ML12082A145

University of Texas Triga II Reactor Request for Change to License Technical Specifications Incorporating 2008, 2010 & 2011 Requests

ML12082A145
Person / Time
Site:	University of Texas at Austin
Issue date:	02/08/2012
From:	Whaley P University of Texas at Austin
To:	Paulette Torres Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML12082A145 (51)

Text

Department of Mechanical Engineering THE UNIVERSITY OF TEXAS AT AUSTIN Nuclear Engineering Teaching Laboratory "http://www.me. utexas.edu/-nuclear/index.php/netl I University Station, R9000

• Austin, Texas - 78712 * (512) 232-5370 Fax (512) 471-4589 February 8, 2012 U.S. Nuclear Regulatory Commission Attn: Document Control Washington, DC, 20555-0001

Subject:

Request for Change to License Technical Specifications Incorporating 2008, 2010, and 2011 Requests Ref:

1. The University of Texas at Austin Facility License R-129, Docket 50-602

2. Letter of March 28 2008 (ML080920755)

3. Letter of April 1, 2010 (ML101241147)

4. Letter of April 6, 2010 (ML101330271)

5. Request for Change to License Technical Specifications Staffing Requirements (January 31, 2011)

6. Email, P. Torres to P. M. Whaley, 1/23/2012, TS Change Request Ms. Torres:

I greatly appreciate your attention in determining to act on active requests for license amendments for the University of Texas TRIGA II reactor. To resolve all issues into a single action and provide a coherent and orderly transition of Technical Specifications requirements, I am combining previous requests, and therefore withdraw previous requests documented in ML080920755, ML101241147, ML101330271, and the January 31, 2011 letter and submitting this request for a revision to the UT Technical Specifications.

Proposed changes are presented in tabular form, with the original version adjacent to the proposed revision. Explanation and justification for the change, including a safety analysis follows each change.

1.0 DEFINTIONS CURRENT PROPOSED 1.1 Certified Operators An individual authorized by the U.S. Nuclear 1.1 Licensee Regulatory commission to carry out the ResolitoryCommiesssioited wirryuththepAn individual licensed operator or senior operator.

responsibilities associated with the position requiring the certification 1.1.1 Senior Reactor Operator 1.1.1 Senior Reactor Operator An individual who is licensed to direct the activities Any individual licensed under 10CFR55 to of reactor operators. Such an individual may be manipulate the controls of a facility and to direct referred to as a Class A operator the licensed activities of licensed operators.

CURRENT PROPOSED CURRENT PROPOSED 1.1.2 Operator 1.1.2 Reactor Operator Any individual licensed under 10CFR55 to An individual who is licensed to manipulate the manipulate a control of a facility. In accordance controls of a reactor. Such an individual may be with 10CFR55, an operator is licensed as either a referred to as a Class B operator.

Reactor Operator or a Senior Reactor Operator.

This change brings the UT Technical Specifications in compliance with 10CFR55 definitions, which state:

• Licensee means an individual licensed operator or senior operator.

• Operatormeans any individual licensed under this part to manipulate a control of a facility.

• Senior operatormeans any individual licensed under this part to manipulate the controls of a facility and to direct the licensed activities of licensed operators.

This change is administrative in nature, and does not affect safety.

CURRENT PROPOSED FuelnElement, 1.5. fuelelem Standard 1.5 Fuel Element, Standard A AAslem ngentSt RIandard n o A fuel fuel elem ent is element is aa single TRIGA elem single TRIGA ent of element of A isa ful sngleTRIA eemen elmen ofstandard type. Fuel is U-ZrH (<20% enriched standard type. Fuel is U-ZrH clad in stainless steel uraniad in stil s H ydrogen clad. Hydrogen to zirconium ratio is nominal 1.6. uranium) clad in stainless steel. Hydrogen to zirconium ratio is nominal 1.6.

This change is editorial in nature, and does not affect safety.

CURRENT PROPOSED Initial Startup A reactor startup and approach to power following:

1 Modifications to reactor safety or control rod drive systems, 2 Fuel element or control rod relocations or No previous definition installations within the reactor core region, 3 Relocation or installation of any experiment in the core region with a reactivity worth of greater than one dollar, or 4 Recovery from an unscheduled (a) shutdown or (b) significant power reductions.

A senior reactor operator is required to be present during initial startup, but the term is not defined.

Defining initial startup ensures the senior reactor operator will be present when required, and therefore enhances reactor safety.

3.0 LIMITING CONDITIONS FOR OPERATIONS 3.1 Reactor Core Parameters 3.1.1 Excess Reactivity Specification(s)

CURRENT PROPOSED The maximum available core reactivity (excess Maximum excess reactivity shall be 4.9% Ak/k. reactivity) does not exceed 4.9% Ak/k ($7.00) for reference core conditions with no negative reactivity worth credited to moveable experiments.

Reactivity units used in measurements at the UT TRIGA are dollars, and therefore were included in the specification. The definition for excess reactivity (1.12 Reactivity, Excess) is "that amount of reactivity that would exist if all the control rods were moved to the maximum reactive condition from the point where the reactor is exactly critical." The current specification and the associated definition does not provide reference conditions, technically permitting compensation for reactivity from various sources in evaluating excess reactivity. The change ensures that experiments with positive reactivity contribute to excess reactivity, while experiments with negative reactivity may not be used to mitigate excess reactivity. This change enhances safety by ensuring excess reactivity limits bound the reactivity balance of fuel and experiments and control rods.

3.1.2 Shutdown Margin Specification(s)

CURRENT PROPOSED The reactor shall not be operated unless the shutdown margin provided by the control rods is greater than 0.2% Ak/k with: The magnitude of shutdown margin in reference

a. The reactor in the reference core core conditions with no reactivity from negative condition worth experiments shall be greater than 0.2% Ak/k

b. The most reactive rod fully withdrawn ($0.29)

c. All moveable experiments in their most reactive state Reactivity units used in measurements at the UT TRIGA are dollars, and therefore were included in the specification. The reactivity associated with shutdown margin is negative; these limits are based on the magnitude of the reactivity.

The definition includes "the most reactive rod is fully withdrawn" and therefore the current part 3.1.2.b is redundant. The definition of shutdown margin is:

1.26 Shutdown Margin Shutdown margin shall mean the minimum shutdown reactivity necessary to provide confidence that the reactorcan be made subcriticalby means of the control and safety systems startingfrom any permissible operatingcondition and with the most reactive rod in its most reactive position, and that the reactor will remain subcritical withoutfurther operatoraction.

This change enhances reactor safety. Experiments with positive reactivity reduce shutdown margin, and experiments with negative worth increase shutdown margin; this change ensures that credit for shutdown margin is based on the control and safety systems (as defined) and that the control and safety systems are capable of maintaining minimum shutdown margin even with positive reactivity worth experiments installed.

3.1.3 Transient Insertions Specification(s)

CURRENT PROPOSED Total worth of the transient rod shall be limited to Total worth of the transient rod shall be limited to 2.8% Ak/k ($4.00), and the total withdrawal time 2.8% Ak/k, and the total withdrawal time for the for the rod shall not exceed 15 seconds during an rod shall not exceed 15 seconds.

operation in the pulse mode.

Reactivity units used in measurements at the UT TRIGA are dollars, and therefore were included in the specification. As written, the current specification does not specify the mode.

This change removes ambiguity in the wording of the specification, and does not otherwise affect reactor safety.

3.2.3 Reactor Safety Systems (Table)

CURRENT PROPOSED Safety System Function: Safety System Function:

a. Scram at <550°C a. Scram at <550°C

- Number Operable: 2 - Number Operable: 1

The safety basis for this specification (A.3.2.3) indicates:

Safety system scram functions consist of three types. These scram types are the limiting safety system settings, operable system conditions, and the manual or program logic scrams. The scrams cause control rod insertion and reactor shutdown.

Scrams for limiting safety system settings consist of signal trip levels that monitor fuel temperature and power level. The trip levels are conservative by a significant margin relative to the fuel element temperaturesafety limit.

Trip logic follows single channel actuation. Two channels are installed and used to provide redundancy so that failure of one channel does not prevent the safety function strictly as a good engineering practice, but only one channel is required for reactor safety.

3.2.4 Reactor Instrument Systems (Table)

CURRENT PROPOSED Instrument System Function: Safety System Function:

a. Temperature b. Temperature

- Number Operable: 2 - Number Operable: 1 and A.3.2.41Reactor Instrument Systems CURRENT PROPOSED The minimum measuring channels are sufficient to The minimum measuring channels are sufficient to provide signals for automatic safety system provide signals for automatic safety system operation. Signals from the measuring systems operation. Signals from the measuring systems provide information to the control and safety provide information to the control and safety systems for a protective action. Instruments systems for a protective action. Temperature provide redundancy by measurements of the same thermocouple sensors monitor the fuel temperature parameters and diversification by measurements of limiting safety system setting ...

different parameters. Two redundant temperature thermocouple sensors monitor the fuel temperature limiting safety system setting ...

