ML12030A102

The University of Texas Triga II Research Reactor Safety Analysis Report, Chapter 12

ML12030A102
Person / Time
Site:	University of Texas at Austin
Issue date:	01/17/2012
From:	University of Texas at Austin
To:	Office of Nuclear Reactor Regulation
References
Download: ML12030A102 (129)

Text

THE UNIVERSITY OF TEXAS TRIGA II RESEARCH REACTOR O00 fl i 01/2012 SAFETY ANALYSIS REPORT, CHAPTER 12 12 CONDUCT OF OPERATIONS 12.1 ORGANIZATON This chapter describes and discusses the Conduct of Operations at the University of Texas TRIGA. The Conduct of Operations involves the administrative aspects of facility operations, the facility emergency plan, the security plan, the Reactor Operator selection and requalification plan, and environmental reports. License is used in Chapter 12 in reference to reactor operators and senior reactors subject to 10CFR50.55 requirements.

12.1.1 Structure 12.1.1.1 University Administration Fig. 12.1 illustrates the organizational structure that is applied to the management and operation of the University of Texas and the reactor facility.

Responsibility for the safe operation of the reactor facility is a function of the management structure of Fig. 12.11. These responsibilities include safeguarding the public and staff from undue radiation exposures and adherence to license or other operation constraints. Functional organization separates the responsibilities of academic functions and business functions. The office of the President administers these activities and other activities through several vice presidents.

12.1.1.2 NETL Facility Administration The facility administrative structure is shown in Fig. 12.2.

Facility operation staff is an organization of a director and at least four full time equivalent persons. This staff of four provides for basic operation requirements. Four typical staff positions consist of an associate director, a reactor supervisor, a reactor operator, and a health physicist. One or more of the listed positions may also include duties typical of a research scientist. The reactor supervisor, health physicist, and one other position are to be full time. One full time equivalent position may consist of several part-time persons such as assistants, technicians and secretaries. Faculty, students, and researchers supplement the organization. Titles for staff positions are descriptive and may vary from actual designations. Descriptions of key components of the organization follow.

I 'Standard for Administrative Controls" ANSI/ANS - 15.18 1979 Page 12-1

CHAPTER 12, CONDUCT OF OPERATIONS 1

01/2012 CHAPTER 12, CONDUCT OF OPERATIONS I 01/2012 Office of the President The Universityof Texas at Austin Figure 12.1, University Administration IT7 TstyFtao~tor1 Figure 12.2, NETL Facility Administration Page 12-2

THE UNIVERSITY OF TEXAS TRIGA II RESEARCH REACTOR 0

I 01/2012 SAFETY ANALYSIS REPORT, CHAPTER 12 NETI 12.1.2 Responsibility 12.1.2.1 Executive Vice President and Provost Research and academic educational programs are administered through the Office of the Executive Vice President and Provost. Separate officers assist with the administration of research activities and academic affairs with functions delegated to the Dean of the Cockrell School of Engineering and Chairman of the Mechanical Engineering Department.

12.1.2.2. Vice President for University Operations University operations activities are administered through the Office of the Vice President for Operations. This office is responsible for multiple operational functions of the University including university support programs, human resources, campus safety and security, campus real estate, and campus planning and facilities management.

12.1.2.3 Associate Vice President Campus Safety and Security The associate vice president for campus safety and security oversees multiple aspects of safety and security on campus including environmental health and safety, campus police, parking and transportation, fire prevention, and emergency preparedness.

12.1.2.4 Director of Nuclear Engineering Teaching Laboratory Nuclear Engineering Teaching Laboratory programs are directed by a senior classified staff member or faculty member.

The director oversees strategic guidance of the Nuclear Engineering Teaching Laboratory including aspects of facility operations, research, and service work.

The director must interact with senior University of Texas at Austin management regarding issues related to the Nuclear Engineering Teaching Laboratory.

12.1.2.5 Associate Director of Nuclear Engineering Laboratory The Associate Director performs the day to day duties of directing the activities of the facility.

The Associate Director is knowledgeable of regulatory requirements, license conditions, and standard operating practices.

The associate director will also be involved in soliciting and carrying out research utilizing the reactor and other specialized equipment at the Nuclear Engineering Teaching Laboratory.

Page 12-3

CHAPTER 12, CONDUCT OF OPERATIONS 01/2012 12.1.2.6 Reactor Oversight Committee The Reactor Oversight Committee is established through the Office of the Dean of the Cockrell School of Engineering of The University of Texas at Austin. Broad responsibilities of the committee include the evaluation, review, and approval of facility standards for safe operation.

The Dean shall appoint at least three members to the Committee that represent a broad spectrum of expertise appropriate to reactor technology. The committee will meet at least twice each calendar year or more frequently as circumstances warrant. The Reactor Oversight Committee shall be consulted by the Nuclear Engineering Teaching Laboratory concerning unusual or exceptional actions that affect administration of the reactor program.

12.1.2.7 Radiation Safety Officer A Radiation Safety Officer acts as the delegated authority of the Radiation Safety Committee in the daily implementation of policies and practices regarding the safe use of radioisotopes and sources of radiation as determined by the Radiation Safety Committee. The Radiation Safety Program is administered through the University Environmental Health and Safety division. The responsibilities of the Radiation Safety Officer are outlined in The University of Texas at Austin Manual of Radiation Safety.

12.1.2.8 Radiation Safety Committee The Radiation Safety Committee is established through the Office of the President of The University of Texas at Austin. Responsibilities of the committee are broad and include all policies and practices regarding the license, purchase, shipment, use, monitoring, disposal, and transfer of radioisotopes or sources of ionizing radiation at The University of Texas at Austin.

The President shall appoint at least three members to the Committee and appoint one as Chairperson. The Committee wwill meet at least once each'year on a called basis or as required to approve formally applications to use radioactive materials. The Radiation Safety Committee shall be consulted by the University Safety Office concerning any unusual or exceptional action that affects the administration of the Radiation Safety Program.

12.1.2.9 Reactor Supervisor Whenever the reactor is not secured, the reactor shall be (1) under the direction of or (2) operated by a (USNRC licensed) Senior Operator, designated as Reactor Supervisor; activities of reactor operators with USNRC licenses will be subject to the direction of a person with a USNRC senior operator license. Prior to operations, the Reactor Supervisor shall ensure conditions and limitations of the license, Technical Specifications, and experiment approvals (as applicable) are met for the intended operation. The reactor supervisor shall assess facility conditions and perform or direct performance of appropriate procedures during normal, routine situations.

Page 12-4

THE UNIVERSITY OF TEXAS TRIGA II RESEARCH REACTOR 0,.

01/2012 SAFETY ANALYSIS REPORT, CHAPTER 12 0

f I

Therefore, the Reactor Supervisor is to be knowledgeable of regulatory requirements, license conditions, and standard operating practices.

In addition to direction for conducting normal operations, the Reactor Supervisor will function to provide expertise for reactor operations in ron-routine situations. The reactor superviscor shall assess facility conditions and select appropriate respcnse procedures during abnormal and emergency situations. All activities that require tVe presence of licensed operators will also require the presence in the facility complex of a second person capable of performing prescribed written instructions. The Reactor Supervisor may act as the second persor. The Supervisor may be on call if cognizant of reactor operations and capable of arriving at the facility within thirty minutes.

(1)

The Reactor Supervisor shall directly supervise:

a.

All fuel element or control rod relocations or installations within the reactor core region, and initial startup subsequent and approach to power.

b.

Relocation or installation of any experiment in the core region with a reactivity worth of greater than one dollar, and subsequent initial startup and approach to power.

c.

Recovery from an urscheduled shutdown or significant power reductions,

a.

Any initial startup and approach to power following modifications to reactor safety or control rod drive systems.

(2)

The Reactor Supervisor will provide direction for, or respond to, situations requiring activation of the Emergency Plan.

(3)

In an emergency, the Reactor Supervisor is authorized to direct or perform a reasonable course of action that departs from a license condition or a Technical Specification (contained in a license issued under this part) when this action is immediately needed to protect the public health and safety, and no action consistent with license conditions and technical specifications that can provide adequate or equivalent protection is immediately apparent2.

Since the UT TRIGA may be operated several times each working day supporting multiple experiment programs, control room supervisory inspections and tours may be more useful in 2

10CFR50.54(x)

Page 12-5

CHAPTER 12, CONDUCT OF OPERATIONS j

01/2012 promoting a healthy conduct of operations than monitoring routine startups. The Reactor Supervisor should consider whether direct supervision of routine operations would be counterproductive to fostering a heightened sense of awareness in non-routine activities. The Reactor Supervisor should consider the experience of Reactor Operators performing the operation.

12.1.2.10 Health Physicist Radiological safety of the Nuclear Engineering Teaching Laboratory is monitored by a health physicist, who will be knowledgeable of the facility radiological hazards. Responsibilities of the health physicist will include calibration of radiation detection instruments, measurements of radiation levels, control of radioactive contamination, maintenance of radiation records, and assistance with other facility monitoring activities.

Activities of the health physicist will depend on two conditions. One condition will be the normal operation responsibilities determined by the director of the facility. A second condition will be communications specified by the radiation safety officer. This combination of responsibility and communication provides for safety program implementation by the director, but establishes independent review.

The health physicist's activities will meet the requirements of the director and the policies of an independent university safety organization.

12.1.2.11 Laboratory Manager Laboratory operations and research support is provide by a designated Laboratory Manager.

The function is typically combined with the Health Physicist position.

12.1.2.12 Reactor Operators Reactor operators (and senior reactor operators) are licensed by the USNRC to operate the UT TREIGA II nuclear research reactor. University staff and/or students may be employed as reactor operators.

12.1.2.13 Technical Support Staff positions supporting various aspects of facility operations are assigned as required.

12.1.2.14 Radiological Controls Technicians Radiological Controls Technicians are supervised by the Health Physicist to perform radiological controls and monitoring functions.

Radiological Controls Technicians are generally supported as Undergraduate Research Assistant positions.

Page 12-6

THE UNIVERSITY OF TEXAS TRIGA II RESEARCH REACTOR 0l00 01/2012 SAFETY ANALYSIS REPORT, CHAPTER 12 Aý n 12.1.2.15 Laboratory Assistants Laboratory Assistants are supervised by the Laboratory Manager to perform laboratory operations and analysis.

Laboratory Assistants are generally supported as Undergraduate Research Assistant positions.

12.1.3 Staffing Operation of the reactor and activities associated with the reactor, control system, instrument system, radiation monitoring system, and engineered safety features will be the function of staff personnel with the appropriate training and certification3.

Whenever the reactor is not secured, the reactor shall be under the direction of a (USNRC licensed) Senior Operator who is designated as Reactor Supervisor. The Supervisor may be on call if capable of arriving at the facility within thirty minutes and cognizant of reactor operations. The Reactor Supervisor shall directly supervise:

d.

All fuel element or control rod relocations or installations within the reactor core region, and subsequent initial startup and approach to power.

e.

Relocation or installation of any experiment in the core region with a reactivity worth of greater than one dollar, and subsequent initial startup and approach to power.

f.

Recovery from an unscheduled shutdown or significant power reductions,

g.

All initial startup and approach to power following modifications to reactor safety or control rod drive systems.

Whenever the reactor is not secured, a (USNRC licensed) Reactor Operator (or Senior Reactor Operator) who meets requirements of the Operator Requalification Program shall be at the reactor control console. and directly responsible for control manipulations. All activities that require the presence of licensed operators will also require the presence in the facility complex of a second person capable of performing prescribed written instructions.

Only the Reactor Operator at the controls or personnel authorized by, arid under direct supervision of, the Reactor Operator at the controls shall manipulate the controls. Whenever 3 "Selection and Training of Personnel for Research Reactors", ANSI/ANS -15.4 - 1970 (N380)

Page 12-7

CHAPTER 12, CONDUCT OF OPERATIONS 01/2012 the reactor is not secured, operation of equipment that has the potential to affect reactivity or power level shall be manipulated only with the knowledge and consent of the Reactor Operator at the controls. The Reactor Operator at the controls may authorize persons to manipulate reactivity controls who are training either as (1) a student enrolled in academic or industry course making use of the reactor, (2) to qualify for an operator license, or (3) in accordance the approved Reactor Operator requalification program.

Whenever the reactor is not secured, a second person (i.e., in addition to the reactor operator at the control console) capable of initiating the Reactor Emergency Plan will be present in the NETL building. Unexpected absence of this second person for greater than two hours will be acceptable if immediate action is taken to obtain a replacement.

Staffing required for performing experiments with the reactor will be determined by a classification system specified for the experiments. Requirements will range from the presence of a certified operator for some routine experiments to the presence of a senior operator and the experimenter for other less routine experiments.

12.1.4 Selection and Training of Personnel 12.1.4.1 Qualifications Personnel associated with the research reactor facility4 shall have a combination of academic training, experience, skills, and health commensurate with the responsibility to provide reasonable assurance that decisions and actions during all normal and abnormal conditions will be such that the facility and reactor are operated in a safe manner.

12.1.4.2 Job Descriptions Qualifications for University positions are incorporated in job descriptions, summarizing function and scope. The typical description includes title, duties, supervision, education, experience, equipment, working conditions, and other special requirements for the job position. Student employment is typically under the general description of Undergraduate or Graduate Research Assistant, with minimal specification to accommodate a wide range of jobs.

12.1.4.2.1 Facility Director A combination of academic training and nuclear experience will fulfill the qualifications for the individual identified as the facility director. A total of six years' experience will be required.

Academic training in engineering or science, with completion of a baccalaureate degree, may account for up to four of the six years' experience. The director is generally a faculty member with a Ph.D. in nuclear engineering or a related field.

4 ANS/ANSI-15.4, op. cit.

Page 12-8

THE UNIVERSITY OF TEXAS TRIGA II RESEARCH REACTOR fl;'B'T 01/2012 SAFETY ANALYSIS REPORT, CHAPTER 12 RE o

12.1.4.2.2 Associate Director A combination of academic training and nuclear experience will fu!fill the qualifications for the individual identified as the facility director. Academic training in engineering or science, with operating and management experience at a research reactor is required.

The Associate Director will be qualified by certification as a senior operator and is typically a person with at least one graduate degree in nuclear engineering or a related field.

12.1.4.2.3 Reactor Supervisor A person with special training to supervise reactor operation and related functions will be designated as the reactor supervisor. The reactor supervisor will be qualified by certification as a senior operator as determined by the licensing agency. Additional academic or nuclear experience will be required as necessary for the supervisor to perform adequately the duties associated with facility activities. The supervisor is typically a person with at least one graduate degree in nuclear engineering or a related field.

12.1.4.2.4 Health Physicist A person with a degree re!ated to health, safety, or engineering, or sufficient experience that is appropriate to the job requirements will be assigned the position of health physicist. A degree in health physics or similar field of study and some experience is preferred.

Certification is not a qualification, but work towards certification should be considered a requirement.

12.1.4.3.4 Laboratory Manager Laboratory operations and researcl support id provide by a designated Laboratory Manager.

The function is typically combined with the Health Physicist position.

12.1.2.12 Reactor Operators Reactor operators (and senior reactor operators) are licensed by the USNRC to operate the UT TREIGA II nuclear research reactor. Training and requalification requirements are indicated below.

12.1.2.13 Technical Support Staff positions supporting various aspects of facility operations are assigned as required.

Selection, qualification and training are on a case by case basis.

Page 12-9

CHAPTER 12, CONDUCT OF OPERATIONS 01/2012 12.1.2.14 Radiological Controls Technicians Radiological Controls Technicians training is provided in the Radiation Protection Program.

12.1.2.15 Laboratory Assistants Laboratory Assistants are supervised by the Laboratory Manager to perform laboratory operations and analysis, with specific training requirements related to job responsibilities..

12.1.5 Radiation Safety Protection of personnel and the general public against hazards of radioactivity and fire is established through the safety programs of the University Safety Office. Safety programs at the reactor facility supplement the university programs so that appropriate safety measures are established for the special characteristics of the facility5 6.

Safety programs are operated as a function of the Vice President for University Operations and include a radiation safety organization as presented in Fig. 12.1. Radiation protection at the reactor facility is the responsibility of the Reactor Supervisor, Health Physicist, or a designated senior operator in charge of operation activities.

The person responsible for radiation protection at the reactor facility will have access to other individuals or groups responsible for Radiological safety at the University. Contact with the Radiation Safety Officer will occur on an as needed basis and contact with the Reactor Oversight Committee will occur on a periodic basis. Responsibility includes the authority to act on questions of radiation protection, the Acquisition of appropriate training for radiation protection and the reporting to management of problems associated with radiation protection.

Radiological management policies and programs are described in Chapter 11.

12.2 REVIEW AND AUDIT ACTIVITES The review and audit process is the responsibility of the Reactor Oversight Committee (ROC).

12.2.1 Composition and Qualifications The ROC shall consist of at least three (3) members appointed bV the Dean of the Cockrell School 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.

s "Radiological Control at Research Reactor Facilities", ANSI/ANS-15.11 1977(N628) 6 "Design Objectives for and Monitoring of Systems Controlling Research Reactor Effluents", ANSI/ANS - 15.12 1977(N647)

Page 12-10

THE UNIVERSITY OF TEXAS TRIGA 11 RESEARCH REACTOR I

01/2012 SAFETY ANALYSIS REPORT, CHAPTER 12 000 12.2.2 Charter and Rules The operations of the ROC shall be in accordance with an established charter, including provisions for:

a.

Meeting frequency (at least twice each year, with approximately 4-8 month frequency).

b.

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

c.

Dissemination, review, and approval of minutes.

d.

Use of subgroups.

12.2.3 Review Function The responsibilities of the Reactor Safeguards Committee to shall include but are not limited to review of the following:

a) All new procedures (and major revisions of procedures) with safety significance b) Proposed changes or modifications to reactor facility equipment, or systems having safety significance c) Proposed new (or revised) experiments, or classes of experiments, that could affect reactivity or result in the release of radioactivity d) Determination of whether items a) through c) involve unreviewed safety questions, changes in the facility as designed, or changes in Technical Specifications.

e) Violations of Technical Specifications or the facility operating licensee f) Violations of internal procedures or instruction having safety significance g) Reportable occurrences h) Audit reports Minor changes to procedures and experiments that do not change the intent and do not significantly increase the potential consequences may be accomplished following review and approval by a senior reactor operator and independently by one of the Reactor Supervisor, Associate Director or Director. These changes should be reviewed at the next scheduled meeting of the Reactor Oversight Committee.

Page 12-11

CHAPTER 12, CONDUCT OF OPERATIONS 01/2012 12.2.4 Audit Function The audit function shall be a selected examination of operating records, logs, or other documents. Audits will be by a Reactor Oversight Committee member or by an individual appointed by the committee to perform the audit. The audit should be by any individual 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 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.

12.3 PROCEDURES Written procedures shall govern many of the activities associated with reactor operation.

Activities subject to written procedures will include:

a)

Startup, operation, and shutdown of the reactor b)

Fuel loading, unloading, and movement within the reactor.

c)

Control rod removal or replacement.

d)

Routine maintenance, testing, and calibration of control rod drives and other systems that could have an effect on reactor safety.

e)

Administrative controls for operations, maintenance, conduct of experiments, and conduct of tours of the Reactor Facility.

f)

Implementing procedures for the Emergency Plan or Physical Security Plan.

Written procedures shall also govern:

a)

Personnel radiation protection, in accordance with the Radiation Protection Program as indicated in Chapter 11.

Page 12-12

THE UNIVERSITY OF TEXAS TRIGA II RESEARCH REACTOR O

n 01/2012 SAFETY ANALYSIS REPORT, CHAPTER 12 MEt b)

Administrative controls for operations and maintenance c)

Administrative controls for the conduct of irradiations and experiments that could affect core safety or reactivity A master Procedure Control procedure specifies the process for creating, changing, editing, and distributing procedures.

Preparation of the procedures and minor modifications of the procedures will be by certified operators.

Substantive changes or major modifications to procedures, and new prepared procedures will be submitted to the Reactor Oversight Committee for review and approval. Temporary deviations from the procedures may be made by the reactor supervisor or designated senior operator provided changes of substance are reported for review and approval.

Proposed experiments will be submitted to the reactor oversight committee for review and approval of the experiment and its safety analysis7, as indicated in Chapter 10. Substantive changes to approved experiments will require re-approval while insignificant changes that do not alter experiment safety may be approved by a senior operator and independently one of the following, Reactor Supervisor, Associate Director, or Director. Experiments will be approved first as proposed experiments for one time application, and subsequently, as approved experiments for repeated applications following a review of the results and experience of the initial experiment implementation.

