Release Criteria The University shall use the release criteria specified in the Decommissioning Plan and as amended in the letter dated March 26, 2010. The University shall submit a revised license condition for review and ap.proval bv the NR.C if alternative release criteria are developed for release of the NRL.

University of Arizona Research Reactor Page 45