The safety basis for this specification (A.3.2.4) indicates:

The minimum measuring channels are sufficient to provide signalsfor automatic safety system operation.Signals from the measuring systems provide information to the control and safety systems for a protective action. Instruments provide redundancy by measurements of the same parametersand diversification by measurements of different parameters.Two redundant temperature thermocouple sensors monitor the fuel temperature limiting safety system setting ...

As noted above, fuel temperature trip logic follows single channel actuation, and only one channel is required for reactor safety.

3.4 Limits on Experiments 3.4.2 Materials Specification(s)

CURRENT PROPOSED

a. Experiments containing materials corrosive to

a. Experiments containing materials corrosive to reactor components, compounds high reactive with reactor components, compounds high reactive with water, potentially explosive materials and liquid water, potentially explosive materials and liquid fissionable materials shall be doubly encapsulated.

fissionable materials shall be doubly encapsulated.

Guidance for classification of materials should use Guidance for classification of materials should use the Material Safety Data Sheet (MSDS) on file or the "Handbook of Laboratory Safety" Tables of similar source of information involving hazardous Chemical Information published by CRC press.

chemicals.

e. Experiment materials, except fuel materials, which could off gas, sublime, volatilize, or produce

e. Experiment materials, except fuel materials, aerosols under (1) normal operating conditions of which could off gas, sublime, volatilize, or produce the experiment or reactor, (2) credible accident aerosols under (1) normal operating conditions of conditions in the reactor, (3) possible accident the experiment or reactor, (2) credible accident conditions in the experiment shall be limited in conditions in the reactor, (3) possible accident activity such that if 100% of the airborne conditions in the experiment shall be limited in concentration of the radioactivity averaged over a activity such that if 100% of the airborne year would not exceed the derived air concentration of the radioactivity averaged over a concentration limits (DAC) of 10CFR20 Appendix year would not exceed the occupational limits for B, and averaged effluent from the reactor room maximum permissible concentration.

to the environment would not exceed effluent limits of Appendix B.

f. In calculations pursuant to e. above, the following f. In calculations pursuant to e. above, the following assumptions shall be used: (1) If the effluent from assumptions shall be used: (1) If the effluent from an experimental facility exhausts through a holdup an experimental facility exhausts through a holdup tank which closes automatically on high radiation tank which closes automatically on high radiation level, at least 10% of the gaseous activity or level, at least 10% of the gaseous activity or aerosols produced will escape. (2) If the effluent aerosols produced will escape. (2) If the effluent from an experimental facility exhausts through a from an experimental facility exhausts through a

filter installation designed for greater than 99% filter installation designed for greater than 99%

efficiency for 0.25micron particles, at least 10% of efficiency for 0.25micron particles, at least 10% of these vapors can escape. (3)For materials whose these vapors can escape. (3)For materials whose boiling point is above 55°C and where vapors boiling point is above 55WC and where vapors formed by boiling this material can escape only formed by boiling this material can escape only through an undisturbed column of water above the through an undisturbed column of water above the core, at least 10% of these vapors can escape. (4) core, at least 10% of these vapors can escape.

Limits for maximum permissible concentrations are specified in the appropriate section oflOCFR20.

The MSDS provides more information for hazard evaluation, although the proposed change permits the use of the CRC Handbook for reference.

The term "maximum permissible concentrations" is obsolete, and has been replaced by Derived Air Concentration.

This change brings the Technical Specifications into compliance with 10CFR, and has no other safety significance.

4.0 SURVEILLANCE REQUIREMENTS 4.1 Reactor Core Parameters 4.1.3 Reactivity Insertion Specification(s)

CURRENT PROPOSED Transient rod function shall be evaluated annually or after maintenance on the transient rod drive or Transient rod function shall be evaluated annually following significant reactor core changes. The or after maintenance on the transient rod drive or transient rod drive and associated air supply shall following significant reactor core changes. The be inspected annually, and the drive cylinder shall transient rod drive and associated air supply shall be cleaned and lubricated annually.

be inspected annually, and the drive cylinder shall be cleaned and lubricated annually.

A comparison of pulse data with previous measurements should be determined annually. It A comparison of pulse data shall be made with is not necessary to pulse the reactor annually only previous measurements at annual intervals or each to perform the surveillance, but a comparison to time the interval to the previous measurement previous measurements shall be performed exceeds the annual interval.

immediately following resumption of pulsing operations.

Reactor pulsing is a severe transient on the reactor and may shorten the lifetime of the thermocouples in the instrumented fuel elements. This change clarifies the specification to minimize pulses performed solely for this requirement. If infrequent pulsing occurs, comparison of power output and temperatures to a previous pulse of the same magnitude is adequate to meet the current specification, with this change providing more explicit guidance. This change is editorial and does not affect reactor safety.

5.0 DESIGN FEATURES 5.1 Site and Facility Description 5.1.1 Location CURRENT PROPOSED

b. The TRIGA reactor is installed in a designated b. The TRIGA reactor is installed in room 1.104 of room of a building constructed as a Nuclear the Nuclear Engineering Teaching Laboratory Engineering Teaching Laboratory

d. Licensed areas of the facility

d. Lcened ofthe rea for reactor aciityforreatord. Licensed areas of the facility for NRC-licensed operation shall consist of the room enclosing the d.tLices aras of th e faci lics reactor shield are and orpool cntrl. structure, eacor roo 1.14, and orrdor the adjacent materials shall designated consist as* the of the Nuclear entire facility Engineering Teaching are for reactor control. (room 1.104, corridor Laboratory.

3.200; and rooms 3.202, 3.204, and 3.208).

This change updates information from the Preliminary Safety Analysis Report to "as-built" conditions. This change does not affect reactor safety.

5.4 Reactor Fuel Element Storage CURRENT PROPOSED

a. All fuel element s shall be stored in a a. All fuel element s shall be stored in a geometric array where effective multiplication geometric array where effective multiplication is less than 0.8 for all conditions of is less than 0.9 for all conditions of moderation. moderation.

Although non-conservative, this change updates the UT specification to the current standard guidance of ANS/ANSI-15.1-2007 and is therefore acceptable.

6.0 ADMINSTRATIVE CONTROLS 6.1 Organization

6.1.1 Structure [OrganizationalChart revised to]

Officeof the President ThenUneersitynf Texas at Austin Executive Vice President Vice President for and Provost University Operatiolns Assceice PresidentD Safety and Security DerectorEnvironmental UniversitypPolice H.ealth and' Safety Radiation SafewOffith Radeation SafetypCo riat

-- m....J Dean of the Cockr l Scho6l of EngineSefng ApChairmaw af the Dept.

S of Mechanaicaol Engineering Reactor Oversgh it of Te Committee Associate Director of NETh ReactorSupervisr [Hah ysct .

The previous org-chart did not correctly reflect level 1, 2 and 3 positions. Level 1, 2, and 3 terminology is not used except in conjunction with reporting. The appropriate section following is revised to indicate which position changes requires a report.

6.1.3 Staffing CURRENT PROPOSED The minimum staffing when the reactor is not The minimum staffing when the reactor is not shutdown shall be: secure shall be:

A minor discrepancy was noted during a review of staffing requirements the Technical Specifications for the University of Texas at Austin TRIGA reactor. Technical Specifications section 6.:1..3 (Staffing) states:

The minimum staffing when the reactoris not shutdown shall be:

a. A certified operatorin the control room

b. A second person in the facility area that can perform prescribedwritten instructions. Unexpected absencefor two hours shall require immediate action to obtain an alternateperson.

c. A seniorreactoroperatorreadily available. The availableoperatorshould be within thirty minutes of the facility and reachable by telephone.

The definition of "reactor shutdown" in section 1.19 states:

The reactoris shutdown if it is subcriticalby at least one dollar in the reference core condition with the reactivity of all installedexperiments included.

UT reactor procedures impose staffing (as specified in 6.1.3) when "reactor secure" condition is not met as defined in 1.18, rather than "reactor shutdown" condition as defined in section 1.19. The definition of "reactor secure" in section 1.18 is stated:

The reactoris secure when:

1.18.1 Subcritical:

There is insufficientfissile materialor moderatorpresent in the reactor,control rods or adjacent experiments, to attain criticality under optimum available conditionsof moderation and reflection, or 1.18.2 The following conditions exist:

a. The minimum number of neutron absorbingcontrol rods arefully inserted in shutdown position, as required by technical specifications.