12.4 REQUIRED ACTIONS This section lists the actions required in the event of certain occurrences.

12.4.1 Safety Limit Violation In the event that a Safety Limit is not met,

a.

The reactor shall be shutdown, and reactor operations secured.

b.

The Reactor Supervisor, Associate Director, and Director shall be notifiea

c.

The safety limit violation shall be reported to the Nuclear Regulatory Commission within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by teiephone, confirmed via written statement by emaii, fax or telegraph

d.

A safety limit violation report shall be prepared within 14 days of the event to describe:

1. Applicable circumstances leading to the violation inciuding (where known) cause and contributing factors 7

ANSI/ANS 15.6, op. cit.

Page 12-13

CHAPTER 12, CONDUCT OF OPERATIONS 1

01/2012

2.

Effect of the violation on reactor facility components, systems, and structures

3.

Effect of the violation on the health and safety of the personnel and the public

4. Corrective action taken to prevent recurrence

e.

The Reactor Oversight Committee shall review the report and any followup reports

f.

The report and any followup reports shall be submitted to the Nuclear Regulatory Commission.

g.

Operations shall not resume until the USNRC approves resumption.

12.4.2 Release of Radioactivity Above Allowable Limits Actions to be taken in the case of release of radioactivity from the site above allowable limits shall include a return to normal operation or reactor shutdown until authorized by management if necessary to correct the occurrence.

A prompt report to management and license authority shall be made. A review of the event by the Reactor Oversight Committee should occur at the next scheduled meeting.

Prompt reporting of the event shall be by telephone and confirmed by written correspondence within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. A written follow up report is to be submitted within 14 days.

12.4.3 Other Reportable Occurrences In the event of a reportable occurrence, as defined in the Technical Specifications, and in addition to the reporting requirements,

a. The Reactor Supervisor, the Associate Director and the Director shall be notified

b. If a reactor shutdown is required, resumption of normal operations shall be authorized by the Associate Director or Director

c. The event shall be reviewed by the Reactor Oversight Committee during a normally scheduled meeting 12.5 REPORTS This section describes the reports required to NRC, including report content, timing of reports, and report format. Refer to section 12.4 above for the reporting requirements for safety limit violations, radioactivity releases above allowable limits, and reportable occurrences. All written reports shall be sent within prescribed intervals to the United States Nuclear Regulatory Commission, Washington, D.C., 20555, Attn: Document Control Desk.

Page 12-14

THE UNIVERSITY OF TEXAS TRIGA II RESEARCH REACTOR 0l I 01/2012 SAFETY ANALYSIS REPORT, CHAPTER 12 M, IT 12.5.1 Operating Reports Routine annual reports covering the activities of the reactcr facili-y during the previous calendar year shall be submitted to licensing authorities within three mcnths 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.

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 new or unanalyzed safety questions were identified.

e.

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

f.

A summarized result of environmental surveys performed outside the facility.

g.

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

12.5.2 Other or Special Reports A written report within 30 days to the chartering or licensing authorities of:

a.

Permanent changes in the facility organization involving Director or Supervisor.

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

Page 12-15

CHAPTER 12, CONDUCT OF OPERATIONS 01/2012 12.6.

RECORDS Records of the following activities shall be maintained and retained for the periods specified below8. The records may be in the form of logs, data sheets, electronic files, or other suitable forms. The required information may be contained in single or multiple records, or a combination thereof.

12.6.1. Lifetime Records Lifetime records are records to be retained for the lifetime of the reactor facility. (Note:

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

a.

Gaseous and liquid radioactive effluents released to the environs.

b.

Offsite environmental monitoring surveys required 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.

12.6.2 Five Year Period Records to be retained for a period of at least five years or for the life of the component involved whichever is shorter.

a.

Normal reactor facility operaticn (supporting documents such as checklists, log sheets, etc. shall be maintained for a period of at least onie 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.

8 "Records and Reports for Research Reactors", ANSI/ANS - 15.3-1974 (N399).

Page 12-16

THE UNIVERSITY OF TEXAS TRIGA II RESEARCH REACTOR o

I 01/2012 SAFETY ANALYSIS REPORT, CHAPTER 12 A rT

f.

Experiments performed with the reactor.

q.

Fuel inventories, receipts, and shipments.

h.

Approved changes in operating procedures.

+/-.

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

12.6.3 One Training Cycle Training records to be retained for at least one license cycle are the requalification records of licensed operations personnel. Records of the most recent complete cycle shall be maintained at all times the individual is employed.

12.7 EMERGENCY PLANNING Emergency planning is guided by an NRC approved Emergency Plan following the general guidance set forth in ANSI/ ANS15.16, Emergency Planning for Research Reactors. The plan specifies two action levels, the first level being a locally defined Non-Reactor Specific Event, and the second level being the lowest level FEMA classification, a Notification of Unusual Event. Procedures reviewed and approved by the reactor Oversight Committee are established to manage implementation of emergency response.

12.8 SECURITY PLANNING Security planning is guided by an NRC approved Security Plan. The plan incorporates compensatory measures implemented following security posture changes initiated post 9/11.

The Plan and portions of the procedures are classified as Safeguards Information. Security procedures implementing the plan, approved by the Reactor Oversight Committee, are established.

12.9 QUALITY ASSURANCE Objectives of quality assurance (QA) may be divided into two major goals. First is the goal of safe operation of equipment and activities to prevent or mitigate an impact on public health and safety. Second is the reliab!e operation cf equipment and activities associated with education and research functions of the University. The risk or potential release of radioactive materials is the primary impact on public health and safety, and may be divided into direct risks and indirect risks.

Direct risks are activities such as waste disposal, fuel transport and decommissioning that introduce radioactive materials into the public domain. Indirect risks are accident conditions created by normal or abnormal operating conditions that generate the potential or actual release of radioactive materials from the controlled areas of a facility.

Page 12-17

CHAPTER 12, CONDUCT OF OPERATIONS 1 01/2012 Quality assurance program procedures have been developed that apply to items or activities determined to be safety-related follows the guidelines of Reg. Guide 2.59 10 Specific procedures apply to fuel shipment and receipt, a general procedure guides unspecified safety related activities.

12.10. OPERATOR REQUALIFICATION Regulatory requirements and standards provide guidance for requalification training. Specific regulatory requirements are found in 10CFR55 for the licensing of operators and senior operators with regulations for requalification set forth in section 55.59. Standards for the selection and training of facility personnel and reactor operators are available.

Specific regulations in the form of two sets of license conditions also apply to the facility personnel and reactor operators. One set of conditions for the facility license, 10CFR 50.54, applies to facility personnel. The other set of conditions for individual licenses, 10CFR 55.53 applies to operators and senior operators.

An NRC approved UT TRIGA Requalification Plan is used to maintain training and qualification of reactor operators and senior reactor operators. License qualification by written and operating test, and license issuance or removal, are the responsibility of the U.S. Nuclear Regulatory Commission.

No rights of the license may be assigned or otherwise transferred and the licensee is subject to and shall observe all rules, regulations and orders of the Commission.

Requalification training maintains the skills and knowledge of operators and senior operators during the period of the license. Training also provides for the initial license qualification.

Active status of any licensee requires successful participation in the UT Operator Requalification program. A process is in place to manage re-establishment of active status where conditions of an active license status are not met.

The program addresses training by lectures, instruction, discussion and self-study. The program addresses training topics. The program establishes requirement for a biennial schedule of activities. The program addresses on the job training. The program requires:

a.

Observation at least once each year of a satisfactory understanding of the reactivity control system and knowledge of operating procedures.

b.

Each operator or senior operator will review facility design changes, procedure changes and license changes as they occur or once each 6 to 8 months.

c.

A review of the contents of abnormal and emergency procedures will be done by each 9 "Quality Assurance Requirements for Research Reactors", Nuclear Regulatory Guide 2.5 (77/05).

10 "Quality Assurance Program Requirements for Research Reactors," ANSI/ANS - 15.8 - 1976 (N402).

Page 12-18

THE UNIVERSITY OF TEXAS TRIGA II RESEARCH REACTOR SAFETY ANALYSIS REPORT, CHAPTER 12 go00 ET I 01/2012 operator or senior operator at 6 to 8 month intervals so that at least 3 reviews occur during the two year training cycle.

The program addresses performance evaluation of on annual examination and periodic observations, including methods to address deficiencies identified ir evaluation. The program addresses records to be generated, including required information and retention schedule.

12.11 STARTUP PROGRAM Startup and testing of the Balcones Research Center TRIGA facility was completed in 1992, therefore a startup plan is not applicable.

12.12 ENVIRONMENTAL REPORT The Environmental Report is provided as a separate document.

Page 12-19

UT TRIGA II TECHNICAL SPECIFICATIONS Table of Contents

1.

DEFINITIONS...........................................................................................................

TS-5

2.

SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS................

TS-11 2.1 Fuel Elem ent Tem perature SAFETY LIM IT......................................................

TS-11 2.1.1. Applicability...........................................................................................

TS-11 2.1.2. Objective..............................................................................................

TS-11 2.1.3. Specification..........................................................................................

TS-11 2.1.4. Actions...................................................................................................

TS-11 2.1.5. Bases.....................................................................................................

TS-11 2.2 Lim iting Safety System Settings......................................................................

TS-13 2.2.1. Applicability.....................................................................................

.. TS-13 2.2.3. Objective...............................................................................................

TS-13 2.2.4. Specification..........................................................................................

TS-13 2.2.5. Actions...................................................................................................

TS-13 2.2.6. Bases.........................................................................................

............ TS-13

3.

LIM ITING CONDITIONS FOR OPERATIONS.............................................................

TS-15 3.1 CORE REACTIVITY............................................................................................

TS-15 3.1.1. Applicability...........................................................................................

TS-15 3.1.3. Objective...............................................................................................

TS-15 3.1.4. Specification..........................................................................................

TS-15 3.1.5. Actions..................................................................................................

TS-15 3.1.6. Bases...............................................................................................................

TS-16 3.2 PULSED M ODE OPERATIONS..........................................................................

TS-18 3.2.1. Applicability...........................................................................................

TS-18 3.2.3. Objective..............................................................................................

.. TS-18 3.2.4. Specification..........................................................................................

TS-18 3.2.5. Actions..................................................................................................

TS-18 3.2.6. Bases.....................................................................................................

TS-18 3.3 M EASURING CHANNELS.................................................................................

TS-19 3.3.1. Applicability...........................................................................................

TS-19 3.3.3. Objective...............................................................................................

TS-19 3.3.4. Specification..........................................................................................

TS-19 3.3.5. Actions...................................................................................................

TS-19 3.3.6. Bases.....................................................................................................

TS-23 3.4. SAFETY CHANNEL AND CONTROL ROD OPERABILITY.....................................

TS-25 3.4.1. Applicability...........................................................................................

TS-25 3.4.3. Objective...............................................................................................

TS-25 3.4.4. Specification..........................................................................................

TS-25 3.4.5. Actions...................................................................................................

TS-26 3.4.6. Bases.....................................................................................................

TS-26 3.5 GASEOUS EFFLUENT CONTROL..................................................................

TS-27 3.5.1. Applicability...........................................................................................

TS-27 TS-1 01/2012

TECHNICAL SPECIFICATIONS 3.5.3. O bjective...............................................................................................

TS-27 3.5.4. Specification..........................................................................................

TS-27 3.5.5. A ctions..........................................................................................

.......... TS-27 3.5.6. Bases.....................................................................................................

TS-29 3.6 LIM ITATIONS ON EXPERIM ENTS............................................

.......................... TS-31 3.6.1. A pplicability...........................................................................................

TS-31 3.6.3. Objective..........................................

TS-31 3.6.4. Specification......................................................

TS-31 3.6.5. A ctions...................................................................................................

TS-3 1 3.6.6. Bases..............................................................

TS-32 3.7 FU EL INTEG RITY..............................................................................................

TS-33 3.7.1. A pplicability...........................................................................................

TS-33 3.7.3. O bjective...............................................................................................

TS-33 3.7.4. Specification..........................................................................................

TS-33 3.7.5. Actions...........................................

TS-33 3.7.6. Bases.....................................................................................................

TS-34 3.8 REACTOR POOL WATER TS-35 3.8.1. A pplicability................................................................................

I.......... TS-35 3.8.3. O bjective................................................................................................

.TS-35 3.8.4. Specification.........................

TS-35 3.8.5. Actions..............................................................................

TS-35 3.8.6. Basis....................................................................................

.......... TS-36 3.9 Retest Requirem ents......................................................................................

TS-38 3.9.1. Applicability...................................

....... TS-38 3.9.3..Objectiv............................

TS-38 3.9.3. O bjective............................................................................... *......;.......... TS-38 3.9.4. Specification

................... TS-38 3.9.5. Actions............................................

TS-38 3.9.6. Basis.............................................

TS-38

4. SURVEILLANCES.....

,...... I.................

TS-39 4.1 CORE REACTIVITY.........

TS-39 4.1.1. Objective.................

TS-39 4.1.2. Specification...........

TS-39 4.1.3. Basis..................

TS-39 4.2 PULSE MODE............................................

TS-40 4.2.1. Objective...................................

TS-40 4.2.2. Specification........................................

TS-40 4.2.3. Basis.....

0 TS-40 4.3 MEASURING CHANNELS....................................

TS-41 4.3.1. Objective...................

TS-41 4.3.2. Specification.......................

TS-41 4.3.3. Basis.............................................

TS-42 4.4 SAFETY CHANNEL AND CONTROL ROD OPERABILITY.....................................

TS-43 4.4.1. O bjective............................... ;............................................................. TS-43 01/2012 TS7 2

UT TRIGA II TECHNICAL SPECIFICATIONS 4.4.2. Specification.............................................................................

I........... TS-43 4.4.3. Bases............................................ TS-43 4.5 GASEOUS EFFLUENT CONTROL TS-45 4.5.1. O bjective...............................................................................................

TS-45 4.5.2. Specification.....................

TS-45 4.5.3. Bases.................

.............. TS-45 4.6 LIMITATIONS ON EXPERIMENTS...............................

TS-46 4.6.1. Objective..........................................

TS-46 4.6.2. Specification........................................

TS-46 4.6.3. Bases TS-46 4.7 FUEL INTEG RITY.............................................................................................

15-47 4.7.1. O bjective...............................................................................................

TS-47 4.7.2. Specification........................................

TS-47 4.7.3. Basis TS-47 4.8 REACTOR POOL WATER TS-47 4.8.1. O bjective...............................................................................................

TS-48 4.8.2. Specification........................................

TS-48

.4.8.3. Basis......................................................................................................

TS-48 4.9 RETEST REQUIREM ENTS..................................................................................

TS-50 4.9.1. Objective..........................................

TS-50 4.9.2. Specification..........................................................................................

TS-50 4.10.3. Basis............

TS-50

5.

DESIG N FEATU RES.................................................................................

................ TS-51 5.1 REACTO R FUEL.............................................................................................

TS-51 5.1.1. Applicability......................

TS-51 5.1.2. Objective..

TS-51 5.1.3. Specification........................................

...... TS-51 5.1.4. Basis......................................................................................................

TS-51 5.2 REACTOR FUEL AND FUELED DEVICES IN STORAGE..............

.TS-51 5.2.1. Applicability...............................

TS-51 5.2.2. Objective................

• TS-51 5.2.3. Specification........................

TS-52 5.2.4. Basis.................................................

.............................................. TS-52 5.3 REACTOR BUILDING.......................................

TS-52 5.3.1. A pplicability........................................................

............. TS-52 5.3.2. O bjective...............................................................................................

TS-52 5.3.3. Specification.........................................................................................

TS-52 5.3.4. Basis.............................................................

.......................................... TS -53 5.4 EXPERIM ENTS..................................................................................................

TS-53 5.4.1. Applicability........................................................................................ TS-53 5.4.2. O bjective.........................................

..................................................... TS-53 5.4.3. Specification........

.................................. TS-53 5.4.4. Basis......................................................................................................

TS-54 "S-.3 01/20,12

TECHNICAL SPECIFICATIONS

6. ADMINISTRATIVE CONTROLS.................................................................................

TS-56 6.1 ORGANIZATION AND RESPONSIBILITIES OF PERSONNEL...............................

TS-56 6.1.1 STRUCTURE....................................................................................................

TS-56 6.1.2 FUNCTIONAL RESPONSIBLITY.......................................................................

TS-57 6.1.3 STAFFING.......................................................................................................

TS-61 6.2 REVIEW AND AUDIT........................................................................................

TS-62 6.2.1 COMPOSITIONS AND QUALIFICATIONS.........................................................

TS-62 6.2.2 CHARTER AND RULES.....................................................................................

TS-62 6.2.3 REVIEW FUNCTION.......................................

TS-62 6.2.4 AUDIT FUNCTION...........................................................................................

TS-63 6.3 PROCEDURES..................................................................................................

TS-63 6.4 REVIEW OF PROPOSALS FOR EXPERIMENTS..................................................

TS-64 6.5 OPERATOR REQUALIFICATION........................................................................

TS-66 6.6 EMERGENCY PLAN AND PROCEDURES...........................................................

TS-66 6.7 PHYSICAL SECURITY PLAN..............................................................................

TS-66 6.8 ACTION TO BE TAKEN IN THE EVENT A SAFETY LIMIT IS EXCEEDED.............. TS-66 6.9 ACTION TO BE TAKEN IN THE EVENT OF A REPORTABLE OCCURRENCE...................................................................

TS-67 6.10 PLANT OPERATING RECORDS.........................................................................

TS-68 6.11 REPORTING REQUIREMENTS.................................................................................

TS-69 01/2012 TS-4

UT TRIGA II TECHNICAL SPECIFICATIONS

1.

DEFINITIONS The following frequently used terms are defined to aid in the uniform interpretation of these specifications. Capitalization is used in the body of the Technical Specifications to identify defined terms.

ACTION Actions are steps to be accomplished in the event a required condition identified in a "Specification" section is not met, as stated in the "Condition" column of "Actions."

In using Action Statements, the following guidance applies:

Where multiple conditions exist in an LCO, actions are linked to the failure to meet a "Specification" "Condition" by letters and number.

Where multiple action steps are required to address a condition, COMPLETION TIME for each action is linked to the action by letter and number.,

AND in an Action Statement means all linked steps need to be performed to complete the action; OR indicates options and alternatives, only one item needs to be performed to complete the action.

If a "Condition" exists, the "Action" consists of completing all steps associated with the selected option (if applicable) unless the "Condition" is corrected prior to completion of the steps.

ANNUAL 12 months, not to exceed 15 months.

BIENNIAL Every two years, not to exceed a 30 month interval.

A channel is the combination of sensor, line, amplifier, and output CHANNEL devices that are connected for the purpose of measuring the value of a parameter.

CHANNEL A channel calibration is an adjustment of the channel so that its CALIBRATION output responds, with acceptable range and accuracy, to known values of the parameter that the channel measures.

CHANNEL CHECK A channel check is a qualitative verification of acceptable performance by observation of channel behavior. This verification shall include comparison of the channel with expected values, other TS-'5 01/2012

TECHNICAL SPECIFICATIONS independent channels, or other methods of measuring the same variable where possible.

A channel test is the introduction of an input signal into a channel to verifythat it is operable.

CHANNEL TEST NOTE:

A functional test of operability is a channel test.

CONFINEMEI CONFINEMEr ISOLATION CONTROL RO (STANDARD)

CONTROL RO (TRANSIENT)

DAILY ENSURE EXCESS REACTIVITY EXPERIMENT qT 4T D

The enclosure which controls the movement of air into and out of the reactor bay through a controlled path.

Condition for reactor bay ventilation where:

(1) dampers controlling confinement ventilation are closed, and (2) confinement ventilation fans are secured (3) the reactor bay fume/sort hood fans are secured (4) the reactor bay fume/sort hood dampers are closed The purge system may be operated in manual override A standard control rod (stainless steel clad, borated graphite, B4C powder, or boron and its compounds in solid form with a fuel follower' is one having an electric induction or stepper motor drive coupled to the control rod by an electromagnet, with scram capability.

)D.:

A transient control, rod (aluminum clad, borated graphite,1 B4C powder;, or boron'and its compounds in ýsolid form followed by air or aluminum) is one that is pneumatically coupled to the control rod drive, is capable of initiating a power pulse, is operated by a

-..-motor drive, and/or air pressure operated and has scram capability.

Prior to initial operation each calendar day (when the.'reactor is operated), or before an operation extending more than 1 day Verify existence of specified condition or (if condition does not meet criteria) take action necessary'to meet condition That amount of reactivity above, the critical: condition which would exist if all the control rods were moved-to the maximum positive reactivity condition An EXPERIMENT is (1) any apparatus, device, or material placed in the reactor core region (in an EXPERIMENTAL FACILITY associated with the reactor, or in line with a beam of radiation emanating from 01/2012 TS-6

UT TRIGA II TECHNICAL SPECIFICATIONS EXPERIMENTAL FACILITY IMMEDIATE INITIAL STARTUP INTSTRUMENTED FUEL ELEMENT LUMITING CONDITION FOR OPERATION (LCO)

LIMITING SAFETY SYSTEM SETTING (LSSS)

MEASURED VALUE the reactor) or (2) any in-core operation designed to measure reactor characteristics.

Experimental facilities are the beamports, pneumatic transfer systems, central thimble, rotary specimen rack, and displacement of fuel element positions used for EXPERIMENTS (single-element positions and the multiple element positions fabricated in the upper grid plate displacing 3, 6 or 7 elements).

Without delay, and not exceeding one hour.

NOTE:

IMMEDIATE permits activities to restore required conditions for up to one hour; this does not permit or imply either deferring or postponing action 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 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.

An instrumented fuel element (GFE) is a stainless steel clad fuel element containing three sheathed thermocouples embedded in the fuel element.

The lowest functional capabiiity or performance levels of equipment required for safe operation of the facility.

Settings for automatic protective devices related to those variables having significant safety functions. Where a limiting safety system setting is specified for a variable on which a SAFETY LIMIT placed, the setting shall be chosen so that the automatic protective action will correct the abnormal situation before a SAFETY UMIT is exceeded.

The measured value of a parameter is the value as indicated at the output of a MEASURING CHANNEL.

ITS--,

01/2012

TECHNICAL SPECIFICATIONS MONTHLY 30 days, not to exceed 6 weeks.

MOVABLE EXPERIMENT OPERABLE OPERATING PULSE MODE QUARTERLY REACTOR SAFETY SYSTEM REACTOR" SECURED MODE A MOVABLE EXPERIMENT is one the EXPERIMENT may be moved into, out-of or near the reactor while the reactor is OPERATING.

A system or component is OPERABLE when it is capable of performing its intended function in a normal manner A system or component is _OPERATING when it is performing its intended function.

The reactor is in the PULSE MODE when the key switch is in the "on" position, the reactor mode selection switch is in the pulse position and the reactor display indicates pulse mode.

NOTE:

In the PULSE MODE, reactor power may be increased on a period of much less than I second by motion of the transient control rod.

3 months, not to exceed 4 months The REACTOR SAFETY SYSTEM is that combination of MEASURING CHANNELS and associated circuitry that is designed to initiate a reactor scram or that pro.vides.information that requires manual protective action to be initiated.

The reactor is secured when the conditions of either item (1) or item (2) are satisfied:

(1)

There is insufficient moderator orinsufficient fissile material in the reactor to attain criticality under optimum available conditions of moderation and reflection (2)

All of the following:

a.

At least three control rods are fully inserted b..

The console key is it 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 the drive is physically decoupled from the control rod) 01/2012 TS;-8

UT TRIGA II TECHNICAL SPECIFICATIONS

/

REACTOR SHUTDOWN REFERENCE CORE CONDITION SAFETY CHANNEL SAFETY LIMITS SECURED EXPERIMENT SHALL (SHALL NOT)

SEMIANNUAL SHUTDOWN MARGIN STANDARD FUEL ELEMENT

d.

No experiments are being moved or serviced that have, on movement, a reactivity worth greater than

$1.00 The reactor is shutdown if it is subcritical by at least the minimum required amount of reactivity (SHUTDOWN MARGIN) in the REFERENCE CORE CONDITION with the reactivity worth of all experiments included.

The condition of the core when it is at ambient temperature (cold) and the reactivity worth of xenon is negligible (<$0.30)

A safety channel is a MEASURING CHANNEL in the REACTOR SAFETY SYSTEM.

Limits on important process variables which are found to be necessary to protect reasonably the integrity of the principal barriers (i.e., fuel element cladding) which guard against the uncontrolled release of radioactivity.

The principal barrier is the fuel element cladding.

A secured EXPERIMENT is an EXPERIMENT held firmly in place by a mechanical device or by gravity: providing that the weight of the EXPERIMENT is such that it cannot be moved by forces (1) normal to the operating environment of the experiment or (2) that might result from credible failures.

Indicates specified action is required/(or required not to be performed)

Every six mohths, with intervals -not greater than 7 Y months The shutdown margin' is 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 (the highest worth MOVEABLE EXPERIMENT in its most positive reactive state, each SECURED EXPERIMENT in its most reactive state), with the most reactive rod in the most reactive position, and that the reactor will remain subcritical without further operator action.

A standard fuel element is a single TRIGA element of standard type, U-ZrH clad in stainless steel with nominal hydrogen to zirconium ratio of 1.6.

T$:9 0"I/2012

TECHNICAL SPECIFICATIONS STEADY-STATE MODE TECHNICAL SPECIFICATION VIOLATION WEEKLY The reactor is in the steady-state mode when the key switch is in the "on" position, the reactor mode selector pushbutton switch has requested either the manual, automatic, or square wave position and the reactor display indicates manual, automatic, or square wave.

(1) A violation of a SAFETY LIMIT occurs, when the SAFETY LIMIT value is exceeded.

(2) A violation of a Limiting Safety System Setting or Limiting Condition for Operation) occurs when a "Condition" exists which does not meet a "Specification" and the corresponding "Action" has not been met within, the required "Completion Time."

A violation has not occurred if the "Action" statement of (1) an LSSS or LCO is completed or (2) the "Specification" is restored within the prescribed "Completion Time,"

NOTE "Condition," "Specification," "Action," and "Completion Time" refer to applicable titles of sections in individual Technical Specifications 7 days, not to exceed 10 days 01/2012 TS-I,0

UT TRIGA II TECHNICAL SPECIFICATIONS

2.

SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1 Fuel Element Temperature SAFETY LIMIT 2.1.1 Applicability Specification A and B apply with the reactor in STEADY STATE MODE, REACTOR SHUTDOWN condition, REACTOR SECURED MODE and the PULSE MODE; specification B applies in STEADY STATE MODE.

2.1.2 Objective This SAFETY LIMIT ensures fuel eiement cladding integrity 2.1.3 Specification 2.1.4 Actions CONDITION REQUIRED ACTION COMPLETION TIME A.

Stainless steel clad, A.

ENSURE SHUTDOWN high-hydride fuel condition A. IMMEDIATE element temperature AND exceeds 1150 0C.

Report per Section 6.8 B. ENSURE SHUTDOWN B. Fuel temperature condition exceeds 7500C in B. IMMEDIATE steady state conditions AND Report per Section 6.8 2.1.5 Bases Safety Analysis Report Chapter 4 (4.2.1 B) identifies design and operating constraints for TRIGA fuel that will ensure cladding integrity is not challenged.

NUREG 1282 identifies the SAFETY LIMIT for the high-hydride (ZrHl.6) fuel elements with stainless steel cladding based on the stress in the cladding (resulting from the hydrogen pressure from the dissociation of the zirconium hydride). This stress will remain below the yield strength of the stainless steel cladding with fuel temperatures below 11500C.

A change in yield strength occurs for stainless steel cladding temperatures of 500°C, but TS-I ;

01/2012

TECHNICAL SPECIFICATIONS there is no scenario for fuel cladding to achieve 5000C while submerged or in air; consequently the SAFETY LIMIT during reactor operations is 1150 0C.

Therefore, the important process variable for a TRIGA reactor is the fuel element temperature. This parameter is well suited as a single specification, and it is readily measured. During operation, fission product gases and dissociation of the hydrogen and zirconium builds up gas inventory in internal components and spaces of the fuel elements.

Fuel temperature acting on these gases controls fuel element internal pressure.

Limiting the maximum temperature prevents excessive internal pressures that could be generated by heating these gases.

Fuel growth and deformation can occur during normal operations, as described in Chapter 4 (4.2.1 Z). Damage. mechanisms include fission recoils and fission gases, strongly influenced by thermal gradients. Limiting steady state operating fuel temperature to less than 750°C limits potential fuel growth.

01/2012 TS-1 2

UT TRIGA II TECHNICAL SPECIFICATIONS 2.2 Limiting Safety System Settings (LSSS) 2.2.1 Applicability This specification applies when the reactor in STEADY STATE MODE 2.2.2 Objective The objective of this specification is to ensure the SAFETY LIMIT is not exceeded.

2.2.3 Specifications A

Power level SHALL NOT exceed 1100 kW Ith) in STEADY STATE MODE of operation B

Instrumented elements in the B or C ring SHALL indicate less than 550°C 2.2.4 Actions CONDITION REQUIRED ACTION COMPLETION TIME A.1 Reduce power to less than A.1 IMMEDIATE 1100 kW (th)

A.

Steady state power level exceeds 1100 kW OR (th)

A.2. ENSURE REACTOR SHUTDOWN condition A.2. IMMEDIATE B.1. ENSURE REACTOR B.2. IMMEDIATE B. An INTSTRUMENTED SHUTDOWN condition FUEL ELEMENT in the B or C ring indicates OR greater than 5500C B.2 VERIFY the MEASURED B.2 IMMEDIATE VALUE is not correct 2.2.5 Bases Analysis in SAR Chapter 4 (4.6 B) demonstrates that if operating thermal (th) power is 1100 kW, the maximum steady state fuel temperature is less than the SAFETY LIMIT for steady state operations by a large margin. For normal pool temperature, calculations in Chapter 4 demonstrate that the heat flux of the hottest area of the fuel rod generating the highest power level in the core during operations is less than the critical heat flux by a large margin up to the maximum permitted cooling temperatures; margin remains even at temperatures approaching bulk boiling for atmospheric conditions. Therefore, TS-13 01/2012

TECHNICAL SPECIFICATIONS steady state operations at a maximum of 1100 kW meet requirements for safe operation with respect to maximum fuel temperature and thermal hydraulics by a wide margin.

Steady state operation of 1100 kW was assumed in analyzing the loss of cooling and maximum hypothetical accidents. The analysis assumptions are protected by assuring that the maximum steady state operating power level is 1100 kW.

The actual safety system setting will be chosen to ensure that a scram will occur at a level that does not exceed 1,100 kW.

Instrumented fuel element temperatures less than 550°C ensures the SAFETY LIMIT on fuel temperature is met.

01/2012 TS-14

UT TRIGA II TECHNICAL SPECIFICATIONS

3. LIMITING CONDITIONS FOR OPERATION (LCO) 3.1 Core Reactivity 3.1.1 Applicability These specifications are required prior to entering STEADY STATE MODE or PULSING MODE in OPERATING conditions; reactivity limits on experiments are specified in Section 3.8.

3.1.2 Objective This LCO ensures the reactivity control system is OPERABLE, and that an accidental or inadvertent pulse does not result in exceeding the SAFETY LIMIT.

3.1.3 Specification The maximum available core reactivity (EXCESS REACTIVITY) with all control rods fully withdrawn does not exceed 4.9% Ak/k ($7.00) when:

A

1.

REFERENCE CORE CONDITIONS exists

2. No MOVEABLE EXPERIMENTS with net-negative reactivity worth are in place SHUTDOWN MARGIN in REFERENCE CORE CONDITIONS is more than 0.2% Ak/k

($0.29) 3.1.4 Actions CONDITION REQUIRED ACTION COMPLETION TIME A.1 ENSURE REACTOR A.1 IMMEDIATE A. Reactivity with all control SHUTDOWN rods fully withdrawn AND exceeds 4.9% Ak/k

($7.00)

A.2 Configure reactor to A.2 Prior to continued meet LCO operations

'I-S-1 5 0 01/2012

TECHNICAL SPECIFICATIONS B.1.a ENSURE operable B.1 IMMEDIATE control rods are fully inserted AND B.1.b Secure electrical power to the control rod circuits (magnet B. The reactor is not or motor power) subcritical by more than B.2 Prior to continued 0.2% Ak/k ($0.29) under AND operations specified conditions B.1.c Secure all work on in-core experiments or installed control rod drives AND B.2 Configure reactor to meet LCO 3.1.5 Bases The stated value for excess reactivity was used in establishing core conditions for calculations in SAR Chapter 13 (13.4) to demonstrate fuel temperature limits are met during potential accident scenarios under extremely conservative conditions of analysis.

Since the fundamental protection for the UT reactor is the maximum power level and fuel temperature that can be achieved with the available positive core reactivity, experiments with positive reactivity are included in determining excess reactivity. Since experiments with negative reactivity will increase available reactivity if they are removed during operation, they are not credited in determining excess reactivity.

Analysis shows that at the limiting pool water temperature and zero power, fuel temperature approaches 950°C with a reactivity addition of $5.94, and 1050°C with a reactivity addition of $5.66, while a $4.00 reactivity addition results in peak fuel temperature of about 770°C. If the pulse occurs with the reactor operating at 880 MW, a $4.00 reactivity insertion results in peak fuel temperature of 930'C; this is only 3%

below the SAFETY LIMIT for cladding with temperature greater than 500°C, but is well below the SAFETY LIMIT when cladding temperature is less than 500'C. Since the cladding temperature is shown to be less than 5000C with the reactor operating in Chapter 4, worst-case steady state operation at 880 kW leads to a maximum fuel temperature well below the SAFETY LIMIT.

01/2012 TS-16

UT TRIGA II TECHNICAL SPECIFICATIONS The limiting SHUTDOWN MARGIN is necessary so that the reactor can be shut down from any operating condition, and will remain shutdown after cool down and xenon decay, even if one control rod (including the transient control rod) should remain in the fully withdrawn position. Analysis in Chapter 4 (4.5.1) demonstrates the capability of the control rods to meet this requirement.

"1S-1117 0"112012

TECHNICAL SPECIFICATIONS 3.2 PULSED MODE Operations 3.2.1 Applicability These specifications apply to operation of the reactor in the PULSE MODE.

3.2.2 Objective This Limiting Condition for Operation prevents fuel temperature SAFETY LIMIT from being exceeded during PULSE MODE operation.

3.2.3 Specification The transient rod drive is positioned for reactivity insertion (upon withdrawal) less than or equal to 2.8% 6k ($4.00) 3.2.4 Actions CONDITION

• REQUIRED ACTION COMPLETION TIME A. With all stainless steel A.1 Position the transient rod A.1 IMMEDIATE cl 'drive for pulse rod worth clad fuel elements, the less than or equal to $4.00 worth of the pulse rod in the transient rod drive OR position is greater than OR

$4.00 in the PULSE A.2 Place reactor in STEADY A.2 IMMEDIATE MODE MODE STATE MODE 3.2.5 Bases The value for pulsed reactivity-with allstainless steel elements in-the core was used in establishing core conditions for calculations in SAR Chapter 13 (13.4) that demonstrate fuel temperature limits are met during potential accident scenarios under extremely conservative conditions of analysis.

01/2012 T.$-,1 8

UT TRIGA II TECHNICAL SPECiFICATIONS 3.3 MEASURING CHANNELS 3.3.1 Applicability This specification applies to the reactor MEASURING CHANNELS during STEADY STATE MODE and PULSE MODE operations.

3.3.2 Objective The objective is to require that sufficient information is available to the operator to ensure safe operation of the reactor 3.3.3 Specifications A

The MEASURING CHANNELS specified in TABLE 1 SHALL be OPERATING B

The neutron count rate on the startup channel is greater 2 mW TABLE 1: MINIMUM MEASURING CHANNEL COMPLEMENT Minimum Number Operable MEASURING CHANNEL I

STEADY STATE PULSE MODE PUODEOD Reactor power level['1 2

A E1 Primary Pool Water Temperature 1

1 Fuel Temperature 1

1 Pool area radiation monitor 2 1

1[2 Lower or middle level area mrndtort 1

1 Argon 41 effluent monitor1 3 1

1 Particulate air continuous air monitor 1

1 NOTE[1]: One "Startup Channel" required to have range that indicates <10 W NOTE[2]: High-level alarms audible in the control room may be used NUTE[3], Whený the auxiliary: purge system.s OPlerating TS-1 9 01/2012

TECHNICAL SPECIFICATIONS 3.3.4 Actions CONDITION REQUIRED ACTION COMPLETION TIME A.1.1 Restore channel to A.1.1 IMMEDIATE operation A.1 Reactor power channels not OPERATING (min 2 for STEADY STATE, 1 OR PULSE MODE)

A.1.2 ENSURE reactor is

__________________SHUTOWNA.1.2 IMMEDIATE

• SHUTDOWN A.2 Communications between DAC and A.2.1 Establish REACTOR control console SHUTDOWN condition interrupted > 10 s OR "AND A.2. IMMEDIATE High voltage to reactor safety channel (power level) detector less than A.2.2 Enter REACTOR SECURED 80% of required mode operating value A.3.1 Restore channel to operation A.3.1 IMMEDIATE OR A.3 Primary water O

A rmaerwaturereor a

A.3.2 Monitor pool water temperature A.3.2 IMMEDIATE differential pressure or AND fueltemperature CHANNEL not operable OR At least once per hour A.3.3 ENSURE reactor is A.3.3.3 IMMEDIATE SHUTDOWN 01/2012 TS-20

UT TRIGA II TECHNICAL SPECIFICATIONS CONDITION REQUIRED ACTION COMPLETION TIME A.4.1 Restore MEASURING A.4.1 IMMEDIATE CHANNEL OR A.4.2 ENSURE reactor is A.4.2 IMMEDIATE shutdown A.4. Pool Area Radiation OR Monitor is not A.4.3 IMMEDIATE OPERATING A.4.3 ENSURE personnel are not on the upper level OR A.4.4 IMMEDIATE A.4.4 ENSURE personnel on upper level are using portable survey meters to monitor dose rates

, A,5.1 Restore.MEASURING A.5.1 IMMEDIATE CHANNEL,_.

OR A.5.2 ENSURE reactor is A.5.2 IMMEDIATE shutdown A.5 Lower or middle level *~A.5.3 IMMEDIATE area moni tor is not A53IMEIT A.5.3 ENSURE personnel are OPERATING not in the reactor bay

-.or A.5.4 IMMEDIATE A.5.4 ENSURE personnel entering reactor bay are using portable survey meters to monitor dose rates rTS-2, 01"2012

TECHNICAL SPECIFICATIONS CONDITION REQUIRED ACTION COMPLETION TIME A.6.1 Restore MEASURING A.6.1 IMMEDIATE CHANNEL.

OR A.6.2 ENSURE reactor is A.6.2. IMMEDIATE shutdown A.6. Argon monitor is not OR OPERATING A.6.3.a. IMMEDIATE A.6.3.a ENSURE continuous air radiation monitor is OPERATING AND A.6.3.b Within 30 A.6.3.b Restore MEASURING working days CHANNEL A.7.1 Restore MEASURING A.7.1 IMMEDIATE CHANNEL OR A.7.2 ENSURE reactor is' A.7.2. IMMEDIATE shutdown A.7 Continuous particulate air radiation monitor is not OPERATING A.7.3.a ENSURE Argon 41 monitor radiation.

monitor is OPERATING "A.7.3.b Within 30 A.7.3.b Restore MEASURING working days

CHANNEL, 3B.1 Do not perform a reactor' B.1 IMMEDIATE B. The neutron count rate startup on the startup channel OR is riot greater than x107 B.2 Perform a neutron-source check-on the startup B.2 IMMEDIATE channel prior to. startup 01t2012 TS-22

UT TRIGA II TECHNICAL SPECIFICATIONS 3.3.5 Bases Maximum steady state power level is 1100 kW; neutron detectors measure reactor power level. Chapter 4 and 13 discuss normal and accident heat removal capabilities.

Chapter 7 discusses radiation detection and monitoring systems, and neutron and power level detection systems.

Communications between the digital acquisition system and the control console computer is monitored by a periodic signal.

If the periodic signal stops, the control system initiates a SCRAM.

According to General Atomics, detector voltages less than 80% of required operating value do not provide reliable, accurate nuclear instrumentation. Therefore, if operating voltage falls below the minimum value the power level channel is inoperable.