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

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

d. No experiments are being moved or serviced that have, on movement, a reactivity worth equal to or exceeding one dollar.

The specifications of 6.1.3 permit the control room to be unstaffed as long as the reactor is at least one-dollar subcritical, which does not adequately define the set of I

conditions where the control room should be manned. Therefore we are requesting that the first sentence in 6.1.3:

The minimum staffing when the reactoris not shutdown shall be:

be changed to The minimum staffing when the reactoris not secure shall be:

This change enhances safety by clearly indicating when a reactor operator at the controls is required.

6.1.3 Staffing (Part 2)

CURRENT PROPOSED Events requiring the direct supervision or performance of a senior reactor operator shall be:

a. Ensure conditions and limitations of the Events requiring the direction of a senior license, Technical Specifications, and reactor operator shall be: experiment approvals.(as applicable) are

a. All fuel element or control rod relocations met prior to operations.

within the reactor core region. b. All initial startups.

b. Relocation of any experiment with a c. All fuel element or control rod relocations reactivity worth of greater than one within the reactor core region.

dollar. d. Relocation of any experiment with a

c. Recovery from an unscheduled shutdown reactivity worth of greater than one dollar.

or significant power reduction. e. During normal, abnormal and emergency situations assess facility conditions and

d. Initial startup and approach to power.

select appropriate response procedures.

f. Response to situations requiring activation of the Emergency Plan.

Regulations for operator training (10CFR55) indicate the knowledge, skills, and abilities needed to perform licensed senior operator duties include:

1. Conditions and limitations in the facility license

2. Facility operating limitations in the technical specifications and their bases.

3. Facility licensee procedures required to obtain authority for design and operating changes in the facility.

4. Radiation hazards that may arise during normal and abnormal situations, including maintenance activities and various contamination conditions.

5. Assessment of facility conditions and selection of appropriate procedures during normal, abnormal, and emergency situations.

6. Procedures and limitations involved in initial core loading, alterations in core configuration, control rod programming, and determination of various internal and external effects on core reactivity.

7. Fuel handling facilities and procedures.

The staffing section was revised to (1) incorporate the new definition of "initial startup,"

and (2) align senior operator staffing requirements with 2OCFR55.

6.2 Review and Audit CURRENT PROPOSED 6.2.1 Composition and Qualifications 6.2.1 Composition and Qualifications A Nuclear Reactor Committee shall consist of at A Reactor Oversight Committee shall consist of at least three (3)members appointed by the Dean of least three (3)members appointed by the Dean of the College of Engineering that are knowledgeable the College of Engineering that are knowledgeable in fields which relate to nuclear safety. The in fields which relate to nuclear safety. The university radiological safety officer shall be a university radiological safety officer shall be a member or an ex-officio member. The committee member or an ex-officio member. The committee will perform the functions of review and audit or will perform the functions of review and audit or designate a knowledgeable person for audit designate a knowledgeable person for audit functions. functions.

6.2.2 Charter and Rules 6.2.2 Charter and Rules The operations of the Nuclear Reactor Committee The operations of the Reactor Oversight shall be inaccordance with an established charter, Committee shall be inaccordance with an including provisions for: established charter, including provisions for:

6.2.3 Review Function 6.2.3 Review Function a..Determinations that proposed changes in a..Determinations in accordance with 10CFR50.59 equipment, systems, tests, experiments, or that proposed changes in equipment, systems, procedures do not involve an unreviewed safety tests, experiments, or procedures do not require a question. license amendment..

6.2.4 Audit Function 6.2.4 Audit Function The audit function shall be a selected examination The audit function shall be a selected examination of operating records, logs, or other documents. An of operating records, logs, or other documents. An audit will be by a person not directly responsible audit will be by a person not directly responsible for the records and may include discussions with for the records and may include discussions with cognizant personnel or observation of operations. cognizant personnel or observation of operations.

The following items shall be audited and a report The following items shall be audited and a report made within 3 months to the Director and Nuclear made within 3 months to the Director and Reactor Reactor Committee: Oversight Committee 6.3 Operating Procedures 6.3 Operating Procedures Written operating procedures shall be prepared, Written operating procedures shall be prepared, reviewed and approved by the Director or a reviewed and approved by the Director or a supervisory Senior Reactor Operator and the supervisory Senior Reactor Operator and Reactor Nuclear Reactor Committee prior to initiation of Oversight Committee prior to initiation of the the following activities: following activities:

CURRENT PROPOSED F.4 Exnprimpnt Rpvipw and Annoval 6.4 Experiment Review and Approval All new experiments or classes of experiments shall All new experiments or classes of experiments shall be approved by the Director or a Supervisory be approved by the Director or a Supervisory Senior Reactor Operator and the Nuclear Reactor Senior Reactor Operator and the Reactor Oversight Operations Committee. Committee.

6.4 Operating Procedures 6.4 Operating Procedures Substantive changes to the above procedures shall Substantive changes to the above procedures shall be made effective after approval by the Director or be made effective after approval by the Director or a supervisory Senior Reactor Operator and the a supervisory Senior Reactor Operator and the Nuclear Reactor Committee.

Reactor Oversight Committee.

Two changes are incorporate in this section. The Nuclear reactor Committee title (abbreviated NRC) was changed to Reactor Oversight Committee in order to remove confusion. The term Unreview Safety Question was removed and the phrase in accordance with 10CFR50.59 that proposed changes in equipment, systems, tests, experiments, or procedures do not require a license amendment" substituted. This change is administrative in nature and does not affect safety.

6.6.2 Special Reports CURRENT PROPOSED A written report within 30 days to the NRC of:

a. Permanent changes in the facility organization for positions including:

• University of Texas President NRC of:

A written report within 30 days to the

• Executive Vice President and Provost

a. Permanent changes in the facility organization

• Da fteCleeo niern involving Level 1 or Level 2 personnel.

• Chai of the Mehnia Engineering 0 Chair of the Mechanical Engineering Department

• Director of the NETL

• Associate Director of the NETL This is an administrative change, and does not affect safety.

6.6.2.3 NO TITLE This section only applied immediately following initial criticality of the UT TRIGA reactor.

(Section requires a startup tests report within 9 months of initial criticality), and is no longer applicable. It is proposed to remove this section.

Please contact me by phone at 512-232-5373 or email whaley@mail.utexas.edu if you require additional information or there is a problem with this submittal.

Thank you, I

P. M. Whaley Associate Director Nuclear Engineering Teaching Laboratory The University of Texas at Austin I declare under penalty of perjury that the foregoing is true and correct.

Executed on February 8, 2012.

Steven R. Biegalski NETL Director ATT: Appendix A, DRAFT Technical Specifications (February 2012)

Appendix A DRAFT Technical Specifications Revision 2 Docket 50-602 The University of Texas at Austin TRIGA Reactor February 2012

Revision 2 Technical Specifications Table of Contents 1.0. DEFINITIONS 6 1.1 Certified Operators 6 1.1.1 Senior Reactor Operator 6 1.1.3 Reactor Operator 6 1.2 Channel 6 1.2.1 Channel Test 6 1.2.2 Channel Check 6 1.2.3 Channel Calibration 6 1.3 Confinement 6 1.4 Experiment 7 1.4.1 Experiment, Moveable 7 1.4.2 Experiment, Secured 7 1.4.3 Experimental Facilities 7 1.5 Fuel Element, Standard 7 1.6 Fuel Element, Instrument 7 1.7 Initial Startup 8 1.8 Mode; Manual, Auto, Square Wave, Pulse 8 1.9 Steady State 8 1.10 Operable 8 1.11 Operating 8 1.12 Protective Action 8 1.12.1 Instrument Channel Level 8 1.12.2 Instrument System Level 9 1.12.3 Reactor Safety System Level 9 1.13 Reactivity, Excess Reactivity Limit 9 1.14 Reactivity Limits 9 1.15 Reactor Core, Standard 9 1.16 Reactor Core, Operational 9 1.17 Reactor Operating 9 1.18 Reactor Safety System 9 1.19 Reactor Secured 10 1.20 Reactor Shutdown 10 1.21 Reference Core Condition 10 1.22 Research Reactor 10 1.23 Rod, Control 11 1.23.1 Shim Rod 11 1.23.2 Regulating Rod 11 1.23.3 Standard Rod 11 1.23.4 Transient Rod 11 01/12 Amended 01/12 Page 2