Pool water temperature indication is required to assure water temperature limits are met, protecting primary cleanup resin integrity. Analysis in Chapter 4 and 13 assume a maximum fuel temperature based on protection of -resin integrity. Fuel temperature indication provides a means of observing that the SAFETY LIMITS are met.

The upper and lower level area radiation monitors provide information about radiation hazards in the reactor bay.

A loss of reactor pool water (Chapter 13), changes in shielding effectiveness (Chapter 11), and releases of radioactive material to the restricted area (Chapter 11) that could cause changes in radiation levels within the reactor bay detectable by these monitors.

Portable survey instruments will detect changes in radiation levels.

The air monitors (continuous particulate air-and argon radiation-monitor) provide indication of; airborne contaminants in the reactor bay.

These channels provide evidence of fuel element failure on, :independent channels; the particulate air monitor gas has maximum sensitivity to iodine and particulate activity, while the argon channel detects noble gas.

Permitting operation using a.single channel of atmospheric monitoring will reduce unnecessary shutdowns while maintaining the ability to detect abnormal conditions as.. they develop..

Relative: indications ensure discharges are routine; abnormal indications trigger investigation or action to prevent the release of radioactive material to the surrounding environment,

-Ensuring the alternate airborne contamination monitor is functioning during outages of one system provides the contamination monitoring required for detecting abnormal conditions. Limiting the outage for a single unit to a maximum of 30 days ensures radioactive atmospheric contaminants are monitored while permitting maintenance and repair outages on the other system.

TS-.23 01/2012

TECHNICAL SPECIFICATIONS SAR Chapter 13 discusses inventories and releases of radioactive material from fuel element failure into the reactor bay, and to the environment. Particulate and noble gas channels monitor more routine discharges. SAR Chapter 11 discusses routine discharges of radioactive gasses generated from normal operations into the reactor bay and into the environment.

SAR Chapters 3 and 9 identifies design bases for the confinement and ventilation system. SAR Chapter 7 discusses air-monitoring systems.

The 30 day interval is selected as adequate to accomplish complex repairs, and limited enough that with one system functional there is no significant chance that the system will fail during a period that requires detection of airborne radioactivity.

Experience has shown that subcritical multiplication with the neutron source used in the reactor does not provide enough neutron flux to correspond to an indicated power level of 2x10"7 %. Therefore an indicated power of 2x10"7 % (or 2 mW) or more indicates operating in a potential critical condition, and at least one neutron channel is required with sensitivity at a neutron flux level corresponding to reactor power levels less than 2x20 7 % ("Startup Channel"). If the indicated neutron level is less than the minimum sensitivity for the channel, a neutron source will be used to determine that the channels is responding to neutrons to ensure that the channel is functioning prior to startup.

0112012 TS-24

UT TRIGA II TECHNICAL SPECIFICATIONS 3.4 Safety Channel and Control Rod Operability 3.4.1 Applicability This specification applies to the reactor MEASURING Channels during STEADY STATE MODE and PULSE MODE operations.

3.4.2 Objective The objectives are to require the minimum number of REACTOR SAFETY SYSTEM channels that must be OPERABLE in order to ensure that the fuel temperature SAFETY LIMIT is not exceeded, and to ensure prompt shutdown in the event of a scram signal.

3.4.3 Specifications A

The SAFETY SYSTEM CHANNELS specified in TABLE 2 are OPERABLE B CONTROL RODS (STANDARD) are capable of full insertion from the fully withdrawn position in less than 1 sec.

TABLE 2: REQUIRED SAFETY SYSTEM CHANNELS Minimum Function Required OPERATING Safety System Number Mode Channel or Operable STEADY PULSE Interlock STATE MODE MODE Reactor power 2

Scram YES NA level Manual scram bar 1

Scram YES YES Fuel Temperature 1

Scram YES YES Pool water level 1

Scram YES YES CONTROL ROD Prevent withdrawal of (STANDARD) 1 standard rods in the NA YES position interlock PULSE MODE Pulse rod Prevent inadvertent interlockill 1

pulsing while in YES NA STEADY STATE MODE NOTE [1]: The pulse rod interlock prevents air from being applied to the pulse rod unless the transient rod is fully inserted except during pulse mode or square wave operations.

TS-25 01/2012

TECHNICAL SPECIFICATIONS 3.4.4 Actions CONDITION REQUIRED ACTION COMPLETION TIME A.1 Restore channel or Al. IMMEDIATE A.

Any required SAFETY interlock to operation SYSTEM CHANNEL or interlock function is not A2. IMMEDIATE OPERABLEA2IM EAT A.2 ENSURE reactor is SHUTDOWN 3.4.5 Bases The power level scram is provided to ensure that reactor operation stays within the licensed limits of 1,100 kW, preventing abnormally high fuel temperature. The power level scram is not credited in analysis, but provides defense in depth to assure that the reactor is not operated in conditions beyond the assumptions used in analysis (Chapter 4 and 13).

The manual scram allows the operator to shut down the system if an unsafe or abnormal condition occurs.

Fuel temperature scram assures the LSSS !s met..

The pool water level scram secures operation on a loss of pool water level.

The CONTROL ROD (STANDARD) interlock function is to prevent withdrawing control rods (other than the pulse rod) when the reactor is in the PULSE MODE. This will ensure the reactivity addition rate during a pulse is limited to the reactivity added by the pulse rod.

The pulse rod interlock function prevents air from being applied to the transient rod drive when it is withdrawn while disconnected from the control rod to prevent inadvertent pulses during STEADY STATE MODE operations. The control rod interlock prevents inadvertent pulses which would be likely to exceed the maximum range of the power level instruments configured for steady state operations.

01/2012 TS-26

UT TRIGA II TECHNICAL SPECIFICATIONS 3.5 Gaseous Effluent Control 3.5.1 Applicability This specification applies to gaseous effluent in STEADY STATE MODE and PULSE MODE.

3.5.2 Objective The objective is to ensure that exposures to the public resulting from gaseous effluents released during normal operations and accident conditions are within limits and ALARA.

3.5.3 Specification T

The reactor bay HVAC confinement system SHALL provide ventilation to the A

reactor bay when particulate continuous air monitor indicates less than 10,000 cpm The reactor bay confinement system will enter CONFINEMENT ISOLATION if the B

particulate continuous air monitor is in-service and indicates greater than 10,000 cpm C

Auxiliary purge system SHALL exhaust from reactor bay pool and in-use experiment areas Releases of Ar-41 from the reactor bay to an unrestricted environment SHALL NOT exceed 100 Ci per year.

TS-27 01/2012

TECHNICAL SPECIFICATIONS 3.5.4 Actions CONDITION

" REQUIRED ACTION COMPLETION TIME A.1 ENSURE reactor is A.1 IMMEDIATE SHUTDOWN OR A.2.a ENSURE auxiliary air A.2.1 IMMEDIATE purge system is OPERATING A. The reactor bay HVAC AND confinement ventilation A.3.a IMMEDIATE system is not OPERABLE A.2.b SECURE EXPERIMENT operations if failure could result in significant A.3.b IMMEDIATE release of rad. gases or aerosols.

A.3.c IMMEDIATE AND A.2.c ENSURE no irradiated fuel handing B.1 ENSURE reactor is B.1 IMMEDIATE B The particulate SHUTDOWN continuous air monitor, AND is in service and B.1 IMMEDIATE indicates greater.than B2 SECURE reactor by

1. 1 1 1)*.

., '. -a

,B, 21 S R r e a t o b a y OO0 cpm, and.the vent.lation

.......... ' " :

• Ventilation ": :* * "

reactor bay confinement system is not in AND CONFINEMENT AND ISOLATION ISOATON~~

.6.3 SECURE'the fume/sorting' hood 01/2012 TS-28

UT TRIGA II TECHNICAL SPECIFICATIONS CONDITION REQUIRED ACTION COMPLETION TIME C. The auxiliary purge system is not OPERABLE D Calculated releases of Ar-41 from the reactor bay exhaust plenum exceed 100 Ci per year.

C.1 ENSURE reactor bay HVAC confinement ventilation system is OPERATING OR C.2.a ENSURE reactor is SHU TDOWN C.2.b Secure EXPERIMENT operations for EXPERIMENT with failure modes that could result in the release of radioactive gases or aerosols C.2.c ENSURE no.irradiated fuel handling C.2.a IMMEDIATE C.2.b IMMEDIATE C.2.c IMMEDIATE C.1 IMMEDIATE

-+

-I-D. Do not operate.

D. IMMEDIATE 3.5.5 Bases The confinement and ventilation system is described in Chapter'9. R'outine' ýopoerations produce radioactive gas, principally Argon 41, in the reactor bay. fffthe 'confin'ement system is not functioning and theý purge system is not operating, raaiioactive g0sss will buildup in the reactor bay. During this.interval, experiment activities-thait-mnight cause airborne radionuclide levels to be elevated are prohibited.

Chapter 13 addresses the maximum hypothetical fission product invedtory release.

Using unrealistically conservative assumptions,:j*concentrations for a fe-'W n Wides of iodine would be in excess of occupational derived air concentrations for a matter of hours or days. 9°Sr activity available for release from fuel rods previously used at other facilities is estimated to be at most about 4 times the ALl. In either case (radio-iodine or

-Sr), there is no credible scenario for accidental inhalation or ingestion of the undiluted nuclides that might be released from a damaged fuel element. Finally, fuel element failure during a fuel handling accident is likely to be observed and mitigated immediately.

1:S-29 01/2012

TECHNICAL SPECIFICATIONS The CAP-88 (Clean Air Act Assessment Package-1988) computer model is a set of computer programs, databases and associated utility programs for estimation of dose and risk from radionuclide emissions to air. CAP-88 is composed of modified versions of AIRDOS-EPA (Mo79) and DARTAB (ORNL5692).

CAP-88 was used to analyze argon 41 effluents from the UT TRIGA reactor.

Analysis shows 100 Ci per year results in a maximum does to individuals in the effluent plume of 0.142 mrem in a year, well within the 10CFR20 limit of 10 mrem/year for stack effluents.

1. ;,,, --ý -,

-1.'

I I.. -,-1 01/2012 TS-*30

UT TRIGA II TECHNICAL SPECIFICATIONS 3.6 Limitations on Experiments 3.6.1 Applicability This specification applies to operations in STEADY STATE MODE and PULSE MODE.

3.6.2 Objectives The objective is to prevent reactivity excursions that might cause the fuel temperature to exceed the SAFETY LIMIT (with possible resultant damage to the reactor), and the excessive release of radioactive materials in the event of an EXPERIMENT failure 3.6.3 Specifications The reactivity worth of any individual MOVEABLE EXPERIMENT SHALL NOT exceed $1.00 (0.007 Ak/k)

The reactivity worth of any individual SECURED EXPERIMENT SHALL NOT exceed

$2.50 (0.0175 Ak/k)

C The total reactivity worth of all EXPERIMENTS shall not exceed $3.00 (0.021 Ak/k) 3.6.4 Actions CONDITION REQUIRED ACTION COMPLETION TIME A.1 ENSURE the reactor is A.1 IMMEDIATE SHUTDOWN A. MOVEABLE EXPERIMENT worth is greater than AND

$1.00 A.2 Remove the experiment A.2 Prior to continued operations B.1 ENSURE the reactor is B.1 IMMEDIATE SHUTDOWN B. SECURED EXPERIMENT worth is greater than AND

$2.50 B.2 Remove the experiment B.2 Prior to continued operations T8,3i S01i2012

TECHNICAL SPECIFICATIONS C.1 ENSURE the reactor is C.1 IMMEDIATE SHUTDOWN C. Total EXPERIMENT worth is greater than $3.00 C.2 Remove the experiment C.2 Prior to continued

_ _operations 3.6.5 Bases Chapter 13 demonstrates that pulsed reactivity worth less than 2.8% Ak/k ($4.00) will not challenge fuel integrity. These limits provide assurance that experiments do not exceed the reactivity analyzed; experiment limits are established lower than analysis limits is used to assure margin for experimental error.

01/2012 TS-32

UT TRIGA II TECHNICAL SPECIFICATIONS 3.7 Fuel Integrity 3.7.1 Applicability This specification applies to operations in STEADY STATE MODE and PULSE MODE.

3.7.2 Objective The objective is to prevent the use of damaged fue in the UT TRIGA reactor.

3.7.3 Specifications A

Fuel elements in the reactor core SHALL NOT be (1) elongated more than 1/10 in.

over manufactured length OR (2) laterally bent more than 1/16 in.

B Fuel elements SHALL NOT have visual indications of cladding integrity failure.

C Fuel elements in the core SHALL NOT release fission products.

3.7.4 Actions CONDITION REQUIRED ACTION COMPLETION TIME A. Any fuel element is elongated greater than Do not re-insert the fuel 1/10in.over element into the upper core IMMEDIATE manufactured length, or grid plate.

bent laterally greater than 1/16 in.

B. Fuel elements have Do insert or not re-insert the visual indication of fuel element into the upper IMMEDIATE cladding integrity failure core grid plate.

C.1 SECURE PULSE MODE C.1 IMMEDIATE operations B. Fission products are C.2.a Operate in STEADY STATE C.2.a IMMEDIATE determined to be MODE only to identify leaking from fuel the failed element elements in the core AND C.2.b When the C.2.b Remove the failed element is identified element from service TS-33 01/2012

TECHNICAL SPECIFICATIONS 3.7.5 Bases The above limits on the allowable distortion of a fuel element have been shown to correspond to strains that are considerably lower than the strain expected to cause rupture of a fuel element and have been successfully applied at TRIGA installations. Fuel cladding integrity is important since it represents the only process barrier for fission product release from the TRIGA reactor.

Lateral bend less than 1/16 in. in adjacent fuel elements assures that there is adequate clearance to prevent element contact during operation.

Limiting the use of fuel elements where cladding has been challenged as specified limits release of fission products to the minimum required for assessing fuel elements.

01/2012T TS-34

UT TRIGA II TECHNICAL SPECIFICATIONS 3.8 Reactor Pool Water 3.8.1 Applicability This specification applies to operations in STEADY STATE MODE, PULSE MODE, and SECURED MODE.

3.8.2 Objective The objective is to set acceptable limits on the water quality, temperature, conductivity, and level in the reactor pool.

3.8.3 Specifications A

Water temperature at the exit of the reactor pool SHALL NOT exceed 110°F (48.9-C)

B Water conductivity SHALL be less than or equal to 5 pVmho/cm averaged over 1 month C

Water level above the core SHALL be at least 6.5 m from bottom of the pool The pressure difference between chilled water outlet from the pool heat exchanger and pool water inlet SHALL NOT be less than 7 kPa (1 psig) 3.8.4 Actions CONDITION REQUIRED ACTION COMPLETION TIME A.1 ENSURE the reactor is A.1 IMMEDIATE SHUTDOWN AND A. Water temperature at A.2 Secure flow through the A.2 IMMEDIATE the exit of the reactor pool exceeds 110'F (48.9-C)

AND A.3 Initiate action to reduce A.3 IMMEDIATE water temperature to less than 110°F TS-135 01/2012

TECHNICAL SPECIFICATIONS CONDITION REQUIRED ACTION COMPLETION TIME B.1 ENSURE the reactor is B.1 IMMEDIATE SHUTDOWN B. Water conductivity is greater than 5 IVmho/cm B.2 Restore conductivity to less B.2 Within 1 month than 5 iVmho/cm C. Water level above the C.1 ENSURE the reactor is C.1 IMMEDIATE core SHALL be at least SHUTDOWN 6.5 m from the bottom AND of the pool for all operating conditions C.2 Restore water level C.2 IMMEDIATE D.1 ENSURE the reactor is D.1 IMMEDIATE SHUTDOWN OR D.2 Verify pressure differential D.2 IMMEDIATE DbTetpesen chiledierec is greater than 7 kPa (1 psig) between chilled water outlet from the pool OR heat exchanger and pool water inlet is less D.3 RESTORE pressure D.3 IMMEDIATE than 7 kPa (1 psig) difference to greater than 7 kPa (1 psig)

OR D.4 Isolate chill water D.4 IMMEDIATE 3.8.5 Bases The resin used in the mixed bed deionizer limits the water temperature of the reactor pool.

Resin in use (as described in Section 5.4) maintains mechanical and chemical integrity at temperatures below 110°F (48.9°C). Therefore, thermal hydraulic analysis was conducted to a maximum pool temperature of 48.9°C, and limiting pool temperature ensures analysis conditions are met.

Maintaining low water conductivity over a prolonged period prevents possible corrosion, deionizer degradation, or slow leakage of fission products from degraded cladding. Although fuel degradation does not occur over short time intervals, long-term 01/2012 TS-36

UT TRIGA II TECHNICAL SPECIFICATIONS integrity of the fuel is important, and a 4-week interval was selected as an appropriate maximum time for averaging conductivity values.

For normal pool temperature, calculations in Chapter 4 assuming 8.1 and 6.5 m above the bottom of the pool demonstrate that the heat flux of the hottest area of the fuel rod generating the highest power level in the core during operations is less than the critical heat flux by a large margin up to the maximum permitted cooling temperatures; margin remains even at temperatures approaching buik boiling for atmospheric conditions.

Therefore, pool levels greater than 6.5 rn above the pool floor meet requirements for safe operation with respect to maximum fuel temperature and thermal hydraulics by a wide margin.

The principle contributor to radiation dose rates at the pool surface is Nitrogen 16 generated in the reactor core and dispersed in the pool. Pool surface radiation dose rates from Nitrogen 16 with 6.5 m of water above the core are acceptable.

Therefore, a minimum pool level of 6.5 feet above the core is adequate to support the core cooling and provide shielding.

The specified pressure difference assures that any postulated heat exchanger leakage will not release potentially contaminated water to the chill water system.

TS-37 3012012

TECHNICAL SPECIFICATIONS 3.9 Retest Requirements 3.9.1 Applicability This specification applies to operations in STEADY STATE MODE and PULSE MODE.

3.9.2 Objective The objective is to ensure Technical Specification requirements are met following maintenance or operational activities that occur within surveillance test intervals.

3.9.3 Specifications Maintenance or operational activities SHALL NOT change, defeat or alter equipment or systems in a way that prevents the systems or equipment from being OPERABLE (when required) or otherwise prevent the systems or equipment from fulfilling the safety basis 3.9.4 Actions CONDITION REQUIRED ACTION COMPLETION TIME Maintenance or an operational activity :is performed that has the Perform surveillance Prior to continued, potential to change a normal operation in setpoint, calibration, flow OR

~STEADY ST ATE MODE rate, or other parameter or PULSE MODE that is measured or verified Operate only to perform retest in meeting a surveillance, or operability requirement 3.9.5 Bases Operation' of the UT TRIGA reactor Will' comply with the requirements of Technical Specifications..

This specificationi ensures, that if maintenance or operations might challenge a Technical Specifications requirement, the requirement is verified prior to resumption of normal operations.

01/2012 TS-38

UT TRIGA II TECHNICAL SPECIFICATIONS

4. Surveillance Requirements 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.

If a surveillance schedule cannot be met because the reactor is operating while performance requires the reactor not be operating, performance may be deferred until the reactor is shutdown.

4.1 Core Reactivity 4.1.1 Objective This surveillance ensures that the minimum SHUTDOWN MARGIN requirements and maximum excess reactivity limits of section 3.1 are met.

4.1.2 Specification SURVEILLANCE REQUIREMENTS SURVEILLANCE J FREQUENCY SHUTDOWN MARGIN Determination ANNUAL ANNUAL Following Insertion of EXCESS REACTIVITY Determination experiments with measurable positive.

Control Rod Reactivity Worth determination BIENNIAL 4.1.3 Basis Experience has shown verification of the minimum allowed SHUTDOWN MARGIN at.:the specified frequency is adequate to assure that the.limiting safety system setting is-met.

When core reactivity parameters are affected by operations or maintenance, additional activity is required to ensure changes are incorporated in reactivity evaluations.

Reactivity limits are verified by comparing critical control rod positions to reference values. The reference values change with burnup and core configuration.

Biennial evaluation of control rod position is adequate, although other activities may result in control rod worth determination through retest requirements.

"TS-39 01/2012

TECHNICAL SPECIFICATIONS 0112012 TS-40

UT TRIGA II TECHNICAL SPECIFICATIONS 4.2 PULSE MODE 4.2.1 Objectives The verification that the pulse rod position does not exceed a reactivity value corresponding to $4.00 assures that the limiting condition for operation is met.