Revision 2 Technical Specifications 1.24 Safety Limit 11 1.25 Shall, Should, May 11 1.26 Scram Time 11 1.27 Shutdown Margin 12 1.28 Shutdown, Unscheduled 12 1.29 Value, Measured 12 1.30 Value, True 12 1.31 Surveillance Activities 12 1.32 Surveillance Intervals 13 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 14 2.1 SAFETY LIMIT 14 2.2 LIMITING SAFETY SYSTEM SETTINGS 14 2.2.1 Fuel Temperature 14 2.2.2 Power Level (Non Pulse) 14 2.2.3 Reactivity Insertion (Pulse) 14 3.0 LIMITING CONDITIONS FOR OPERATION 15 3.1 REATOR CORE PARAMETERS 15 3.1.1 Excess Reactivity 15 3.1.2 Shutdown Margin 15 3.1.3 Transient Insertions 15 3.1.4 Fuel Elements 15 3.2 REACTOR CONTROL AND SAFETY SYSTEM 16 3.2.1 Control Assemblies 16 3.2.2 Reactor Control System 16 3.2.3 Reactor Safety System 17 3.2.4 Reactor Instrument System 17 3.3 OPERATIONAL SUPPORT SYSTEMS 18 3.3.1 Water Coolant Systems 18 3.3.2 Air Confinement Systems 18 3.3.3 Radiation Monitoring Systems 19 3.40 LIMITATIONS ON EXPERIMENTS 20 3.4.1 Reactivity 20 3.4.2 Materials 20 4.0 SURVEILLANCE REQUIREMENTS 22 4.1 REACTOR CORE PARAMETERS 22 4.1.1 Excess Reactivity 22 4.1.2 Shutdown Margin 22 4.1.3 Transient Insertion 22 4.1.4 Fuel Elements 22 4.2 REACTOR CONTROL AND SAFETY SYSTEM 23 4.2.1 Control Assemblies 23 4.2.2 Reactor Control System 23 01/12 Amended 01/12 Page 3

Revision 2 Technical Specifications 4.2.3 Reactor Safety System 23 4.2.4 Reactor Instrument System 23 4.3 OPERATIONAL SUPPORT SYSTEMS 24 4.3.1 Water Coolant Systems 24 4.3.2 Air Confinement Systems 24 4.3.3 Radiation Monitoring Systems 25 4.4 LIMITATIONS ON EXPERIMENTS 25 4.4.1 Reactivity 25 4.4.2 Materials 25 5.0 DESIGN FEATURES 26 5.1 SITE AND FACILITY DESGRIPTION 26 5.1.1 Location 26 5.1.2 Confinement 26 5.1.3 Safety Related Systems 26 5.2 REACTOR COOLANT SYSTEM 26 5.2.1 Natural Convection 27 5.2.2 Siphon Protection 27 5.3 REACTOR CORE AND FUEL 27 5.3.1 Fuel Elements 27 5.3.2 Control Rods 27 5.3.3 Configuration 28 5.4 REACTOR FUEL ELEMENT STORAGE 28 5.5 REACTOR POOL GAMMA IRRADIATOR 28 6.0 ADMINISTRATIVE 29 6.1 ORGANIZATION 29 6.1.1 Structure 29 6.1.2 Responsibility 29 6.1.3 Staffing 30 6.1.4 Selection and Training of Personnel 30 6.2 REVIEW AND AUDIT 31 6.2.1 Composition and Qualifications 31 6.2.2 Charter and Rules 31 6.2.3 Review Function 31 6.2.4 Audit Function 32 6.3 OPERATING PROCEDURES 32 6.4 EXPERIMENT REVIEW AND APPROVAL 33 6.5 REQUIRED ACTIONS 33 6.5.1 In case of Safety Limit Violation 33 6.5.2 Event of a Reportable Occurrence 34 6.6 REPORTS 34 6.6.1 Operating Reports 34 6.6.2 Special Reports 35 01/12 Amended 01/12 Page 4

Revision 2 Technical Specifications 6.7 RECORDS 36 6.7.1 Lifetime of the Facility 36 6.7.2 Five Years or the Life of the Component 37 6.7.3 One Licensing Cycle 37 APPENDICES A.1 A Introduction A.2 A Objectives & Bases for Safety Limits A.3 A Objectives & Bases for Limiting Conditions for Operations A.4 A Objectives & Bases for Surveillance Requirements A.5 A Objectives & Bases for Design Features 01/12 Amended 01/12 Page 5

Revision 2 Technical Specifications 1.0 DEFINITIONS 1.1 Licensee An individual licensed operator or senior operator.

1.1.1 Senior Reactor Operator Any individual licensed under 10CFR55 to manipulate the controls of a facility and to direct the licensed activities of licensed operators.

1.1.2 Reactor Operator Any individual licensed under 10CFR55 to manipulate a control of a facility. In accordance with 10CFR55, an operator is licensed as either a Reactor Operator or a Senior Reactor Operator.

1.2 Instrumentation Channel A channel is the combination of sensor, line, amplifier, and output device which are connected for the purpose of measuring the value of a parameter.

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

1.2.2 Channel Check Channel check is a qualitative verification of acceptable performance by observation of channel behavior. This verification, where possible, shall include comparison of the channel with other independent channels or systems measuring the same variable.

1.2.3 Channel Calibration Channel calibration is an adjustment of the channel such that its output corresponds with acceptable accuracy to known values of the parameter which the channel measures. Calibration shall encompass the entire channel, including equipment actuation, alarm, or trip and shall be deemed to include a channel test.

1.3 Confinement Confinement means an enclosure on the overall facility which controls the movement of air into it and out through a controlled path.

01/12 Amended 01/12 Page 6

Revision 2 Technical Specifications 1.4 Experiment Any operation, component, or target (excluding devices such as detectors, foils, etc.), which is designed to investigate non-routine reactor characteristics or which is intended for irradiation within the pool, on or in a beam tube or irradiation facility and which is not rigidly secured to a core or shield structure so as to be part of their design.

1.4.1 Experiment, Moveable A moveable experiment is one where it is intended that all or part of the experiment may be moved in or near the core or into and out of the reactor while the reactor is operating.

1.4.2 Experiment, Secured A secured experiment is any experiment, experiment facility, or component of an experiment that is held in a stationary position relative to the reactor by mechanical means. The restraining force must be substantially greater than those to which the experiment might be subjected by hydraulic, pneumatic, buoyant, or other forces which are normal to the operating environment of the experiment, or by forces which can arise as a result of credible conditions.

1.4.3 Experimental Facilities Experimental facilities shall mean rotary specimen rack, pneumatic transfer tube, central thimble, beam tubes and irradiation facilities in the core or in the pool.

1.5 Fuel Element, Standard A fuel element is a single TRIGA element of standard type. Fuel is U-ZrH (<20% enriched uranium) clad in stainless steel. Hydrogen to zirconium ratio is nominal 1.6.

1.6 Fuel Element, Instrumented An instrumented fuel element is a special fuel element fabricated for temperature measurement. The element shall have at least one thermocouple embedded in the fuel near the axial and radial midpoints.

01/12 Amended 01/12 Page 7

Revision 2 Technical Specifications 1.7 Initial Startup A reactor startup and approach to power following:

1 Modifications to reactor safety or control rod drive systems, 2 Fuel eler ent or control rod relocations or installations within the reactor core region, 3 Relocation or installation of any experiment in the core region with a reactivity worth of greater than one dollar, or 4 Recovery from an unscheduled (a) shutdown or (b) significant power reductions.

1.8 Mode; Manual, Auto, Pulse, Square Wave Each mode of operation shall mean operation of the reactor with the mode selection switches in the manual, auto, pulse or square wave position.

1.9 Steady-state Steady-state mode operation shall mean any operation of the reactor with the mode selection switches in the manual, auto or square wave mode. The pulse mode switch will define pulse operation.

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

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

1.12 Protective Action Protective action is the initiation of a signal or the operation of equipment within the reactor safety system in response to a variable or condition of the reactor facility having reached a specified limit.

1.12.1 Instrument Channel Level At the protective instrument channel level, protective action is the generation and transmission of a trip signal indicating that a reactor variable has reached the specified limit.

01/12 Amended 01/12 Page 8

Revision 2 Technical Specifications 1.12.2 Instrument System Level At the protective instrument system level, protective action is the generation and transmission of the command signal for the safety shutdown equipment to operate.

1.12.3 Reactor Safety System Level At the reactor safety system level, protective action is the operation of sufficient equipment to immediately shut down the reactor.

1.13 Reactivity, Excess Excess reactivity is that amount of reactivity that would exist if all the control rods were moved to the maximum reactive condition from the point where the reactor is exactly critical.

1.14 Reactivity Limits The reactivity limits are those limits imposed on the reactor core excess reactivity. Quantities are referenced to a reference core condition 1.15 Reactor Core, Standard A standard core is an arrangement of standard TRIGA fuel in the reactor grid plate and may include installed experiments.

1.16 Reactor Core, Operational An operational core is a standard core for which the core parameters of excess reactivity, shutdown margin, fuel temperature, power calibration, and reactivity worths of control rods and experiments have been determined to satisfy the requirements set forth in the Technical Specifications.

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

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

01/12 Amended 01/12 Page 9

Revision 2 Technical Specifications 1.19 Reactor Secure The reactor is secure when:

1.19.1 Subcritical:

There is insufficient fissile material or moderator present in the reactor, control rods or adjacent experiments, to attain criticality under optimum available conditions of moderation and reflection, or 1.19.2 The following conditions exist:

a. The minimum number of neutron absorbing control rods are fully inserted in shutdown position, as required by technical specifications.

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

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

d. No experiments are being moved or serviced that have, on movement, a reactivity worth equal to or exceeding one dollar.

1.20 Reactor Shutdown The reactor is shutdown if it is subcritical by at least one dollar in the reference core condition with the reactivity of all installed experiments included.

1.21 Reference Core Condition The condition of the core when it is at ambient temperature (cold) and the reactivity worth of xenon is negligible (<.30 dollars).

1.22 Research Reactor A research reactor is defined as a device designed to support a self-sustaining neutron chain reaction for research, development, educational, training, or experimental purposes, and which may have provisions for the production of radioisotopes.

01/12 Amended 01/12 Page 10

Revision 2 Technical Specifications 1.23 Rod, Control A control rod is a device fabricated from neutron absorbing material or fuel which is used to establish neutron flux changes and to compensate for routine reactivity loses. A control rod may be coupled to its drive unit allowing it to perform a safety function when the coupling is disengaged.

1.23.1 Shim Rod A shim rod is a control rod with an electric motor drive that does not perform a special function such as automatic control or pulse control. The shim rod shall have scram capability.

1.23.2 Regulating Rod A regulating rod is a control rod used to maintain an intended power level and may be varied manually or by a servo-controller. The regulating rod shall have scram capability.

1.23.3 Standard Rod The regulating and shim rods are standard control rods.

1.23.4 Transient Rod A transient rod is a control rod used to initiate a power pulse that is operated by a motor drive and/or air pressure. The transient rod shall have scram capability.

1.24 Safety Limits Safety limits are limits on important process variables which are found to be necessary to protect reasonably the integrity of the principal barriers which guard against the uncontrolled release of radioactivity. The principal barrier is the fuel element cladding.

1.25 Scram Time Scram time is the elapsed time between reaching a limiting safety system set point and a specified control rod movement.

01/12 Amended 01/12 Page 11

Revision 2 Technical Specifications 1.26 Shall, Should and May The word shall is used to denote a requirement. The word should is used to denote a recommendation. The word may is used to denote permission, neither a requirement nor a recommendation.

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

1.28 Shutdown, Unscheduled An unscheduled shutdown is defined as any unplanned shutdown of the reactor caused by actuation of the reactor safety system, operator error, equipment malfunction, or a manual shutdown in response to conditions which could adversely affect safe operation, not including shutdowns which occur during testing or check-out operations.

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

1.30 Value, True The true value is the actual value of a parameter.

1.31 Surveillance Activities Surveillance activities (except those specifically required for safety when the reactor is shutdown), may be deferred during reactor shutdown, however, they must be completed prior to reactor startup unless reactor operation is necessary for performance of the activity.

Surveillance activities scheduled to occur during an operating cycle which cannot be performed with the reactor operating may be deferred to the end of the cycle.

01/12 Amended 01/12 Page 12

Revision 2 Technical Specifications 1.32 Surveillance Intervals Maximum intervals are to provide operational flexibility and not to reduce frequency.

Established frequencies shall be maintained over the long term. Allowable surveillance intervals shall not exceed the following:

1.32.1 5 years (interval not to exceed 6 years).

1.32.2 2 years (interval not to exceed 2-1/2 years).

1.32.3 Annual (interval not to exceed 15 months).

1.32.4 Semiannual (interval not to exceed 7-1/2 months).

1.32.5 Quarterly (interval not to exceed 4 months).

1.32.6 Monthly (interval not to exceed 6 weeks.

1.32.7 Weekly (interval not to exceed 10 days).

01/12 Amended 01/12 Page 13

Revision 2 Technical Specifications 2.0 SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 Safety Limit Specification(s)

The maximum temperature in a standard TRIGA fuel element shall not exceed 1150 0 C for fuel element clad temperatures less than 500 0 C and shall not exceed 950 0 C for fuel element clad temperatures greater than 500 0 C. Temperatures apply to any condition of operation.

2.2 Limiting Safety System Settings 2.2.1 Fuel Temperature Specification(s)

The limiting safety system setting shall be 5500 C as measured in an instrumented fuel element. One instrumented element shall be located in the B or C ring of the reactor core configuration.

2.2.2 Power Level (Manual, Auto, Square Wave)

Specification(s)

The maximum operating power level for the operation of the reactor shall be 1100 kilowatts in the manual, auto and square wave modes.

2.2.3 Reactivity Insertion (Pulse)

Specification(s)

The maximum transient reactivity insertion for the pulse operation of the reactor shall be 2.2% Ak/k in the pulse mode.

01/12 Amended 01/12 Page 14

Revision 2 Technical Specifications 3.0 LIMITING CONDITIONS FOR OPERATION 3.1 Reactor Core Parameters 3.1.1 Excess Reactivity Specification(s)

The maximum available core reactivity (excess reactivity) does not exceed 4.9% Ak/k

($7.00) for reference core conditions with no negative reactivity worth credited to moveable experiments.

3.1.2 Shutdown Margin Specification(s)

The magnitude of shutdown margin in reference core conditions with no reactivity from negative worth experiments shall be greater than 0.2% Ak/k

($0.29).

3.1.3 Transient insertions Specification(s)

Total worth of the transient rod shall be limited to 4.00 dollars (2.8% Ak/k), and the total withdrawal time for the rod shall not exceed 15 seconds during an operating in the pulse mode.

3.1.4 Fuel Elements Specification(s)

The reactor shall not be operated with fuel element damage except for the purpose of locating and removing the elements. A fuel element shall be considered damaged and must be removed from the core if:

a. In measuring the elongation, the length exceeds the original length by 2.54 mm (1/10 inch).

b. In measuring the transverse bend, the bend exceeds the original bend by 1.5875 mm (1/16 inch).

c. A clad defect exists as indicated by release of fission products or visual observation 01/12 Amended 01/12 Page 15

Revision 2 Technical Specifications 3.2 Reactor Control and Safety System 3.2.1 Control Assemblies Specification(s)

The reactor shall not be operated unless the control rods are operable, and

a. Control rods shall not be operable if damage is apparent to the rod or drive assemblies.

.b. The scram time measured from the instant a simulated signal reaches the value of a limiting safety system setting to the instant that the slowest scrammable control rod reaches its fully inserted position shall not exceed 1 second.

c. Maximum reactivity insertion race of a standard control rod shall be less than 0:2% Ak/k per second.

3.2.2 Reactor Control System Specification(s)

The reactor shall not be operable unless the minimum safety interlocks are operable. The following control system safety interlocks shall be operable:

Number Effective Mode*

Control Rod Drive Interlock Function Control Rod Operable M A S P Startup Withdrawal - prevent rod up 3 Standard rods X X a movement if startup signal is less than 2 1 Transient rod X X X X counts per second 3 Standardrods rods X Simultaneous Withdrawal - prevent rod up 2 Shim b movement for two or more rods 2 Shim rods X 1 Transient rod X X Non pulse drive is notcondition down - air actuation if rod Transient rod X X d Pulse Withdrawal - prevent withdrawal of 3 Standard rods X non pulse rods Transient Withdrawal - Prevent air actuation e if linear power is more than 1 kilowatt 1 Transient rod X X

• Modes are: (M) Manual, (A) Auto, (5) Square Wave, and (P) Pulse 01/12 Amended 01/12 Page 16

Revision 2 Technical Specifications 3.2.3 Reactor Safety System Specification(s)

The reactor shall not be operable unless the minimum safety channels are operable. The following control rod scram safety channels shall be operable.