4.2.2 Specification SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY ENSURE Transient Pulse Rod position corresponds to Prior to pulsing reactivity not greater than $4.00 operations 4.2.3 Basis Verifying pulse rod position corresponds to less than or equal to $4.00 ensures that the maximum pulsed reactivity meets the limiting condition for operation.

TS:41 01,12012

TECHNICAL SPECIFICATIONS 4.3 MEASURING CHANNELS 4.3.1 Objectives Surveillances on MEASURING CHANNELS at specified frequencies ensure instrument problems are identified and corrected before they can affect operations.

4.3.2 Specification SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Reactor power level CHANNEL CHANNEL TEST DAILY Calorimetric calibration ANNUAL CHANNEL CHECK loss of high voltage to required power level DAILY instruments CALIBRATION high voltage to required power level ANNUAL instruments Primary pool water temperature CHANNEL CHANNEL TEST DAILY CHANNEL CALIBRATION ANNUAL Fuel temperature CHANNEL CHANNEL TEST DAILY CHANNEL CALIBRATION ANNUAL Upper level Area radiation monitor CHANNEL CHECK WEEKLY CHANNEL CALIBRATION ANNUAL Lower or middle level Area Radiation Monitor CHANNEL CHECK WEEKLY CHANNEL CALIBRATION ANNUAL (Particulate) Continuous Air Radiation Monitor CHANNEL CHECK DAILY CHANNEL CALIBRATION ANNUAL Argon Monitor CHANNEL CHECK DAILY 01/2012 TS-42

UT TRIGA II TECHNICAL SPECiFICATIONS SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY CHANNEL CALIBRATION (Electronic)

BIENNIAL Startup Count Rate DAILY 4.3.3 Basis The DAILY CHANNEL CHECKS will ensure that the SAFETY SYSTEM and MEASURING CHANNELS are operable. The required periodic calibrations and verifications will permit any long-term drift of the channels to be corrected.

1"S-3 01,12012

TECHNICAL SPECIFICATIONS 4.4 Safety Channel and Control Rod Operability 4.4.1 Objective The objectives of these surveillance requirements are to ensure the REACTOR SAFETY SYSTEM will function as required. Surveillances related to safety system MEASURING CHANNELS ensure appropriate signals are reliably transmitted to the shutdown system; the surveillances in this section ensure the control rod system is capable of providing the necessary actions to respond to these signals.

4.4.2 Specifications SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Pool level scram SHALL be functionally tested MONTHLY CONTROL ROD (STANDARD) drop times SHALL be measured to have a drop time from the fully withdrawn position of ANNUAL less than 1 sec.

The control rods SHALL be visually inspected for corrosion BIENNIAL and mechanical damage at intervals BIENNIAL CONTROL ROD (STANDARD) position interlock functional SEMIANNUAL test Pulse rod interlock functional test SEMIANNUAL The CONTROL ROD (TRANSIENT) rod drive cylinder and the associated air supply system SHALL be inspected, cleaned, ANNUAL and lubricated, as necessary.

4.4.3 Basis Manual and automatic scrams are not credited in accident analysis, although the systems function to assure long-term safe shutdown conditions. The manual scram and control rod drop timing surveillance s are intended to monitor for potential degradation that might interfere with the operation of the control rod systems. The functional test of pool level trip channel assures that the channel will function on demand.

The control rod inspections (visual inspections and transient drive system inspections) are similarly intended to identify potential degradation that lead to control rod degradation or inoperability.

A test of the interlock that prevents the pulse rod from coupling to the drive in the state mode unless the drive is fully down or square wave mode is being used assures that pulses will not unintentionally occur. In particular, instrumentation alignment for the 01/2012 TS-44

UT TRIGA II TECHNICAL SPECIFICATIONS pulsing mode causes safety channels to be capable of monitoring pulse power; if pulsing occurs while the instruments are set to normal, steady state operations, they will not be capable of monitoring peak power.

A test of the interlock that prevents standard control rod motion while in the pulse mode assures that the interlock will function as required.

The functional checks of the control rod drive system assure the control rod drive system operates as intended for any pulsing operations. The inspection of the pulse rod mechanism will assure degradation of the pulse rod drive will be detected prior to malfunctions.

I S-45 S

01/2012

TECHNICAL SPECIFICATIONS 4.5 Gaseous Effluent Control 4.5.1 Objectives These surveillance ensure that routine releases are normal, and (in conjunction with MEASURING CHANNEL surveillance) that instruments will alert the facility if conditions indicate abnormal releases.

4.5.2 Specification SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY ENSURE confinement HVAC operable DAILY Prior to entering an ENSURE adequate auxiliary air purge system valve alignment operating mode with an EXPERIMENTAL FACILITY in use CONFINEMENT ISOLATION functional test MONTHLY CONFINEMENT ISOLATION damper inspection ANNUALLY Calculate Ar4l discharge SEMIANNUALLY 4.5.3 Basis Verification that the confinement HVAC system is operable daily is adequate to assure the HVAC function.

Since the experimental facilities in use may vary between operations, the auxiliary purge system valve line:up may require multiple manipulations on a given day of operations. If the EXPERIMENTALFACIrTES usied in arioperat'on do not change, a review of operating logs and records may be adequate to verify proper valve alignment.

Confinement isolation functional test frequency is adequate to ensure potential failures are detected prior to system demand.

The annual test is adequate to detect degradation of sealing surfaces.

Semiannual calculation of Argon 41 is adequate to ensure that discharge limits are met.

01/2012 TS-4.6

UT TRIGA II TECHNICAL SPECIFICATIONS 4.6 Limitations on Experiments 4.6.1 Objectives This surveillance ensures that experiments do not have significant negative:impact on safety of the public, personnel or the facility.

4.6.2 Specification SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Prior to inserting a new Experiments SHALL be evaluated and approved prior to experiment for purposes implementation.

other than determination of reactivity worth Initial insertion of a new Measure and record experiment worth of the EXPERIMENT experiment where (where the absolute value of the estimated worth is greater absolute value of the than $0.50).

estimated worth is greater than $0.50 4.6.3 Basis These surveillances support determination that the limits of 3.6 are met.

Experiments with an absolute value of the estimated significant reactivity worth (greater than $0.50) will be measured to assure that maximum experiment reactivity worths are met. If an absolute value of the estimate indicates less than $0.50 reactivity,, worth, any error less than 100% will, result in actual reactivity, less,than the assumptions used in analysis for inadvertent pulsing at low-power~operations inthe Safety Analysis Report (13.2.3, Case 1).

TS-47 0112012

TECHNICAL SPECIFICATIONS 4.7 Fuel Integrity 4.7.1 Objective The objective is to ensure that the dimensions of the fuel elements remain within acceptable limits.

4.7.2 Applicability This specification applies to the surveillance requirements for the fuel elements in the reactor core.

4.7.3 Specification SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY The STANDARD FUEL ELEMENTS SHALL be visually inspected for corrosion and mechanical damage, and measured for length and bend 500 pulses of magnitude equal, to or greater than a pulse insertion of $3.00 AND Following the exceeding of a limited safety system set point with potential for causing degradation Approximately 1/4 of the core SHALL be visually inspected BIENNIAL annually for corrosion and mechanical damage Complete full core inspection 4, not to exceed 5, years 4.7.4-Basis" The most severe stresses induced in the fuel elerments result from pulse operation of the reactor, when temperature causes increased g~s pressure. and fuel-to-cladding differential expansion. The magnitude of $3.00 pulses warrants inspection following a sufficient number of cycles.

Visual inspection of fuel elements measurements at intervals determined to identify potential degradation of fuel at the specified intervals combined with by pulsing as described is considered adequate prior to catastrophic fuel element failure.

01/2012 T-S-48

UT TRIGA II TECHNICAL SPECIFICATIONS 4.8 Reactor Pool Water This specification applies to the water contained in the UT TRIGA reactor pool.

4.8.1 Objective The objective is to provide surveillance of reactor primary coolant water quality, pool level, temperature and (in conjunction with MEASURING CHANNEL surveillances), and conductivity.

4.8.2 Specification SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Verify reactor pool water level above the inlet line vacuum DAILY breaker Verify reactor pool water temperature channel operable DAILY WEEKLY Measure reactor pool water conductivity A

t 3

At least every 30 days CALIBRATE pool water conductivity channel ANNUALLY CALIBRATE heat exchanger differential pressure channel ANNUALLY CHANNEL CHECK heat exchanger differential pressure DAILY channel with loss of differential pressure 4.9.3 Bases Surveillance of the reactor pool will ensure that the water level is adequate before reactor operation. Evaporation occurs over longer periods of time, and daily checks are adequate to identify the need for water replacement. Pool water level status (not high, not low) is indicated on the control console.

Pool water temperature must be monitored to ensure that the temperature limit related to resin will not be exceeded, and that the conditions for analysis are maintained.

A daily check on the pool temperature instrument prior to reactor operation is adequate to ensure the instrument is operable when it will be needed.

Water conductivity must be checked to ensure that the pool cleanup system is performing properly and to detect any increase in water impurities. A weekly check is adequate to verify water quality is appropriate and also to provide data useful in trend TS-49 0112012

TECHNICAL SPECIFICATIONS analysis.

If the reactor is not operated for long periods of time, the requirement for checks at least every 30 days ensures water quality is maintained in a manner that does not permit fuel degradation.

Annual calibration of the conductivity channel is adequate to assure the channel functions as required.

Annual calibration of the heat exchanger differential pressure channel has proven adequate to assure the required specification is met.

A daily functional test using loss of differential pressure is adequate to ensure the channel functions as required.

01/2012 TS-50

UT TRIGA II TECHNICAL SPECIFICATIONS 4.9 Retest Requirements 4.9.1 Objective The objective is to ensure that a system is OPERABLE within specified limits before being used after maintenance or operational activities has been performed.

4.9.2 Specification SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY Evaluate potential for maintenance or operational activities Following maintenance or operational activities to affect operability and function of equipment required by for systems of equipment Technical Specifications; for standard procedures, this evaluation is incorporated in instructions, required by Technical Specifications Perform surveillance to assure affected function meets Prior to resumption of requirements normal operations 4.9.3 Bases This specification ensures that work on systems or components has been properly carried out and that the system or component has been properly reinstalled or reconnected before reliance for safety is placed on it.

01/2012

TECHNICAL SPECIFICATIONS

5. Design Features 5.1 Reactor Fuel 5.1.1 Applicabi!ity This specification applies to the fuel elements used in the reactor core.

5.1.2 Objective The objective is to ensure 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.

5.1.3 Specification (I) The high-hydride fuel element shall contain uranium-zirconium hydride, clad in 0.020 in. of 304 stainless steel It shall contain nominally 8.5 weight percent uranium which has a maximum nominal enrichment of 20%. There shall be 1.55 to 1.80 hydrogen atoms to 1.0 zirconium atom.

(2) For the fuel loading process, elements shall be loaded in an array except for experimental facilities or for single positions occupied by control rods and a neutron. startup source..

5.1.4 Bases These typesof fuel elements have a long history of successful use in TRIGA reactors.

5.2 Reactor Fuel and Fueled Devices in Storage 5,2.1 Applicability This specification applies to reactor fuel elements in storage 5.2.2 Objective The objective is to ensure fuel elements or fueled devices in storage are maintained Subcritical in a safe condition.

01/201,2

,TS-52

UT TRIGA II TECHNICAL SPECUFICATIONS 5.2.3 Specification, (1)

All fuel elements or fueled devices shall be in a safe, stable geometry; (2)

The keff of all fuel elements or fueled devices in storage is less than 0.9; (3)

The keff of fuel elements or fueled devices in an approved shipping container will meet the applicable Certificate of Compliance specifications for keff; (4)

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

5.2.4 Bases This specification is based on American Nuclear Society standard 15.1, section 5.4.

5.3 REACTOR BUILDING 5.3.1 Applicability This specification applies to the building that houses the TRIGA reactor facility.

5.3.2 Objective The objective is to ensure that provisions are made to restrict the amount of release of radioactivity into the environment.

5.3.3 Specification (I) The reactor shall be housed in a closed room designed to restrict leakage when the reactor is in operation, with HVAC system designed to maintain negative differential pressure with respect to adjacent spaces and the environment.

(2) The minimum free volume of the reactor room shall be approximately 4120 M 3.

(3) The reactor bay HVAC confinement ventilation system and the auxiliary purge system is capable of exhausting air or other gases from the reactor room at a minimum of 60 ft. above ground level.

T S-53 01/2012

TECHNICAL SPECIFICATIONS (4) Reactor bay HVAC confinement ventilation system operation is designed to provide a minimum of 2 changes of reactor bay air per hour.

5.3.4 Bases To control the escape of gaseous effluent, the reactor room contains no windows that can be opened. The room air is exhausted through an independent exhaust system, and discharged above the roof to provide dilution.

5.4 EXPERIMENTS 5.4.1 Applicability This specification applies to the design of experiments.

5.4.2 Objective The objective is to ensure that experiments are designed to meet criteria.

5.4.3 Specifications (1)

EXPERIMENTS with design reactivity worth greater than $1.00 SHALL be securely fastened (as defined in Section I, Secured Experiment).

(2)

Design shall ensurethat failhre of an EXPERIMENT SHALL NOT lead to a direct failure of a fuel element or of other experiments that could result in a S,::measurable increase in reactivity or a measurable release. of radioactivity due

..to the associated failure..

(3)

EXPERIMENTS SHALL be designed so that they do not cause bulk boiling of

• core water

. (4),:-, EXPERIMENT -design SHALL,,ensure-no interference with control rods or shadowing of reactor control instrumentation.

(5)

EXPERIMENT design shall minimize the potential for industrial hazards, such as fire or the release of hazardous and toxic materials.

(6)

Where the possibility exists that the failure of an EXPERIMENT (except fueled EXPERIMENTS) could release radioactive gases or aerosols to the reactor bay or atmosphere, the quantity.and type ýof material shall be limited such that 01/2012 TS-54

UT TRIGA II TECHNICAL SPECIFICATIONS the airborne concentration of radioactivity is less than 1,000 times the Derived Air Concentration.

For in-core samples a decay time of five minutes following irradiation may be used in radioactive inventory calculations to account for processing prior to potential exposure.

(7)

Each fueled experiment shall be limited such that the total inventory of (1) radioactive iodine isotopes 131 through 135 in the experiment is not greater than 9.32E5 pgCi, and (2) radioactive strontium is not greater than 9.35E.4 iCi.

Alternate calculations may be accomplished to demonstrate equivalent times for protective actions based on DAC limits for specific experiments, if desired.

These limits do not apply to TRIGA fuel elements used in experiments as maximum hypothetical accident analysis applies. For in-core samples a decay time of five minutes following irradiation to account may be used in calculations.

(8)

The following assumptions shall be used in experiment design:

a.

If effluents from an experimental facility exhaust through a hold-up tank which closes automatically at a high radiation level, at least 10% of the gaseous activity or aerosols produced will escape.

b. If effluents from.an experimental facility exhaust through a filter installation designed for greater than 99% efficiency for 0.3 micron particles, at least 1,0% of the aerosols produced will escape.

c.

For materials, whose boiling point is 'above 1306F ý: and: swhere vapors formed by boiling this material could escape only through an undisturbed column of water above the core, at least 10% of these vapors will escape.

(9)

Use of explosive solid or liquid material with a Nationhal 'Fire Protection Association Reactivity (Stability) index of 2, 3, or 4 in the reactor pool or biological shielding SHALL NOT exceed the equivalent of 25 milligrams of TNT without prior NRC approval.

5.4.4 Basis Designing the experiment to reactivity and thermal-hydraulic conditions ensures that the experiment is not capable of breaching fission product barriers or interfering with the control systems (interferences from other - than reactivity w effects with the control and safety systems are also prohibited). '- Design constraints on industrial hazards TS--55 V01/2012

TECHNICAL SPECIFICATIONS ensure personnel safety and continuity of operations. Design constraints limiting the release of radioactive gasses prevent unacceptable personnel exposure during off-normal experiment conditions.

A Derived Air Concentration assumes a 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> per year exposure; if exposure is controlled to a specific time limit, such as time required for recognizing the situation and evacuating, limiting values for an experiment can be higher than a DAC.

Limits on radioiodine and radioactive strontium in fueled experiments permits a 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> evacuation time for releases of radioiodine and a 2-hour evacuation time for releases of radioactive strontium based on a TRIGA fuel distribution of the radioisotopes from fission of 2 3 5U.

01/2012 TS-56

UT TRIGA II TECHNICAL SPECIFICATIONS

6. Administrative Controls 6.1 Organization and Responsibilities of Personnel This chapter describes and discusses the Conduct of Operations at the University of Texas TRIGA. The Conduct of Operations involves the administrative aspects of facility operations, the facility emergency plan, the security plan, the Reactor Operator selection and requalification plan, and environmental reports.

License is used in Chapter 12 in reference to reactor operators and senior reactors subject to 2OCFR50.55 requirements.

6.1.1 Structure University Administration Fig. 1 illustrates the organizational structure that is applied to the management and operation of the University of Texas and the reactor facility. Responsibility for the safe operation of the reactor facility is a function of the management structure of Fig. 11.

These responsibilities include safeguarding the public and staff from undue radiation exposures and adherence to license or other operation constraints. Functional organization separates the responsibilities of academic functions and business functions. The office of the President administers these activities and other activities through several vice presidents.

Assoclate Diredor of NETI.

Feiguor e 6Servisor Health Phyni Stt r

Figure 6.1, Organzational Structure

'"Standard for Administrative Controls" ANSI/ANS - 15.18 1979

rs-57 01/2012

TECHNICAL SPECIFICATIONS NETL Facility Administration The facility administrative structure is shown in Fig. 2.

Facility operation staff is an organization of a director and at least four full time equivalent persons. This staff of four provides for basic operation requirements. Four typical staff positions consist of an associate director, a reactor supervisor, a reactor operator, and a health physicist. One or more of the listed positions may also include duties typical of a research scientist. The reactor supervisor, health physicist, and one other position are to be full time. One full time equivalent position may consist of several part-time persons such as assistants, technicians and secretaries. Faculty, students, and researchers supplement the organization. Titles for staff positions are descriptive and may vary from actual designations. Descriptions of key components of the organization follow.

Rtead= SUpvt Li I 7

"-Ily I'"

Figure 2, NETL Facility Administration 6.1.2 Functional Responsibility Vice President and Provost Vice President for University Operations Research and academic educational programs are administered through the Office of the Executive-Vice President and Provost.

Separate officers assist with the administration of research activities and academic affairs with 'functions delegated to the Dean of the College of Engineering and Chairman of the Mechanical Engineering Department.

University operations activities are administered through the Office of the Vice President for Operations. This office is responsible for multiple operational functions of the University including university support programs, human resources, campus safety and security, campus real estate, and campus planning and facilities management.

01/2012 TS-58

UT TRIGA II TECHNICAL SPECIFICATIONS Associate Vice President, Campus Safety and Security Director, Nuclear Engineering Teaching Laboratory Associate Director, Nuclear Engineering Teaching Laboratory Reactor Oversight Committee The associate vice president for campus safety and security oversees multiple aspects of safety and security on campus including environmental health and safety, campus police, parking and transportation, fire prevention, and emergency preparedness.

Nuclear Engineering Teaching Laboratory programs are directed by a senior classified staff member or faculty member. The director oversees strategic guidance of the Nuclear Engineering Teaching Laboratory including aspects of facility operations, research, and service work. The director must interact with senior University of Texas at Austin management regarding issues related to the Nuclear Engineering Teaching Laboratory.

The Associate Director performs the day to day duties of directing the activities of the facility.

The Associate Director is knowledgeable of regulatory requirements, license conditions, and standard operating practices. The associate director will also be involved in soliciting and carrying out research utilizing the reactor and other specialized equipment at the Nuclear Engineering Teaching Laboratory.

The Reactor Oversight,Committee is established through the Office of the Dean of the College-of Engineering of The -University.of Texas at Austin. Broad responsibilities of the committee include the evaluation, review, and approval of facility standards for safe operation.

The Dean shall appoint at least three members to the Committee that represent a broad spectrum of expertise appropriate to reactor technology. The committee will meet at least twice each calendar year or more frequently as c.rcumsttnces warrant. The

.Reactor Oversight Committee. shall be consulted by the Nuclear Engineering Teaching -:-LaboratMr

.:concerning unusual or exceptiona! actin&. that. affect -administration of the reactor program.