NumberEfetvMo*

Safety System Function Oper Safety Channel Effective Mode*

operable M A S P a Scram at _ 550'C 1 Fuel Temperature X X b Scram at < 1.1 MW 2 Power Level X Scram at < 2000 MW 1 Pulse Power X c Scram on loss 2 High Voltage X X d Scram on loss 1 Magnet Current X X Scram on demand e Manual Scram Console Button Watchdog Trip f Scram on loss of timer 2 Microprocessor X X scan rate

• Modes are: (M) Manual, (A) Auto, (5) Square Wave, and (P) Pulse 3.2.4 Reactor Instrument System Specification(s)

A minimum configuration of measuring channels shall be operable. The following minimum reactor parameter measuring channels shall be operable:

Number M

Effective A Mode* e Instrument System Function Oper Safety Channel Operable M A S P A Temperature 1 Fuel Temperature X X Power 2 Power Level X B Pulse 1 Pulse Power X C Pulse 1 Pulse Power X

• Modes are: (M) Manual, (A) Auto, (5) Square Wave, and (P) Pulse 01/12 Amended 01/12 Page 17

Revision 2 Technical Specifications 3.3 Operational Support Systems 3.3.1 Water Coolant Systems Specification(s)

Corrective action shall be taken or the reactor shut down if any of the following (a.-d.)

reactor coolant conditions are observed:

a. The bulk pool water temperature exceeds 48 'C.

b. The water depth is less than 6.5 meters measured from the pool bottom to the pool water surface.

c. The water conductivity exceeds 5.0 limho/cm for the average value during measurement periods of one month.

d. The pressure difference during heat exchanger operation is less than 7 kPa (1 psig) measured between the chilled water outlet pressure and the pool water inlet pressure to the heat exchanger.

e. Pool water data from periodic measurements shall exist for water pH and radioactivity. Radioactivity measurements shall include total alpha-beta activity and gamma ray spectrum analysis.

3.3.2 Air Confinement Systems Specification(s)

Corrective action shall be taken or the reactor shut down if any of the following air -

confinement conditions do not exist:

a. Equipment shall be operable to isolate the reactor area by closure of room ventilation supply and exhaust dampers, and shutdown of system supply and exhaust fans.

b. The reactor room ventilation system shall have an automatic signal to isolate the area if air particulate radioactivity exceeds preset values.

c. An auxiliary air purge system to exhaust air from experiment systems shall have a high efficiency particulate filter.

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Revision 2 Technical Specifications

d. Room ventilation shall require two air changes per hour or exhaust of pool areas by the auxiliary air purge system.

3.3.3 Radiation Monitoring Systems Specification(s)

Radiation monitoring while the reactor is operating requires the following minimum conditions :

a. A continuous air monitor (particulate) shall be operable with readout and audible alarm. The monitor shall sample reactor room air within 5 meters of the pool at the pool access level. Alarm set point shall be equal to or less than a measurement concentration of 2 x 10-9 ltCi/cm3 with a two hour particulate accumulation.

The particulate continuous air monitor shall be operating when the reactor is operating. A set point of the monitor will initiate the isolation signal for the air ventilation system.

The particulate air monitor may be out of service for a period of 1 week provided the filter is evaluated daily, and a signal from the argon-41 continuous air monitor is available to provide information for manual shutdown of the HVAC.

b. A continuous air monitor (argon-41) shall be operable with readout and audible alarm. The monitor shall sample exhaust stack air from the auxiliary air purge system when the system is operating. Alarm set point shall be equal to or less than a measurement concentration of 2 x 10-5 liCi/cm3 for a daily release.

The argon-41 continuous air monitor shall be operating when the auxiliary air purge system is operating. The average annual concentration limit for release at the stack shall be 2 x 10-6 jICi/cm3.

If the argon-41 monitor is not operable, operating the reactor with the auxiliary air purge system shall be limited to a period of ten days.

c. Area radiation monitors (gamma) shall be operable with readout and audible alarm. Alarm set point shall be a measurement value equal to or less than 100 mr/hr.

One area radiation monitor shall be operating at the pool level when the reactor is operating. Two additional area radiation monitors shall be operating at other reactor areas when the reactor is operating.

01/12 Amended 01/12 Page 19

Revision 2 Technical Specifications 3.4 Limitations on Experiments 3.4.1 Reactivity Specification(s)

The reactor shall not be operated unless the following conditions governing experiment reactivity exist:

a. A moveable experiment shall have a reactivity worth less than 1.00 dollar.

b. The reactivity worth of any single secured experiment shall be less than 2.50 dollars.

c. The total of absolute reactivity worths of reactor core experiments shall not exceed 3.00 dollars, including the potential reactivity which might result from malfunction, flooding, voiding, or removal and insertion of the experiments.

3.4.2 Materials Specification(s)

The reactor shall not be operated unless the following conditions governing experiment materials exist:

a. Experiments containing materials corrosive to material corrosive to reactor components, compounds highly reactive with water, potentially explosive materials, and liquid fissionable materials shall be doubly encapsulated.

Guidance for classification of materials shall use the Material Safety Data Sheet (MSDS) on file or similar source of information involving hazardous chemicals.

b. If a capsule fails and releases material which could damage the reactor fuel or structure by corrosion or other means, removal and physical inspection shall be performed to determine the consequences and need for corrective action.

The results of the inspection and any corrective action taken shall be reviewed by the Director, or his designated alternate, and determined to be satisfactory before operation of the reactor is resumed.

c. Explosive materials in quantities greater than 25 milligrams shall not be irradiated in the reactor or experimental facilities. Explosive materials in quantities less than 25 milligrams may be irradiated provided the pressure produced upon detonation of the explosive has been calculated and/or experimentally demonstrated to be less than the design pressure of the container.

01/12 Amended 01/12 Page 20

Revision 2 Technical Specifications

d. Each fueled experiment shall be controlled such that the total inventory of iodine isotopes 131 through 135 in the experiment is no greater than 750 millicuries and the maximum strontium inventory is no greater than 2.5 millicuries

e. Experiment materials, except fuel materials, which could off-gas, sublime, volatilize, or produce aerosols under (1) normal operating conditions of the experiment or reactor, (2) credible accident conditions in the reactor, .(3) possible accident conditions in the experiment shall be limited in activity such that if 100% of the gaseous activity or radioactive aerosols produced escaped to the reactor room or the atmosphere, the airborne concentration of radioactivity averaged over a year would not exceed the derived air concentration limits (DAC) of 10CFR20 Appendix B, and averaged effluent from the reactor room to the environment would not exceed effluent limits of Appendix B.

f. In calculations pursuant to e. above, the following assumptions shall be used: (1) If the effluent from an experimental facility exhausts through a holdup tank which closes automatically on high radiation level, at least 10% of the gaseous activity or aerosols produced will escape. (2) If the effluent from an experimental facility exhausts through a filter installation designed for greater than 99% efficiency for 0.25 micron particles, at least 10% of these vapors can escape. (3) For materials whose boiling point is above 55°C and where vapors formed by boiling this material can escape only through an undisturbed column of water above the core, at least 10%

of these vapors can escape.

01/12 Amended 01/12 Page 21

Revision 2 Technical Specifications 4.0 SURVEILLANCE REQUIREMENTS 4.1 Reactor Core Parameters 4.1.1 Excess Reactivity Specification(s)

Excess reactivity shall be determined annually or after significant control rod or reactor core changes.

4.1.2 Shutdown Margin Specification(s)

Shutdown margin shall be determined annually or after significant controlcrod or reactor core changes.

4.1.3 Transient Insertion Specification(s)

Transient rod function shall be evaluated annually or after significant control rod or reactor core changes. The transient rod drive and associated air supply shall be inspected annually, and the drive cylinder shall be cleaned and lubricated annually.

A comparison of pulse data with previous measurements should be determined annually. It is not necessary to pulse the reactor annually only to perform the surveillance but a comparison to previous measurements shall be performed immediately following resumption of pulsing operations.

4.1.4 Fuel Elements Specification(s)

The reactor fuel elements shall be examined for physical damage by a visual inspection, including a check of the dimensional measurements, made at biennial intervals 01/12 Amended 01/12 Page 22

Revision 2 Technical Specifications 4.2 Reactor Control and Safety System 4.2.1 Control Assemblies Specification(s)

Control rod worths shall be determined annually or after significant control rod or reactor core changes, and

a. Each control rod shall be inspected at biennial intervals by visual observation.

b. The scram time of a scrammable control rod shall be measured annually or after maintenance to the control rod or drive.

c. The reactivity insertion rate of a standard control rod shall be measured annually or after maintenance to the control rod or drive.

4.2.2 Reactor Control System Specification(s)

The minimum safety interlocks shall be tested at semiannual intervals or after repair or modification.

4.2.3 Reactor Safety System Specification(s)

The minimum safety channels shall be calibrated annually or after repair or modifications. A channel test shall be done prior to each day's operation, after repair or modifications, or prior to each extended period of operation.

4.2.4 Reactor Instrument System Specification(s)

The minimum configuration of instrument channels shall be calibrated annually or after repair or modification. Calibration of the power measuring channels shall be by the calorimetric method. A channel check and channel test of the fuel temperature instrument channels and power level instrument channels shall be made prior to each day's operation or prior to each extended period of operation.