TrS-59 01/2012

TECHNICAL SPECIFICATIONS Radiation Safety Officer Radiation Safety Committee A Radiation Safety Officer acts as the delegated authority of the Radiation Safety Committee in the daily implementation of policies and practices regarding the safe use of radioisotopes and sources of radiation as determined by the Radiation Safety Committee.

The Radiation Safety Program is administered through the University Environmental Health and Safety division.

The responsibilities of the Radiation Safety Officer are outlined in The University of Texas at Austin Manual of Radiation Safety.

The Radiation Safety Committee is established through the Office of the President of The University of Texas at Austin.

Responsibilities of the committee are broad and include all policies and practices regarding the license, purchase, shipment, use, monitoring, disposal, and transfer of radioisotopes or sources of ionizing radiation at The University of Texas at Austin.

The President shall appoint at least three members to the Committee and appoint one as Chairperson. The Committee will meet at least once each year on a called basis or as required to approve formally applications to use radioactive materials. The Radiation Safety Committee shall be consulted by the University Safety Office concerning any unusual or exceptional action that affects the administration of the Radiation Safety Program.

Reactor The Reactor Supervisor shall be qualified as a senior operator, and Supervisor is. to. be knowledgeable of regulatory requirements, license conditions, and standard. operating practices. The Reactor Supervisor is responsible-for directing or performing reactor operations.

Activities of reactor operators with USNRC licenses

will be subject to the direction.of a person with a USNRC senior

-. operator license.

The reactor supervisor shall assess facility conditions and select

.:appropriate.response procedures.during normal, abnormal and emergency.situations' ;

(1) Prior to operations, the Reactor Supervisor shall ensure conditions and limitations of the

license, Technical Specifications,- and experiment approvals (as applicable) are m et.

I (2) Reactor Supervisor, shall directly supervise all INITIAL STARTUPs.

01/2012 S6 TS&W

UT TRIGA II TECHNICAL SPECIFICATIONS Health Physicist (3) The Reactor Supervisor will provide direction for, or respond to, situations requiring acVvadion of the Emergency Plan.

(4) In an emergency, the Reactor Supervisor is authorized to direct or perform a reasonable course of action that departs from a license condition or a Technical Specification when this action is immediately needed to protect the public health and safety, and no action consistent with i-cense conditions and technical specifications that can provide adequate or equivalent protection is immediately apparent 2.

Radfological safety of the Nuclear Engineering Teaching Laboratory is monitored by a health physicist, who will be knowledgeable of the facility radiological hazards.

Responsibilities of the health physicist will include calibration of radiation detection instruments, measurements of radiation levels, control of radioactive contamination, maintenance of radiation records, and assistance with other facility monitoring activities.

Activities of the health physicist will depend on two conditions.

One condition will,be the normal operation responsibilities determined by the director of the facility. A second condition will be communications specified by:the radiation safety officer. This combination of responsibility and communication provides for safety program implementation by the director, but establishes independent review. Thelhealth physicist's activities will meet the requirements of the director and the policies of an independent u niversity;safety organization; Laboratory czperations and research support is provided by a designated Laboratory Manager..

The function is typically combined with the Health Physicist position.

Reactor operatcrs (and senior. reactor operators) are licensed by the USNRC to operate the. UT TRIGA li nuclear research reactor.

University staff and/or students may be employed as reactor operators.

Staff pos;tions supporting various aspects of facility operations are assigned as required.

Radiological Controls Technicians are supervised by the Health Laboratcwry Manager Reactor Operators Technical Support Radiological 2 1oCFR5o.54(x)

'T.Sý61 01/2012

TECHNICAL SPECIFICATIONS Controls Physicist to perform radiological controls and monitoring Technicians functions.: -, -Radiological Controls Technicians are generally supported as Undergraduate Research Assistant positions.

Laboratory Laboratory Assistants are supervised by the Laboratory Manager Assistants to perform laboratory operations and analysis.

Laboratory Assistants are generally supported as Undergraduate Research Assistant positions.

6.1.3 Staffing Operation of the reactor and activities associated with the reactor, control system, instrument system, radiation monitoring system,. and engineered safety features will be the function of staff personnel with the appropriate training and certification 3.

Whenever the reactor is not secured, the reactor shall be (1) under the direction of or (2) directly operated by a (USNRC licensed) Senior Operator, designated as Reactor Supervisor.

The Supervisor may be:on call if cognizant of reactor operations and capable of arriving at the facility within thirty minutes.

Whenever the reactor is not secured, a (USNRC licensed) Reactor Operator (or Senior Reactor Operator) who meets requirements of the Operator Requalification Program shall be at the reactor: control. console, and directly :responsible for control manipulations; as indicated above, the Reactor Supervisor may be the Reactor Operator at the controls.

Only the Reactor Operator at the controls or personnel authorized by, and under direct supervision of,ý the.Reactor,Operator-,at the controls shall manipulate the controls.

Whenever the reactor is not secured, operation of equipment that has the potential to affect reactivity or power level shall be..manipulated only with the, knowledge and consent of the Reactor Operator at the controls. The Reactor Operator at the controls may authorize persons to manipulate reactivity controls who are training either as (1) a student enrolled in academic or industry course making use of the reactor, (2) to qualify for an operator license, or (3) in accordance the approved Reactor Operator requalification program.

Whenever the reactor is not secured, a second person (i.e., in addition to the reactor operator at the control console) capable of initiating the Reactor Emergency Plan will be present in the NETL building. Unexpected absence of this second person for greater than two hours will be acceptable if immediate action is taken to obtain a replacement.

3 oSelection and Training of Personnel for Research Reactors", ANSI/ANS -15.4 - 1970 (N380) 01/2012 TS-62

UT TRIGA II TECHNICAL SPECIFICATIONS If the reactor supervisor is in the NETL building and not acting as the Reactor operator at the controls, the Reactor Supervisor may act as the second person.

Staffing required for performing experiments with the reactor will be determined by a classification system specified for the experiments. Requirements will range from the presence of a certified operator for some routine experiments to the presence cf a senior operator and the experimenter for other less routine experiments.

6.2 Review and Audit The review and audit process is the responsibility of the Reactor Oversight Committee (ROC).

6.2.1 Composition and Qualifications The ROC 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 atmember 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 ROC shall-be in accordance with an established charter, including provisions for:

a.

Meeting frequency (at least twice each year, with approximately 4-8 month frequency)..

b.

Quorums (not less than one-half the membership where-the operating staff does not contribute a majority):,:,.

c.

Dissemination, review, and approva! of minutes.

d.

Use of subgroups.

6.2.3 Review Functior.

The responsibilities of the Reactor Safeguards Committee to shall include but are not limited to review of the following:

a.

All new procedures (and major revisions of procedures) with safety significance

b.

Proposed changes or modifications to reactor facility equipment, or systems having safety significance

c.

Proposed new (or revised) experiments, or classes of experiments, that could affect reactivity or result in the release of radioactivity

'1S363 01120 12

TECHNICAL SPECIFICATIONS

d.

Determination of whether items a) through c) involve unreviewed safety questions, changes in the facility as designed, or changes in Technical Specifications.

e.

Violations of Technical Specifications or the facility operating licensee

f.

Violations of internal procedures or instruction having safety significance

g.

Reportable occurrences

h.

Audit reports Minor changes to procedures and experiments that do not change the intent and do not significantly increase the potential consequences may be accomplished following review and approval by a senior reactor operator and independently by one of the Reactor Supervisor, Associate Director or Director. These changes should be reviewed at the next scheduled meeting of the Reactor Oversight Committee.

6.2.4 Audit Function The audit function shall be a selected examination of operating records, logs, or other documents.

Audits will be by a Reactor Oversight Committee member or by an individual appointed by the committee to perform the audit. The audit should be by any individual 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 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 Procedures Written procedures shall govern many of the activities associated with reactor operation. Activities subject to written procedures will include:

a.

Startup, operation, and shutdown of the reactor

b.

Fuel loading, unloading, and movement within the reactor.

c.

Control rod removal or replacement.

01/2012 TS-64

UT-TRIGA II TECHNICAL SPECIFICATIONS

d.

Routine maintenance, testing, and calibration of control rod drives and other systems that could have an effect on reactor safety.

e.

Administrative controls for operations, maintenance, conduct of experiments, and conduct of tours of the Reactor Facility.

f.

Implementing procedures for the Emergency Plan or Physical Security Plan.

Written procedures shall also govern:

a.

Personnel radiation protection, in accordance with the Radiation Protection Program as indicated in Chapter 11,

b.

Administrative controls for operations and maintenance

c.

Administrative controls for the. conduct of irradiations and experiments that could affect core safety or reactivity A master Procedure Control procedure specifies the process for creating, changing, editing, and distributing procedures.

Preparation of the procedures and minor modifications of the procedures will be by certified operators. Substantive changes or major modifications to procedures, and new prepared procedures will be submitted to the Reactor Oversight Committee for review and approval. Temporary deviations from the procedures may be made by the reactor supervisor or designated senior operator provided changes of substance are reported for review and approval.

Proposed experiments will be submitted to the reactor oversight committee for review and approval of the experiment and its safety analysis4, as indicated in Chapter 10.

Substantive changes to approved experiments will: require re-approval while insignificant changes that do not alter experiment safety may be approved by a senior operator.. and independently one of the following, Reactor Supervisor, Associate Director, or Director. Experiments will be approved first as proposed experiments for one time application, and subsequently, as approved. experiments for repeated applications following a review of the results and experience of the initial experiment implementation.

6.4 Review of Proposals for Experiments a)

All proposals for new experiments: ivolving the reactor :shall be reviewed with respect to safety in accordance with the procedures in (b) below and on the basis of criteria in (c) below.

b)

Procedures.

1.

Proposed reactor operations by an experimenter are reviewed by the Reactor Supervisor, who may determine that the operation is described by a 4 ANSI/ANS 15.6, op. cit.

J'S-65 01/2012

TECHNICAL SPECIFICATIONS previously approved EXPERIMENT or procedure. If the Reactor Supervisor determines that the proposed operation has not been approved by the Reactor Oversight Committee, the experimenter shall describe the proposed EXPERIMENT in written form in sufficient detail for consideration of safety aspects.

If potentially hazardous operations are involved, proposed procedures and safety measures including protective and monitoring equipment shall be described.

2.

The scope of the EXPERIMENT and the procedures and safety measures as described in the approved proposal, Including any amendments or conditions added by those reviewing and approving it, shall be binding on the experimenter and the OPERATING personnel. Minor deviations shall be allowed only in the manner described in Section 6 above. Recorded affirmative votes on proposed new or revised experiments or procedures indicate that the Committee determines that the proposed actions do not involve changes in the facility as designed, changes in Technical Specifications, changes that under the guidance of 10 CFR 50.59 require prior approval of the NRC, and could be taken without endangering the health and safety of workers or the public or constituting a significant hazard to the integrity of the reactor core.

3.

Transmission to the Reactor Supervisor for scheduling.

c) Criteria that shall be met before approval can be granted shall include:

1. The EXPERIMENT must meet the applicable Limiting Conditions for Operation and Design Description specifications.

2. It must not involve violation of any condition of the facility license or of Federal, State, University, or Facility regulations and procedures.

3. The conduct of testis,or experiments not described in the safety analysis report (as updpted) must be evaluated in accordance with 10CFR 50.59 to determine if the test or experiment -can be accomplished without obtaining prior NRC approval via license amendment pursuant to 10 CFR Sec. 50.90.

4. In the safety review the basic criterion is that there shall be no hazard to the reactor, personnel gr public. The review SHALL determine that there is reasonable assurance that the experiment can be performed with no significant risk to the safety of the reactor, personnel or the public.

6.5 Operator Requalification 01/2012 TS-66

UT TRIGA II TECHNICAL SPECIFICATIONS An NRC approved UT TRIGA Requalification Plan is in place to maintain training and qualification of reactor operators and senior reactor operators. License qualification by written and operating test, and license issuance or removal, are the responsibility of the U.S. Nuclear Regulatory Commission.

No rights of the license may be assigned or otherwise transferred and the licensee is subject to and shall observe all rules, regulations and orders of the Commission. Requalification tbVaining maintains the skills and knowledge of operators and senior operators during the period of the license.

Training also provides for the initial license qualification.

6.6 Emergency Plan and Procedures An NRC approved Emergency Plan following the general guidance set forth in ANSI/

ANS15.16, Emergency Planning for Research Reactors is in place. The plan specifies two action levels, the first level being a locally defined Non-Reactor Specific Event, and the second level being the lowest level FEMA classification, a Notification of Unusual Event.

Procedures reviewed and approved by the Reactor Oversight Committee are established to manage implementation of emergency response.

6.7 Physical Security Plan An NRC approved Security Plan is in place. The plan incorporates compensatory measures implemented following security postumrechanges initiated post 9/11. The Plan and portions of the procedures are classified as Safeguards Information. Security procedures implementing the plan, approved by the Reactor Oversight Committee, are established.

6.8 Action To Be Taken In The Event A SAFETY LIMIT Is Exceeded In the event that a SAFETY LIMITV is riot met,

a.

The reactor shall be shutdown and secured.

b.

The Reactor Supervisor, Asosciate Direct6r, and Director shall be notified

c.

The SAFElY LIMIVlTvioiation shall be reported to the Nuclear Regulatory Commission' within 24 hobrs'bytelephorne, confirmed via written statement by emaii, fax" or'telegraiph'

d.

A SAFETY LIMIT violation report shall be prepared within 14 days of the event to describe:"'

1.

Applicable circu6mstances leading to,e violationincluding (where known) cause and contributing factors

2. Effect of the violation on. reactor facility components, systems, and structures

3. Effect of the violation on the health and safety of the personnel and the public

4. Corrective action taken to prevent recurrence

.:TS-,67 S 01/2012

TECHNICAL SPECIFICATIONS

e.

The Reactor Oversight Committee shall review the report and any followup reports

f.

The report and any followup reports shall be submitted to the Nuclear Regulatory Commission.

g.

Operations shall not resume until the USNRC approves resumption.

6.9 Action To Be Taken In The Event Of A Reportable Occurrence a) A reportable occurrence is any of the following conditions:

1. Any actual safety system setting less conservative than specified in Section 2.2, Limiting Safety System Settings;

2. VIOLATION OF SL, LSSS OR LCO; NOTES Violation of an LSSS or LCO occurs through failure to comply with an "Action" statement when "Specification" is not met; failure to comply with the "Specification" is not by itself a violation.

Surveillance Requirements must be met for all equipment/components/conditions to be considered operable.

Failure to perform surveillance within the required time interval or failure of a surveillance test shall result in the equipment /cornponent/condition being inoperable

3. Incidents or conditions that prevented or could have prevented the performance of the intended safety functions of an engineered safety feature or the REACTOR SAFETY SYSTEM;

4. Release of fission products from the fuel that cause airborne contamination levels in the reactor bay to exceed 10CFR20 limits for releases to unrestricted areas;

5. An uncontrolled or unanticipated change in reactivity greater than $1.00;

6. An observed inadequacy in the implementation of either administrative or procedural controls, such that the inadequacy has caused the existence or development of an unsafe condition in connection with the operation of the reactor.

01/2012 TS-68

UT TRIGA II TECHNICAL SPECIFICATIONS b) In the event of a reportable occurrence, as defined in the Technical Specifications, and in addition to the reporting requirements,

1. The Reactor Supervisor, the Associate Director and the Director shall be notified.

2. If a reactor shutdown is required, resumption of normal operations shall be authorized by the Associate Director or Director

3. The event shall be reviewed by the Reactor Oversight Committee during a normally scheduled meeting 6.10 Plant Operating Records Records of the following activities shall be maintained and retained for the periods specified belows. The records may be in the form of logs, data sheets, electronic files, or other suitable forms. The required information may be contained in single or multiple records, or a combination thereof.

Lifetime Records Lifetime records are records to be retained for the lifetime of the reactor facility. (Note:

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

a.

Gaseous and liquid radioactive effluents released to the environs.

b.

Offsite environmental monitoring surveys'required by Technical Specifications.

c.

Events that impact or effect decommissioning of the facility.

d.

Radiatiorn exposure for al! Personnel monitored.

e.

Updated drawings of the reactor facility.

Five Year Period...

Records to be retained for a period of at least five years or for the life of the component involved whichever is shotir.

a.

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

5 "Records and Reports for Research Reactors", ANSI/ANS - 15.3-1974 (N399).

Tl'G-69 01/2012

TECHNICAL SPECIFICATIONS

b.

Principal maintenance operations.

C.

Reportable occurrences.

d.

Surveillance activities required by technical specifications.

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.

One Training Cycle Training records to be retained for at least one license cycle are the requalification records of licensed operations personnel. Records of the most recent complete cycle shall be maintained at all times the individual is employed.

6.11 Reporting Requirements This section describes the reports required to NRC, including report content, timing of reports, and report format. Refer to section 12.4 above for the reporting requirements for SAFETY LIMIT violations, radioactivity releases above allowable limits, and reportable occurrences. All written reports shall be sent within prescribed intervals to the United States Nuclear Regulatory Commission, Washington, D.C., 20555, Attn: Document Control Desk.

Operating Reports Routine annual reports covering the activities of the reactor facility during the previous calendar year shall be submitted to licensing authorities 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.

01/2012 TS-70

UT TRIGA II TECHNICAL SPECIFICATIONS

c.

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

d.

Tabulation of major changes in the reactor facility and procedures, and tabulation of new tests or experiments, or both, that are significantly different from those performed previously, induding conclusions;. that no new or unanalyzed safety questions were identified.

e.

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

f.

A summarized result of environmental surveys performed outside the facility.

g.

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

Other or Special Reports There shal be a report not later than the fo*!owing-working day by ýtelephone and confirmed in writing by facsimile or similar conveyance of any reportable occurrence identified in 6.9.

There shall be a written. report..describing *the. circumstances: Of any.- reportable occurrence identified in 6.9 within 14 days of occurrence.

There shall be a written report within 30 days of:

a.

Permanent changes in the fac'lity organization iivoliving-Director or Supervisor.

b.

Siggnificant changes i the transient.or accident analysis as described in the Safety Analysis Report.

J.S.,71 G11/2012

Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change

ýNIEWIVMATERIAL7 New LCO to provide requirements

! (TOC) 3.9 RETEST REQUIREMENTS for evaluating how activities affect safety function and follow on testing Actions are steps to be accomplished in the event a required condition identified in a "Specification" section is not met, as stated in the "Condition" column of "Actions."

In using Action Statements, the following guidance applies:

Where multiple conditions exist in an LCO, actions are linked to the failure to meet a "Specification" "Condition" by letters and number.

Where multiple action steps are required to address a condition, COMPLETION TIME for each action is linked to the action by Guidance for use of TS letter and number.

AND in an Action Statement means all linked steps need to be performed to complete the action; OR indicates options and alternatives, only one item needs to be performed to complete the action.

If a "Condition" exists, the "Action" consists of completing all steps associated with the selected option (if applicable) unless the "Condition" is corrected prior to completion of the steps

"'CONFINEMENT ISOLATION: Condition for reactor bay ventilation where:

(1) dampers controlling confinement ventilation are closed, and (2) confinement ventilation fans are secured (3) the reactor bay fume/sort hood fans are securedNew definition (4) the reactor bay fume/sort hood dampers are closed.

The purge system may be operated while in CONFINEMENT ISOLATION mode.

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 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.

Adapted from NUREG 0800 (14.2) and REG GUIDE 1.68 "initial startup testing" as "test activities" including

"... that confirm the design bases and demonstrate, to the extent practical, that the plant will operate in accordance with design and is capable of responding as designed to anticipated transients and postulated accidents as specified in the SAR" for item 1-3 with 4 as a facility commitment This specification ensures that if maintenance or operations might 3.9.3 Maintenance or operational activities SHALL NOT change, defeat or alter equipment or systems in a way that prevents the systems or equipment from being OPERABLE or otherwise prevent the systems or equipment from fulfilling the safety basis

Page 2of 39 Supplemental Information, Table TS-1 Proposed Technical Specifications Current Technical Specifications 3.9.4 Maintenance or an operational activity is performed that has the potential to change a setpoint, calibration, flow rate, or other parameter that is measured or verified in meeting a surveillance or operability requirement, Perform surveillance OR Operate only to perform retest Analysis of Change challenge a Technical Specifications requirement, the requirement is verified prior to resumption of normal operations.