01/12 Amended 01/12 Page 23

Revision 2 Technical Specifications 4.3 Operational Support Systems 4.3.1 Water Coolant Systems Specification(s)

The following measurements shall monitor the reactor coolant conditions:

a. The pool temperature channel shall have a channel calibration annually, channel check monthly and will be monitored during reactor operation.

b. The pool.water depth channel shall have a channel calibration annually, channel check monthly and will be monitored during reactor operation.

c. The water conductivity channel shall have a channel calibration annually and pool water conductivity will be measured weekly.

d. The pressure difference channel shall have a channel test prior to each days operation, after repair or modifications, or prior to each extended period of operation of the heat exchanger and will be monitored during operation.

e. Measure pool water pH with low ion test paper or equivalent quarterly. Sample pool water radioactivity quarterly for total alpha-beta activity. Analyze pool water sample by gamma spectroscopy annually for isotope identification.

4.3.2 Air Confinement Systems Specification(s)

The following actions shall demonstrate the air confinement conditions:

a. Annual examination of door seals and isolation dampers.

b. Monthly functional tests of air confinement isolation.

c. Monthly check of the auxiliary air purge system valve alignments for experimental areas.

d. Daily check of ventilation system alignment for proper exhaust conditions prior to reactor operation.

01/12 Amended 01/12 Page 24

Revision 2 Technical Specifications 4.3.3 Radiation Monitoring Systems Specification(s)

The following conditions shall apply to radiation monitoring systems:

a. Calibrate particulate air monitor at semiannual intervals and check operability weekly.

b. Calibrate argon-41 air monitor at biennial intervals and check operability monthly.

c. Calibrate area radiation monitors at semiannual intervals and check operability weekly prior to reactor operation.

4.4 Limitations on Experiments 4.4.1 Reactivity Specification(s)

The reactivity of an experiment shall be measured before an experiment is considered functional.

4.4.2 Materials Specification(s)

Any surveillance conditions or special requirements shall be specified as a part of the experiment approval.

01/12 Amended 01/12 Page 25

Revision 2 Technical Specifications 5.0 DESIGN FEATURES 5.1 Site and Facility Description 5.1.1 Location Specification(s)

a. The site location is in the northeast corner of The University of Texas at Austin J.J. Pickle Research Campus.

b. The TRIGA reactor is installed in room 1.104 of the Nuclear Engineering Teaching Laboratory.

c. The reactor core is assembled in an above ground shield and pool structure with horizontal and vertical access to the core.

d. Licensed areas of the facility for NRC-licensed materials shall consist of the entire facility designated as the Nuclear Engineering Teaching Laboratory.

5.1.2 Confinement Specification(s)

a. The reactor room shall be designed to restrict leakage and will have a minimum enclosed air volume of 4120 cubic meters.

b. Ventilation system should provide two air changes per hour and shall isolate air in the reactor area upon detection of a limit signal related to the radiation level,

c. An air purge system should exhaust experiment air cavities and shall be filtered by high efficiency particulate absorption filters.

d. All exhaust air from the reactor area enclosure shall be ejected vertically upward at a point above the facility roof level.

5.1.3 Safety Related Systems Specifications Any modifications to the air confinement or ventilation system, the reactor shield, the pool or its penetrations, the pool coolant system, the core and its associated support structure, the rod drive mechanisms or the reactor safety system shall be made and tested in accordance with the specifications to which the systems were originally 01/12 Amended 01/12 Page 26

Revision 2 Technical Specifications designed and fabricated. Alternate specifications may be approved by the Reactor Oversight Committee. Asystem shall not be considered operable until after it is tested successfully.

5.2 Reactor Coolant System 5.2.1 Natural Convection Specification(s)

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

5.2.2 Siphon Protection Specification(s)

Pool water level shall be protected by holes for siphon breaks in pool water system pipe lines.

5.3 Reactor Core and Fuel 5.3.1 Fuel Elements Specification(s)

The standard TRIGA fuel element at fabrication shall have the following characteristics:

a. Uranium content: 8.5 Wt% uranium enriched to a nominal 19.7% Uranium-235.

b. Zirconium hydride atom ratio: nominal 1.6 hydrogen to zirconium, ZrHx.

c. Cladding: 304 stainless steel, nominal .020 inches thick.

5.3.2 Control Rods Specification(s)

The shim, regulating, and transient control rods shall have scram capability, and

a. Include stainless steel or aluminum clad and may be followed by air or aluminum, or for a standard rod may be followed by fuel with stainless steel clad.

b. Contain borated graphite, B4C powder, or boron and its compounds in solid form 01/12 Amended 01/12 Page 27

Revision 2 Technical Specifications as a poison.

c. The transient rod shall have a mechanical limit. An adjustable limit will. allow a variation of reactivity insertions.

d. Two shim rods, one regulating rod and the transient rod are the minimum control rods.

5.3.3 Configuration Specification(s)

The reactor shall be an arrangement of core single grid positions occupied by fuel elements, control rods, and graphite elements. Single element positions may be occupied by voids, water or experiment facilities. Special multielement positions or single element positions may be occupied by approved experiments.

5.4 Reactor Fuel Element Storage Specification(s)

a. All fuel elements shall be stored in a geometric array where the effective multiplication is less than 0.9 for all conditions of moderation.

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

5.5 Reactor Pool Irradiator Specification(s)

The irradiator assembly shall be an experiment facility.

a. A 10,000 Curie gamma irradiator may be located in the reactor pool. The irradiator isotope shall be cobalt-60.

b. Location of the assembly shall be at a depth of at least 4.5 meters and at a distance of at least 0.5 meters from the reactor core structure.

c. Pool water sample requirements shall monitor pool water for source leakage. At a pool water activity of 2.5x10 IiCi/cm3 the gamma irradiator components shall be tested to locate and remove any leaking source.

01/12 Amended 01/12 Page 28

Revision 2 Technical Specifications 6.0 ADMINISTRATIVE CONTROLS 6.1 Organization 6.1.1 Structure The facility shall be under the control of the Director, Associate Director or a delegated Senior Reactor Operator. The management for operation of the facility shall consist of the organizational structure as follows:

K Vice President for niversify Operations i Asrsocia.e Vice President Safety and Security I

Director Envir onmental UniversityPoice Health and SafetO RadiationSaf* sty Officer Radiation Safet. Comie Dean of-he Cockrell School of Enrineering Chairman of the Dept.

of Mechanical Engineering Reactor Oversight Director of NEIL Com m i.ttee Associa-e Direccor of ,ETL Reaczor Sspervsor HealtPh Physicist 6.1.2 Responsibility The Director shall be responsible to the Dean of the College of Engineering and the Chairman of the Department of Mechanical Engineering for safe operation and maintenance of the reactor and its associated equipment. These responsibilities may be delegated to the Associate Director during the Director's absence from the Facility. A member of Facility Management (Director or Associate Director) or a Senior Reactor Operator shall review and approve all experiments and experimental procedures prior to their use in the reactor. Line Management designated in Section 6.1.1 shall be responsible for the policies and operation of the facility, shall be responsible for safeguarding the public and facility personnel from undue radiation exposures and for adhering to the operating license and technical specifications.

01/12 Amended 01/12 Page 29

Revision 2 Technical Specifications 6.1.3 Staffing The minimum staffing when the reactor is not secure shall be:

a. A certified operator in the control room.

b. A second person in the facility area that can perform prescribe written instructions. Unexpected absence for two hours shall require immediate action to obtain an alternate person.

c. A senior reactor operator readily available. The available operator should be within thirty minutes of the facility and reachable by telephone.

Events requiring the direct supervision or performance of a senior reactor operator shall be:

a. Ensure conditions and limitations of the license, Technical Specifications, and experiment approvals (as applicable) are met prior to operations.

b. All initial startups.

c. All fuel element or control rod relocations within the reactor core region.

d. Relocation of any experiment with a reactivity worth of greater than one dollar.

e. During normal, abnormal and emergency situations assess facility conditions and select appropriate response procedures.

f. Response to situations requiring activation of the Emergency Plan.

A list of reactor facility personnel by name and telephone number shall be available to the operator in the control room. The list shall include:

a. Management personnel.

b. Radiation safety personnel.

c. Other operations personnel.

6.1.4 Selection and Training of Personnel The selection, training and requalification of operators shall meet or exceed the requirements of American National Standard for Selection and Training of Personnel for Research Reactors ANSI/ANS -15.4. Qualification and requalification of licensed 01/12 Amended 01/12 Page 30

Revision 2 Technical Specifications operators shall be subject to an approved NRC (Nuclear Regulatory Commission) program.