4.9.2 Evaluate potential for maintenance or operational activities to affect operability and function of equipment required by This specification ensures that work Technical Specifications; for standard procedures, this evaluation is incorporated in instructions. Following maintenance or on systems or components has been operational activities for systems of equipment required by Technical Specifications.

properly carried out and that the system or component has been 4.9.2 Perform surveillance to assure affected function meets requirements. Prior to resumption of normal operations properly reinstalled or reconnected before reliance for safety is placed on it.

5.4 Experiments;

5.4.1 Applicability

This specification applies to the design of experiments.

5.4.2 Objective

The objective is to ensure that experiments are designed to meet criteria.

5.4.3 (1) EXPERIMENTS with design reactivity worth greater than $1.00 SHALL be securely fastened (as defined in Section I, Secured Experiment).

5.4.3 (2)

Design shall ensure that failure of an EXPERIMENT SHALL NOT lead to a direct faiiure of a fuel element or of 6ther experiments that could result in a measurable increase in reactivity or a measurable release of radioactivity due to the associated failure.

Moved material related to 5.4.3 (3) EXPERIMENTS SHALL be designed so that they do not cause bulk boiling ofcore water.

experiment design previously listed 5.4.3 (4) EXPERIMENT design SHALL ensure no interference with control rods orshadowing of reactor control instrumentation.

as LCO into the Design section 5.4.3 (5) EXPERIMENT design shall minimize the potential for industrial hazards, such as fireor the release of hazardous and toxic materials 5.4.3 (6) Where the possibility exists that the failure of an EXPERIMENT (except.fueled EXPERIMENTS) could release radioactive gases or aerosols to the reactor bay or atmosphere, the quantity and type of material shall be limited such that the airborne concentration of radioactivity is less than 1,000 times the Derived Air Concentration.

For in-core samples a decay time of five minutes following irradiation may be used in radioactive inventory calculations to account for processing prior to potential exposure.

5.4.3 (7) Each fueled experiment shall be limited such that the total inventory of (1) radioactive iodine isotopes 131 through 135..

in the experiment is not greater than 9.32E5 pCi, and (2) radioactive strontium is not greater than 9.35E4 pCi.

Alternate calculations may be accomplished to demonstrate equivalent times for protective actions based on DAC limits for.

New calculations specific experiments, if desired.

New calculations These limits do not apply to TRIGA fuel elements used in experiments as maximum hypothetical accident, analysis applies.

For in-core samples a decay time of five minutes following irradiation to account may be used in calculations.

Page 3of 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change 6.6 Emergency Plan and Procedures An NRC approved Emergency Plan following th e general guidance set forth in ANSI/ ANS15.16, Emergency Planning for Research Reactors is in place. The plan specifies two action levels, the first level being a locally defined Non-Reactor Specific Event, and the second level being the lowest level FEMA classification, a Notification of Unusual Event. Procedures reviewed and approved by the Reactor Oversight Committee are established to manage implementation of emergency response.

6.7 Physical Security Plan An NRC approved Security Plan Security Plan is in place. The plan incorporates compensatory measures implemented following security posture changes initiated post 9/11. The Plan and portions of the procedures are classified as Safeguards Information.

Security-procedures implementing the plan, approved by the Reactor Oversight Committee, are established.

IAL

-~~

.~tU<<

1.1 Certified Operators (1.1.1/1.1.2) 1.2 Channel (TOC) 1.2 Instrumentation Channel: A channel is the combination of sensor, line, amplifier, and output devices which are connected for the purpose of mea suring the value of a parameter 1.2.1 Channel Test: A channel test is the introduction of an input signal into a channel to verify that it is operable.

1.2.2 Channel Check: A 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 expected values, other independent channels, or other methods of measuring the same variable.

1.2.3 Channel Calibration: A channel calibration is'ah 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 a trip and shall be deemed 'co include a channel test.

The terms are fully understood without definitions, and USNRC Deleted approved Reactor Requalification Program identifies RO/SRO W CHANNEL: A channel is the combination of sensor, line, amplifier, and output devices that are connected for the purpose ANSI/ANS 15.1-7 of measuring the value of a parameter

"* CHANNEL TEST A channea test is the introduction of an input

signa! into a chainel Wo verify that it is operable.

.Note added for clarification

• NOTE: A Junctional test of operability is a channel test.

.CHANNEL CHECK: A channel check is a qualitative verification of acceptable performance by observation of channel behavior. This verification shall include comparison of the channel with Editorial expected values, other independent channels, or other methods of measuring the same variable where possible.

.CHANNEL CALIBRATION: A channel calibration is an adjustment of the channel so that its output responds, with acceptable range and accuracy, to known values of the parameter that the channel measures.

Editorial; calibration of argon monitor is split into electronic calibration and a source calibration and conducted at different intervals

Page 4of 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change

1.3 Confinement

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

1.4 Experiment

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 clad in stainless steel clad.

Hydrogen to zirconium ratio is nominal 1.6.

[11CONFINEMENT: The enclosure which controls the movement of air into and out of the reactor bay through a controlled path.

Editorial EXPERIMENT: An EXPERIMENT is (1) any apparatus, device, or material placed in the reactor core region (in an EXPERIMENTAL FACILITY associated with the reactor, or in line with a beam of radiation emanating from the reactor) or (2) any in-core operation designed to measure reactor characteristics.

MOVABLE EXPERIMENT: A MOVABLE EXPERIMENT is one the EXPERIMENT may be moved into, out-of or near the reactor while the reactor is OPERATING.

A secured EXPERIMENT is an EXPERIMENT held firmly in place by a mechanical device or by gravity providing that the weight of the EXPERIMENT is such that it cannot be moved by forces (1) normal to the operating environment of the experiment or (2) that might result from credible failures.

EXPERIMENTAL FACILITY: Experimental facilities are the beamports, pneumatic transfer systems, central thimble, rotary specimen rack, and displacement of fuel element positions used for EXPERIMENTS (single-element positions and the multiple element positions fabricated in the upper grid plate displacing 3, 6 or 7 elements).

Deleted Not used in specifications

Page Sof 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change 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 inthe fuel near the axial and radial midpoints.

1.7 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.

1.8 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

1.9 Operable

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

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

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

1.11.1 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.

1.11.2 Instrument System Level: Atthe protective instrument system level, protective action is the generation and transmission of the command signal for the safety shutdown equipment to operate.

Deleted Not used in specifications Deieted Not used in specifications STEADY-STATE MODE: The reactor is in the steady-state mode when the key switch is in the "on" position, the reactor mode selector pushbutton switch has requested either the manual, automatic, or square waveposition and the reactor display indicates manual, automatic, or square wave.

OPERABLE: A system or component is OPERABLE when it is No change capable of performing its intended function.

Deleted Not used as a defined term De!eted Not used as a defined term in specifications 1.11.3 Reactor Safety-System Level: At the reactor safety system level, protective action is the operation of sufficient equipment to immediately shut down the reactor.

Page 6of 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change 1.12 Reactivity, Excess: Excess reactivity is that amount of reactivity that would exist if all the control rods were moved to the maximum reactive condition from the point where the reactor is exactly critical.

1.13 Reactivity Limit: The reactivity limits are those limits imposed on the reactor core excess reactivity. Quantities are referenced to a reference core condition.

1.14 Reactor Core, Standard: A standard core is an arrangement of standard TRIGA fuel in the reactor grid plate and may include installed experiments.

1.15 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.

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

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

EXCESS REACTIVITY: That amount of reactivity above the critical condition which would exist if all the control rods were moved to the maximum positive reactivity condition Deleted Not used as a definition Deleted Not used in specification*

Deleted Not used in specification Deleted Not used in specification REACTOR SAFETY SYSTEM: The REACTOR SAFETY SYSTEM is that combination of MEASURING CHANNELS and associated circuitry that is designed to initiate a reactor scram or that provides information that requires manual protective action to be initiated.

Page 7of 39 Su pplemental Information, Table TS-1 posed Technical Specifications Current Technical Specifications Prc 1.18 Reactor Secure: The reactor is secure when:

1.18.1 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 1.18.2 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.

1.19 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.

1.20 Reference Core Condition: The condition of the core when it is at ambient temperature (cold) and the reactivity worth of xenon is negligible (<$0.30).

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

Analysis of Change 111REACTOR SECURED MODE: The reactor is secured when the conditions of either item (1) or item (2) are satisfied:

(1) There is insufficient moderator or insufficient fissile material in the reactor to attain criticality under optimum available conditions of moderation and reflection (2) All of the following:

a. No experiments are being moved or serviced that have, on movement, a reactivity worth greater than $1.00.

b. The reactivity value of fully inserted control rods exceeds the minimum shutdown margin value

c. The console key is it the OFF position and the key is removed from the lock

d. No work is in progress involving core fuel, core structure, installed control rods, or control rod drives (unless the drive is physically decoupled from the control rod)

Essentially unchanged except in referencing and using the minimum shutdown margin REACTOR SHUTDOWN: The reactor is shutdown if it is subcritical Previous definition was not by at least the minimum required amount of reactivity (shutdown consistent with minimum margin) in the REFERENCE CORE CONDITION with the reactivity shutdown requirements worth of all experiments included.

REFERENCE CORE CONDITION: The condition of the core when it is at ambient temnperature (cold) and the reactivity worth of No change xenon is negligible (<$0.30).

DELETED Not used in Specifications

Page 8of 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change 1.22 Rod, Control: A control rod is a device fabricated from neutron absorbing material or fuel which is used to establish neutron flux changes and to compensate for routine reactivity loses. A control rod may be coupled to its drive unit allowing it to perform a safety function when the coupling is disengaged.

1.22.1 Shim Rod: A shim rod is a control rod 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.

1.22.2 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.

1.22.3 Standard Rod: The regulating rod and shim rods are standard control rods.

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

1.23 Safety Limit: Safety Limits are limits on important process variables which are found to be necessary to protect reasonably the integrity of the principal barriers (i.e., fuel element cladding) which guard against the uncontrolled release of radioactivity. The principal barrier is the fuel element cladding.

1.24 Scram lime: Scram time is the elapsed time between reaching a limiting safety system set point and a specified control rod movement.

1.25: Shall, Should and May: The word shall is used to denote a requirement. The word should is used to denote a recommendation. The word may is used to denote permission, neither a requirement nor a recommendation.

11)CONTROL ROD (STANDARD): A standard control rod (stainless steel clad, borated graphite, B4C powder, or boron and its compounds in solid form with a fuel follower) is one having an electric induction or stepper motor drive coupled to the control rod by an electromagnet, with scram capability.

(1) Reduced to single definition as used in Specifications (2) lAW ANSI/ANS-15.1-2007 Section 5, control rod descriptions are revised to incorporate specific material specifications to allow reducing information in Design Specifications.

]CONTROL ROD (TRANSIENT): A transient control rod (aluminum clad, borated graphite, B4C powder, or boron and its compounds in solid form followed by air or aluminum) is one that is pneumatically coupled to the control rod drive, Is capable of initiating a power pulse, is operated by a motor drive, and/or air pressure operated and has scram capability.

(1) Reduced to single definition as used.in Specifications (2) lAW ANSI/ANS-15.1-2007 Section 5, control rod descriptions are revised to incorporate specific material specifications to allow reducing Information in Design Soeciflcatlons.

111SAFETY LIMITS: Umits on important process variables which are found to be necessary to protect reasonably the integrity of the principal barriers (i.e., fuel element cladding) which guard against No change the uncontrolled release of radioactivity. The principal barrier is the fuel element cladding.

Notcdefined Not used in the Technical Specifications as a defined term SHALL (SHALL NOT)

Indicates specified action is required/(or required not to be performed)

In the context of action statements, Should and May are not used

Page 9of 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change 1.26: 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 an safety systems starting from any permissible operating condition and with the most reactive rod in its moist reactive position, and the that reactor will remain subcritical without further operator action 1.27: Shutdown, Unscheduled: An unscheduled shutdown is defined as any unplanned shutdown of the reactor caused by actuation of the reactor safety system, operator error, equipment malfunction, or a manual shutdown in response to conditions which could adversely affect safe operation, nct including shutdowns which occur during testing or check-out operations.

1.28: Value, Measured.

1.29:Vaiue, True: The true value is the actual value of a paraimeter.

"' SHUTDOWN MARGIN: The shutdown margin is 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 (the highest worth NONSECURED EXPERIMENT in its most positive reactive state, each SECURED EXPERIMENT in its most reactive state), with the most reactive rod in the most reactive position, and that the reactor will remain subcritical without further operator action.

Clarity Deleted Not used in the Technical Specifications as a defined term Delete d "Not used in the Technical Specifications as a defined term Deleted

Not used in the Technical Specifications as a defined term 1.30: Surveillance Activities: Surveillance activities (except those specifically required for safety when the reactor is shutdown), may-be deferred during reactor shutdown, however,ý they must be completed prior to reactor startup unless reactor operation is 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.

1.31: Surveillance Intervals - Maximum intervals are to provide operational flexibility and not to reduce frequency. Established freauencies shall be maintained over the long term. Allowable, surveillance intervals shall not exceed the following:

[114. SURVIELLANCE REQUIREMENTS 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. If a surveillance schedule cannot be met because the reactor is operating while performance requires the reactor not be operating, performance may be deferred until the reactor is shutdown.

Not used in the Technical Specifications as a defined term; information relocated to Surveillance section Deleted Intervals are included in Technical Specifications as separately defined rather than grouped; 5 years, Quarterly are not used 1.31.1 - 5 years (interval not to exceed 6 years).

Deleted Not used 1.31.1 - 5 years (interval not to exceed 6 years).

Deleted Not used

Page lOof 39 Current Technical Specifications P

1.31.3 - Annual (interval not to exceed 15 months).

1.31.2 -0 2 years (interval not to exceed 2-1/2 years).

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

1.31.5 - Quarterly (interval not to exceed 4 months).

1.31.6 - Monthly (interval not to exceed 6 weeks).

1.31.7 - Weekly (interval not to exceed 10 days).

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

2.0 Safety Limit Specification(s)

The maximum temperature in a standard TRIGA fuel element shall not exceed11500C for fuel element clad temperatures less than 500'C and shall not exceed 950'C for fuel element clad temperatures greater than 5000C. Temperatures apply to any condition of operation.

upplemental Information, Table TS-1 roposed Technical Specifications ANNUAL: 12 months not to exceed 15 months.

BIENNIAL: Every two years, not to exceed a 30 month interval SEMIANNUAL: Every six months, with intervals not greater than7 Y2 months l11QUARTERLY: 3 months, not to exceed 4 months Ml]MONTHLY: 30 days, not to exceed 6 weeks.

!1]WEEKLY: 7 days, not to exceed 10 days DAILY: Prior to initial operation each calendar day (when the reactor is operated), or before an operation extending, more than, 1 day 2.1.3 Specifications (A) Stainless steel clad, high-hydride fuel element temperature SHALL NOT exceed 11500C.

(B) Steady state fuel temperature shall not exceed 7500C.

knalysis of Change Editorial Editorial Editorial Editorial Editorial Editorial (1) Analysis shows clad temperature will not exceed 5000C (2) GA data indicates steady state operations at 7500C can cause deformation Typographical error

2.1.5 Bases

Safety AnalysisReport Chapter 4 (4.2.1 B)

Page 11of 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change 2.2, LIMITING SAFETY SYSTEM SETTINGS 2.2.1 Fuel Temperature Specifications(s) The limiting safety system setting shall be 550°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) Specifications(s) The maximum operating power level for the operation of thereactor shall be 1100 kilowatts in the manual, auto and square wave modes.

2.2.3 Reactivity Insertion (Pulse) Specifications(s) The maximnum transient reactivity insertion for the pulse operation of the 'reactor shall be 2.2% Bk/k in the pulse mode.

2.2.3 Specifications (A) Power level SHALL NOT exceed 1100 kW (th) in STEADY STATE MODE of operation (B) Instrumented elements in the B or C ring SHALL indicate less than 550*C Setpoints remain the same; reactivity specification is not a setpoint or LSSS and is therefore move to an LCO 3.1.1, Excess reactivity, Maximum excess reactivity shall be 4.9%

Dk/k.

3.1.2, Shutdown Margin, The reactor shall not be operated unless the shutdown margin provided by control rods is greater than 0.2%

Dk/k with:

a. The reactor in the reference core condition.

b.

The most reactive control rod fully withdrawn.

3.1.3, Transient Insertions --Total worth of the transient rod shall be limited to 2.82 Dk/k, and the total withdrawal time for the rod shall not exceed 15 seconds.

3.1.4, The maximum available core reactivity (EXCESS REACTIVITY) with all control rods fully withdrawn does not exceed 4.9% Akk ($7.00) when:

when:

Limit!I ng value unchanged

1.

REFERENCE CORE CONDITIONS exists

2.

No MOVEABLE EXPERIMENTS with net-negative reactivity worth are in place 2B: SHUTDOWN MARGIN in REFERENCE CORE CONDITIONS Major rewording based on is more than 0.002 Ak/k ($0.29) definition; limiting value unchanged

3.2.3 Specification

The transient rod drive is positioned for Limiting value unchanged for reactivity insertion (upon withdrawal) less than or equal to 2.8%

pulsed reactivity; no safety basis 6k ($4.00) for total withdrawal time 3.7, Fuel Integrity Essentially unchanged 3.7, Fuel Integrity Essentially unchanged

Page 12of 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change 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 (a) Startup Withdrawal-Prevent rod up movement if startup signal less than 2 counts per second.

3.2.2 (b) Simultaneous Withdrawal interlock-prevent rod up movement for two or more rods.

3.2.2 (c) Non-pulse condition, prevent air actuation if rod is not down 3.2.2 (d) Pulse withdrawal - prevent withdrawal of non-pulse rod 3.2.2 (e) Transient Withdrawal-prevents air actuation if linear power is more than 1 kilowatt.

3.4.3 Specifications, CONTROL RODS (STANDARD) are capable of full insertion from the fully withdrawn position in less than 1 sec.

(a) Safety function is a reactor scram, (b) specification for insertion unchanged, (c) pulsed insertion bounds motor driven insertion Safety basis is operability of the startup channel which is covered 3.3.3 B The neutron count rate on the startup channel is greater 2 by 3.3, Measuring Channel; units mW; interlock not credited are revised to instrument with the relationship between cps and % power provided in basis Delte Bounded by reactivity additiorn Deleted of pulsing 3.4.3 Table 2: Pulse rod interlocktl-Prevent inadvertent pulsing while in STEADY STATE MODE No change; safety basis -

NOTE [1]: The pulse rod interlock prevents air from being applied instrument gain set by pulse to the pulse rod unless the transient rod is fully inserted except, mode.

during pulse mode or square wave operations.

3.4.3 Table 2: CONTROL ROD (STANDARD) position interlock -

No change; safety basis - pulsed Prevent withdrawal of standard rods in the PULSE MODE-reactivity analysis Deleted Analysis used max pulse at the.

max available SS power level

Page 13of 39 Current Technical Specifications Supplemental Information, Table TS-1 Proposed Technical Specifications Analysis of Change 3.2.2, Reactor Safety System minimum safety channels Scram at <550°C Scram at <1.1 MW Scram at <2000 MW Scram on loss High Voltage Scram on loss of Magnet Current Scram on loss of timer reset Scram on demand 3.2.4, Instrument channels: Minimum of 2 operable fuel temperature channels 3.2.4, Instrument channels: 2 power level channels 3.2.4, Instrument rhannels: 1 pulse power channel 3.2.4, Instrument channels Minimum of 1 operable pulse energy measuring channel 3.3.1 Water Coolant Systems (a) Corrective action shall be taken or the reactor shut down if any of the following: The bulk pool water temperature exceeds 48°C 3.3.1 Water Coolant Systems (b) Corrective action shall be takený or the reactor shut down if any of the following: The water depth is less than 6.5 meters measured from the pool bottom to the pool water surface 3.3.1 Water Coolant Systems (c) Corrective action shall be taken or the reactor shut down if any of the following: The water conductivity exceeds 5.0 pmho/cm for the average value during measurement periods of one month LSSS:

A.