6.2 Review and Audit 6.2.1 Composition and Qualifications A Reactor Oversight Committee shall consist of at least three (3) members appointed by the Dean of the College of Engineering that are knowledgeable in fields which relate to nuclear safety. The university radiological safety officer shall be a member or an ex-officio member. The committee will perform the functions of review and audit or designate a knowledgeable person for audit functions.

6.2.2 Charter and Rules The operations of the Reactor Oversight Committee shall be in accordance with an established charter, including provisions for:

a. Meeting frequency (at least once each six months).

b. Quorums (not less than one-half the membership where the operating staff does not represent a majority).

c. Dissemination, review, and approval of minutes.

d. Use of subgroups.

6.2.3 Review Function The review function shall include facility operations related to reactor and radiological safety. The following items shall be reviewed:

a. Determination in accordance with 10CFR50.59 that proposed changes in equipment, systems, tests, experiments, or procedures do not require a license amendment.

b. All new procedures and major revisions thereto, and proposed changes in reactor facility equipment or systems having safety significance.

c. All new experiments or classes of experiments that could affect reactivity or result in the release of radioactivity.

d. Changes in technical specifications or license.

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Revision 2 Technical Specifications

e. Violations of technical specifications or license.

f. Operating abnormalities or violations of procedures having safety significance.

g. Other reportable occurrences.

h. Audit reports.

6.2.4 Audit Function The audit function shall be a selected examination of operating records, logs, or other documents. An audit will be by a person not directly responsible for the records and may include discussions with cognizant personnel or observation of operations. The following items shall be audited and a report made within 3 months to the Director and Reactor Oversight Committee:

a. Conformance of facility operations with license and technical specifications at least once each calendar year.

b. Results of actions to correct deficiencies that may occur in reactor facility equipment, structures, systems, or methods of operation that affect safety at least once per calendar year.

c. Function of the retraining and requalification program for reactor operators at least once every other calendar year.

d. The reactor facility emergency plan and physical security plan, and implementing procedures at least once every other year.

6.3 Operating Procedures Written operating procedures shall be prepared, reviewed and approved by the Director or a supervisory Senior Reactor Operator and the Reactor Oversight Committee prior to initiation of the following activities:

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

b. Fuel loading, unloading and movement in the reactor.

c. Routine maintenance of major components of systems that could have a'n effect on reactor safety.

d. Surveillance calibrations and tests required by the technical specifications or those that could have an effect on reactor safety.

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e. Administrative controls for operation, maintenance: and the conduct of experiments or irradiations that could have an effect on reactor safety.

f. Personnel radiation protection, consistent with applicable regulations or guidelines, and shall include a management commitment and programs to maintain exposures and releases as low as reasonably achievable.

g. Implementation of required plans such as the emergency plan or physical security plan.

Substantive changes to the above procedures shall be made effective after approval by the Director or a supervisory Senior Reactor Operator and the Reactor Oversight Committee.

Minor modifications to the original procedures which do not change the original intent may be made by a senior reactor operator but the modifications must be approved by the Director or a supervisory Senior Reactor Operator. Temporary deviations from the procedures may be made by a senior reactor operator in order to deal with special or unusual circumstances or conditions. Such deviations shall be documented and reported to the Director or a supervisory Senior Reactor Operator.

6.4 Experiment Review and Approval All new experiments or classes of experiments shall be approved by the Director or a Supervisory Senior Reactor Operator and the Nuclear Reactor Operations Committee.

a. Approved experiments shall be carried out in accordance with established and approved procedures.

b. Substantive changes to previously approved experiments shall require the same review as a new experiment.

c. Minor changes to an experiment that do not significantly alter the experiment may be made by a supervisory senior reactor operator.

6.5 Required Actions 6.5.1 Action to be taken in case of a Safety Limit Violation In the event of a safety limit violation, the following section shall be taken:

a. The reactor shall be shut down and reactor operation shall not be resumed until a report of the violation is prepared and authorization to restart by the Nuclear Regulatory Commission (NRC) is issued.

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Revision 2 Technical Specifications or a designated alternate.

c. The safety limit violation shall be subsequently reported to the NRC.

d. A safety limit violation report shall be prepared and submitted to the Reactor Oversight Committee. The report shall describe: (1) Applicable circumstances leading to the violation including, when known the cause and contributing factors, (2) Effect of the violation on reactor facility components, systems, or structures and on the health and safety of the public, (3) Corrective actions taken to prevent recurrence.

6.5.2 Action to be taken in the Event of an Occurrence that is Reportable.

In the event of a reportable occurrence, the following action shall be taken:

a. Reactor conditions shall be returned to normal or the reactor shutdown. If it is necessary to shut down the reactor to correct the occurrence, operations shall not be resumed unless authorized by the Director or his designated alternate.

b. Occurrence shall be reported to the Director or his designated alternate and to the Nuclear Regulatory Commission as required.

c. Occurrence shall be reviewed by the Reactor Oversight Committee at the next regularly scheduled meeting.

6.6 Reports All written reports shall be sent within the prescribed interval to the NRC, Washington D.C.

20555, Attention: Document Control Desk.

6.6.1 Operating Reports Routine annual reports covering the activities of the reactor facility during the previous calendar year shall be submitted within three months following the end of each prescribed year. Each annual operating report shall include the following information:

a. A narrative summary of reactor operating experience including the energy produced by the reactor or the hours the reactor was critical, or both.

b. The unscheduled shutdowns including, where applicable, corrective action taken to preclude recurrence.

c. Tabulation of major preventive and corrective maintenance operations having safety significance.

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d. Tabulation of major changes in the reactor facility and procedures, and tabulation of new tests or experiments, or both, that are significantly different from those performed previously, including conclusions that no unreviewed safety questions were involved.

e. A summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective control of the university as determined at or before the point of such release or discharge. The summary shall include to the extent practicable an estimate of individual radionuclides present in the effluent. If the estimated average release after dilution or diffusion is less than 25% of the concentration allowed or recommended, a statement to this effect is sufficient.

f. A summary of exposures received by facility Personnel and visitors where such exposures are greater than 25% of that allowed or recommended.

g. A summarized result of environmental surveys performed outside the facility.

6.6.2 Special Reports A written report within 30 days to the NRC of:

a. Permanent changes in the facility organization for positions including:

• University of Texas President

• Executive Vice President and Provost

• Dean of the Cockrell School of Engineering

• Chair of the Mechanical Engineering Department

• Director of the NETL

• Associate Director of the NETL

b. Significant changes in transient or accident analysis as described in the Safety Analysis Report.

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

d. Violation of fuel element temperature safety limit.

e. Release of radioactivity above allowable limits.

f. Other reportable occurrences.

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Revision 2 Technical Specifications Other events that will be considered reportable events are listed in this section. A return to normal operation or curtailed operation until authorized by management will occur.

(Note: Where components or systems are provided in addition to those required by the technical specifications, the failure of components or systems is not considered reportable provided that the minimum number of components or systems specified or required performs their intended reactor safety function.)

a. Operation with actual safety-system settings for required systems less conservative than the limiting safety system settings specified in the technical specifications.

b. Operation in violation of limiting conditions for operation established in technical specifications unless prompt remedial action is taken.

c. Reactor safety system component malfunctions which render 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 shutdowns.

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

Reactor trips resulting from a known cause are excluded.

e. Abnormal and significant degradation in reactor fuel, or cladding, or both, coolant boundary, or confinement boundary (excluding minor leaks) where applicable which could result in exceeding prescribed radiation exposure limits of personnel or environment, or both.

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

6.7 RECORDS The records may be in the form of logs, data sheets, or other suitable forms. The required information may be contained in single or multiple records, or a combination thereof.

6.7.1 Records to be Retained for the Lifetime of the Reactor Facility:

(Note: Applicable annual reports, if they contain all of the required information, may be used as records in this section.)

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

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b. Offsite environmental monitoring surveys required by technical specifications.

c. Events that impact or effect decommissioning of the facility

d. Radiation exposure for all personnel monitored.

e. Updated drawings of the reactor facility.

6.7.2 Records to be Retained for a Period of at Least Five Years or for the Life of the Component Involved Whichever ls Shorter:

a. Normal reactor facility operation (supporting documents such as checklists, log sheets, etc. shall be maintained for a period of at least one year).

b. Principal maintenance operations.

c. Reportable occurrences.

d. Surveillance activities required by technical specifications.

e. Reactor facility radiation and contamination surveys where required by applicable regulations.

f. Experiments performed with the reactor.

g. Fuel inventories, receipts, and shipments.

h. Approved changes in operating procedures.

i. Records of meeting and audit reports of the review and audit group.

6.7.3 Records to be Retained for at Least One Licensing Cycle:

Retraining and requalifications of licensed operations personnel. Records of the most recent complete cycle shall be maintained at all times the individual is employed.

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