Power level SHALL NOT exceed 1100 kW (th) in STEADY STATE MODE of operation B. Instrumented elements in the B or C ring SHALL indicate less than 550°C 3.3.3 The MEASURING CHANNELS specified in TABLE 1 SHALL be OPERATING 3.3.4 - A.2 High voltage to reactor safety channel (power level) detector less than 80% of required operating value 3.4.3 A The SAFETY SYSTEM CHANNELS specified in TABLE 2 are OPERABLE Table 2:

Reactor power level - SCRAM Fuel temperature SCRAM Manual scram bar - SCRAM (1) Trip points for LSSS moved to LSSS (2)

HV requirement moved to Measuring Channels (3) Pulsing power deleted; no safety basis (4) Magnet current, no safety basis (fail safe)

(5) Loss of time reset coved by 3.4, Reactor Power Level operability (6) SCRAM on demand in 3.4 3.3.3 Table 1: Minimum of I operable fuel temperature channels No safety basis for 2 channels 3.3.3 Table 1: 2 reactor power level channels No change 3.3.3 Table 1: 1 pulse power level channel No change Deleted.

No safety basis 3.8.3 (A) Water temperature at the exit of the reactor pool SHALL Analysis performed for NOT exceed 110'F (48.9°C); 3.8.4 Actions: (A) 110°F/49°C 3.8.3 (C) Water level above the core SHALL be at least 6.5 m from No change bottom of the pool; 3.8.4 Actions: (C) 3.8.3 (B) Water conductivity SHALL be less than or equal to 5 Imho/cm averaged over 1 month, 3.8.4 Actions: (B)

No change

Page 14of 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change 3.3.1 Water Coolant Systems (d) Corrective action shall be taken or the reactor shut down if any of the following: 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.

3.3.1 (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 Water Coolant Systems Corrective action... (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.

3.3.2 Air Confinement Systems Corrective action... (b) The reactor room ventilation system shall have an automatic signal to isolate the area if air particulate radioactivity exceeds preset values.

3.3.2 Air Confinement Systems Corrective action... (c) An auxiliary air purge system to exhaust air from experiment systems shall have a high efficiency particulate filter.

3.3.2 Air Confinement Systems Corrective action... (d) Room ventilation shall require two air changes per hour or exhaust of pool areas by the auxiliary air purge system.

3.8.3 (D) The pressure difference between chilled water outlet from the pool heat exchanger and pool water inlet SHALL NOT be less than 7 kPa (1 psig); 3.8.4 Actions (D)

No change Deleted No safety basis (1) definition of CONFINEMENT ISOLATION and (2) 3.3.3 C The particulate continuous air monitor SHALL be operating and Essentially unchanged capable of initiating CONFINEMENT ISOLATION (1) definition of CONFINEMENT ISOLATION and (2) 3.3.3 C The particulate continuous air monitor SHALL be operating and Essentially unchanged capable of initiating CONFINEMENT ISOLATION Deleted Auxiliary air system HEPA filters are not required in analysis 5.3.3 (2) Reactor bay HVAC confinement ventilation system operation is designed to provide a minimum of 2 changes of This is a design specification, not reactor bay air per hour.

3.3.3 Radiation Monitoring Systems (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 piCi/cm3 with a two hour particulate accumulation.

Page 15of 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change 3.3.3 Radiation Monitoring Systems (a) 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.

3.3.3 Radiation Monitoring Systems (a) 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.

3.3.3 Radiation Monitoring Systems (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 3.3.3 Radiation Monitoring Systems (b) Alarm set point shall be equal to or less than a measurement concentration of 2 x 10-5 ICi/cm3 for a daily release.

3.3.3 Radiation Monitoring Systems (b) If the argon-41 monitor is not operable, operating the reactor with the auxiliary air purge system shall be limited to a period often days..

3.3.3 Radiation Monitoring Systems (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.

The reactor bay confinement system will enter CONFINEMENT ISOLATION if the particulate continuous air monitor is in-service and indicates greater than 10,000 cpm Isolation signal units are revised to the instrument reading, with the correlation to concentration in the basis (1) The likelihood of fuel

- Continuous particulate air radiation monitor is not OPERATING:

elem ilure oincien Restore MEASURING CHANNEL OR ENSURE reactor is shut down witheCA failure is IMMEDIATELY.

with CAM failure is OR ENSURE Argon 41 monitor radiation monitor is OPERATING sufficiently low enough that coupled with the capability IMMEDIATELY and restore MEASURING CHANNEL within 30 of the Ar-41 monitor, 30 working days.

days to effect repairs or replacement is satisfactory 1113.3.3, Table 1: Argon 41 effluent monitor13 NOTE[3]: When the Essentially unchanged auxiliary purge system is operating No safety basis; CAP-88 indicates Deleted effluent limits are met at much greater than 100 Ci annual discharge The likelihood of fuel element

3.3.4 Actions

If the Argon monitor is not OPERATING:

failure coincident with Ar-41 Restore MEASURING CHANNEL or ENSURE reactor is shutdown or monitor failure is sufficiently low ENSURE continuous air radiation monitor is OPERATING enough that coupled with the immediately and restore MEASURING CHANNEL within 30 capability of the particulate cam, working days.

30 days to effect repairs or replacement is satisfactory Alarm setpoint deleted.

Personnel exposure is controlled by the approved Radiation Protection Program, with specific requirements for monitoring high radiation areas

Page 16of 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change 3.3.3 Radiation Monitoring Systems (c) 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.

3.4.1 (a) A moveable experiment shall have a reactivity worth less than 1.00 dollar 3.4.1 (b) The reactivity worth of any single secured experiment shall be less than 2.50 dollars.

3.4.1 (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 (a) Experiments containing materials 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 "Handbook of Laboratory Safety" Tables of Chemical Information published by CRC Press.

3.4.2 (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.

3.4.2 (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.

3.3.3 Table 1: 1 pool area radiation monitor and one lower or middle level area monitor required for minimum measuring channel for reactor operation.

Essentially unchanged 3.6.3 (a) The reactivity worth of any individual MOVEABLE Essentially unchanged EXPERIMENT SHALL NOT exceed $1.00 (0.007 Ak/k) 3.6.3 (b) The reactivity worth of any individual SECURED unchanged EXPERIMENT SHALL NOT exceed $2.50 (0.0175 Ak/k) 3.6.3 (c) The total reactivity worth of all EXPERIMENTS shall not exceed $3.00 (0.021 Ak/k)

Essentially unchanged This is a design requirement for Not required experiments which would be identified in experiment review and approval This is a corrective action which Not required would be incorporated in reviews 5.1.3 (2), Use of explosive solid or liquid material with a National Fire Protection Association Reactivity (Stability) index of 2, 3, or 4 in the reactor pool or biological shielding SHALL NOT exceed the equivalent of 25 milligrams of TNT without prior NRC approval.

Moved to Design, Revised to bound *explosive" in a standard method

Page 17of 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change 3.4.2 (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.

3.4.2 (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 shalibe limited in activity such that if 100% of the gaseous activity or radioactive aerosols produced escaped to the reactor room or the atmosphere, the airborne concentration of radioactivity averaged over a year would not exceed the, occupational limits for maximum permissible concentration.

3.4.2 (f) 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.

4.1.1 Excess reactivity shal! be determined annually or after significant control rod or reactor core changes.

4.1.2 Shutdown margin shall be determined annually or after significant control rod or reactor core changes.

4.1.3 Transient Insertion 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.

4.1.3 Transient Insertion A comparison of pulse data shall be made.

with previous measurements at ýannua! intervals or each time the interval to the previous measurement exceeds the annual interval.

Each fueled experiment shall be limited such that the total inventory of (1) radioactive iodine isotopes 131 through 135 in the experiment is not greater than 9.32E5 uCi, and (2) radioactive strontium is not greater than 9.35E4 uCi.

Based on analysis Where the possibility exists that the failure of an EXPERIMENT (except fueled EXPERIMENTS) could release radioactive gases or aerosols to the reactor bay or atmosphere, the quantity and type Provides adequate time for of material shall be limited such that the airborne concentration evacuation of radioactivity is less than 1,000 times the Derived Air Concentration.

If effluents from an experimental facility exhaust through a filter installation designed for greater than 99% efficiency for 0.3 HEPA filters are rated for 0.3 micron particles, at least 10% of the aerosols produced will micron escape.

3.9, RETEST REQUIREMENTS, EXCESS REACTIVITY determination performed annually or r 3.9, RE R

E N

following insertion of experiments with measurable positive rqiresnevan ofeall reactivity maintenance and operations for effect on safety function 3.9, RETEST REQUIREMENTS, SHUTDOWN MARGIN determination performed annually.

requires evaluation of all maintenance and operations for effect on safety function 4.4.2 The CONTROL ROD (TRANSIENT) rod drive cylinder and the associated air supply system SHALL be inspected, cleaned, and No Change lubricated, as necessary. ANNUAL.

No safety basis Deleted

Page 18of 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change SURVIELLANCE REQUIREMENTS SURVEILLANCE The standard fuel elements SHALL be visually inspected for corrosi and mechanical damage, and measured for length and bend, 500 I of magnitude equal to or greater than a pulse insertio'n of S3.00 AND Following the exceeding of a limited safety system set point with potential for causing degradation 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.

Operating experience has demonstrated reliability of TRIGA fuel that justifies less frequent surveillance Approximately 1/4 of the core SHALL be visually inspected annuall corrosion and mechanical damage BIENNIAL 4.2.1 Control rod worths shall be determined annually or after significant control rod or reactor Core-changes 4.2.1 (a) Each control rod shall be inspected at biennial intervals by visual observation.

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

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

Complete full core inspection 4 not to exceed 5 years 3.9 requires verification that control rod worths are not

'significantly affected, at intervals.

Control Rod Reactivity Worth determination with a frequency of b na y.,.

related to other SRs; the need biennially for a complete determination is evaluated -equently with a full determination biennially 4.4.2 The control rods SHALL be visually inspected for cOrrosion N

and mechanical damage at intervals No change 4.4.2 CONTROL ROD (STANDARD) drop times SHALL be measured to have a drop time from the fully withdrawn position of less than In conjunction with Retest I sec.

Requirements, no change.

Deleted Reactivity insertion rate LCO removed

Page 19of 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change 4.2.2 The minimum safety interlocks shall be tested at semiannual intervals or after repair or modification.

4.4.2 CONTROL ROD (STANDARD) position interlock functional test SEMIANNUAL; Pulse rod interlock functional test SEMIANNUAL No change for required interlocks 4.2.3 The minimum safety channels shall be calibrated annually or after repair or modifications. A channei test shall be doneprior to each day's operation, after repair or modifications, or prior to each extended period of operation.

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 Instrurnent System: Specification(s); The minimum configuration of instrument channels shall be calibrated annually or after repair or moodification. Calibration of the power measuring channels shall be by the calorimetric method. A channel check and channel test of the fe, temperature instrument channels and power level instrureent channels shall be made prior to each day's operation or prior to each extended period of operation.

4.3.1 (a) The pool temperature channel shall have a channel calibration annually, channel check monthly andwill be monitored during reactor operation.

4.3.2 Reactor power level CHANNEL, CHANNEL TEST DAILY Calorimetric Calibration ANNUAL; Pool and Fuel temperature CHANNELs, CHANNEL TEST DAILY, CHANNEL CALIBRATION ANNUAL; 4.4.2, Pool level scram shall be functionally tested MONTHLY; 4.4.2 Manual scram SHALL be tested by releasing partially withdrawn CONTROL RODS (STANDARD) DAILY Pool level scram check is monthly based on reliability of channel; no other changes for required safety system channels; Channel test or functional test moved to individual channel specifications Calibrations of required measuring channels and channel tests are incorporated in 4.2.3; channel test for argon monitor, continuous air monitor, area monitors are changed to channel check Calibrations of required measuring channels are incorporated in 4.2.3 Calibrations of required measuring channels and channel tests are incorporated in 4.2.3 Calibrations of required measuring channels are incorporated in 4.2.3 Primary pool water temperature CHANNEL CALIBRATION annually Verify reactor pool water temperature channel operable daily Monthly channel check.

superseded by daily check

Page 20of 39 Current Technical Specifications Supplemental Information, Table TS-1 Proposed Technical Specifications 4.3.1 (b) The pool water depth channel shall have a channel calibration annually, channel check monthly and will be monitored during reactor operation.

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

4.3.1 (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.

4.3.1 (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.

Analysis of Change The minimum pool level is 6.5 m, well below the level range.

Minimum level is assured by the design of the vacuum breakers.

Termination of reactor operations on a loss of pool water is not credited above 6.5 e inlet line vacuum

m. Therefore any trip using the pool level instrument is adequate to assure the analysis is preserved. A monthly functional trip from the pool level channel will be incorporated in supplementary 4.8.2, Verify reactor pool water level above th breaker; DAILY information.

Annual calibration will be incorporated in supplementary 4.8.2; Measure reactor Pool water conductivity; WEEKLY at least informatin 30eday da,**...

information.

30 day every 30ay requirement assures monitoring during long.shutdown periods 4.8.2, CALIBRATE heat:exchanger differential preswsure canhel Essentially no change based on ANNUALLY;. CHANNEL CHECK heat exchanger differential pressure definition of DAILY and channel with loss of differential pressure DAILY Specifications 3.9/4.9 Not listed See previous item re pH and radioactivity

Page 21of 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change 4.3.2 (a) Annual examination of door seals and isolation dampers.

4.3.2 (b)Monthly functional test of air confinement isolation.

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

4.3.2 (d) Daily check of ventilatio.n system alignment for proper exhaust conditions prior to reiactor operation.

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

4.3.3 (b) Calibrate argon-41 airnmnitor at biennial intervals and check operability monthly.

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

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 bespecified as a part of the experiment approval.

4.5.2, CONFINEMENT ISOLATION damper inspection annually, removed door seal inspection as a TS issue Damper operation has demonstrated reliability since initial criticality that justifies annual inspection; accident analysis assumes large gap at approximate door frame clearance 4.5.2, CONFINEMENT ISOLATION functional test MONTHLY No change.

4.5.1, ENSURE adequate auxiliary air purge system valve Required to ensure auxiliary alignment: Prior to entering an operating mode with an EXPERIMENTAL FACILITY in use purge system function 4.5.2,ENSURE confinement HVAC operable, DAILY No change 4.3.2, Continuous Particulate Air Monitor Monthly check, Annual CHANNEL CHECK MONTHLY CHANNEL CALIBRATION ANNUAL calibration is adequate.

4.3.2, Argon monitor CHANNEL CHECK DAILY Typographical error should be CHANEL CECK AILYBiennial vice Semiannual.

CHANNEL CALIBRATION (Electronic) SEMIANNUALLY 4.3.2, Upper/Lower or middle level Area Radiation Monitor Area monitors are not used to CHANNEL CHECK WEEKLY measure personnel dose rates, CHANNEL CALIBRATION ANNUALLY therefore annual calibration 4.6.2, Measure and record experiment worth of the EXPERIMENT (where the absolute value of the estimated worth is greater than Specific criteria for the

$0.50): Initial insertion of a new experiment where absolute value surveillance of the estimated worth is greater than $0.50 4.6.2, Experiments SHALL be evaluated and approved prior to implementation: Prior to inserting a new experiment for purposes other than determination of reactivity worth Experiment approval is not surveillance.

Page 22of 39 Supplemental Information, Table TS-1 Current Technical Specifications Prc 5.1.1 Location; Specifications:

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 a designated room of a building constructed as a Nuclear Engineering Teaching Laboratory.

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

d. License areas of the facility for reactor operation shall consist of the room enclosing the reactor shield and pool structure, and the adjacent area for reactor control (room 1.104, corridor 3.200; and rooms 3.202, 3.204, and 3.208).

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

5.1.2 (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 5.1.2 (c) An air purge system should exhaust experiment air cavities and shall be filtered by high efficiency particulate absorption filters 5.1.2 (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 designed and fabricated. Alternate specifications may be approved by the Nuclear Reactor Committee. A system shall not be considered operable until after it is tested successfully.

)posed Technical Specifications Analysis of Change ANSI/ANS-15.1-2007, "This section should be kept to a minimum considered necessary to ensure that major alteration to safety related components or

• equipment are not made prior to safety reviews." None of the previous.ly identified material is subject to change without review independent of the specification in section 5.

Deleted 5.3.3 (2) The minimum free volume of the reactor room shall be approximately 4120 M3.

Essentially no change 5.3.3 (4) Reactor bay HVAC confinementý ventilation system" Esentially no change; the operation is designed to provide a minimum of 2 changes of iso!ation is moved into an LCO reactor bay air per hour.

Deleted No safety basis 5.3.3 (4) The reactor bay HVAC confinement ventilation system and the auxiliary purge system is capable of exhausting air Better description or other gases from the reactor room at a minimum of 60 ft.

above ground level.

Not listed.

This is part of the review process for design changes, requiring 10CFR50.59 review

Page 23of 39 Current Technicai Specifications Supplemental Information, Table TS-1 Proposed Technical Specifications 5.2.1 Natural Convection, Specification(s): The reactor core shall be cooled by natural convection flow of water.

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

a. Include stainless steel or aluminumclad and~may be followed by air or aluminum, or for a standard rod may befollowed.byfuel with stainless steel clad.

b. Contain borated graphite, B4C powder, or boron and its compounds in solid form 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.

5.4 Reactor Fuel Element Storage, Specification(s)::

a. All fuel elements shall be stored in a geometrical array where the effective multiplication is less than 0.8 for all conditions of moderation.

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

Analysis of Change Forced convention is a design change, requiring 10CFR50.59 review Not listed The high-hydride fuel element shall contain uranium-zirconium hydride, clad in 0.020 in. of 304 stainless steel. It shall contain a nominal 8.5 weight percent uranium which has a maximum enrichment of 20%. There shall be 1.55 to 1.80 hydrogen atoms to 1.0 zirconium atom.

Essentially no change Not Listed The definition of control rods to preserve the materials of construction; the required complement is that which meets required reactivity limits All fuel elements or fueled devices shall be in a safe, stable geometry; The keff of all fuel elements or fueled devices in storage is less than 0.9; The keff of fuel elements or fueled devices in an approved shipping container will meet the applicable Certificate of Compliance specifications for keff; Irradiated fuel elements or fueled devices will be stored in an array which will permit sufficient natural convection cooling by air or water such that the fuel element or fueled device will not exceed design values.

(1)

No change, (2) ANSI/ANS-15.1-2007 indicates keff 0.9 (3) Certificates of Compliance

. have specific requirements (4) No change.

Page 24of 39 Sur plemental Information, Table TS-1 posed Technical Specifications Current Technical Specifications Pro 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 4.5meters 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 pICi/cm3the gamma irradiator components shall be tested to locate and remove any leaking source.

6.1.1 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: (FIGURE) 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.

No previous specification Analysis of Change Not Listed The irradiator is removed, with no plans to resume or restore capabilities Rewritten in 6.1 Rewritten in Section 6i with partial incorporation in 4.6.2 6.1 (c) Operation of the reactorand activities associated with the reactor, control system, instrument system, radiation monitoring system, and engineered safety features will be the function of staff personnel with the appropriate training and certification'.

1"Selection and Training of Personnel for Research Reactors", ANSI/ANS -15.4 - 1970 (N380)

Page 25of 39 Current Technical Specifications P

6.1.3 Staffing

The minimum staffing when the reactor is not shutdown shall be:

a. A certified operator In the control room No previous specification

6.1.3 Staffing

The minimum staffing when the reactor is not shutdown shall be:

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

No previous specification Supplemental Information, Table TS-1

'roposed Technical Specifications 6.1 (c) Whenever the reactor is not secured, a (USNRC licensed)

Reactor Operator (or Senior Reactor Operator) who meets requirements of the Operator Requalification Program shall be at the reactor control console, and directly responsible for control manipulations; as indicated above, the Reactor Supervisor may be the Reactor Operator atfthe controls.

Only the Reactor Operator at the controls or personnel authorized by, and under direct supervision of, the Reactor Operator at the controls shall manipulate the controls.

Whenever the reactor is not secured, operation of equipment that has the potential to affect reactivity or power level shall be manipulated only with the knowledge and consent of the Reactor Operator at the controls. The Reactor Operator at the controls may authorize persons to manipulate reactivity controls who are training either as (1) a student enrolled in academic or industry course making use of the reactor, (2) to qualify for an operator license, or (3) in accordance the approved Reactor Operator requalification program.

Whenever the reactor is not secured, a second person (i.e., in addition to the reactor operator at the control console) capable of initiating the Reactor Emergency Plan will be. present in the NETLbuilding. Unexpected absence of this second person for greater than two hours will be acceptable if immediate action is taken to obtain a replacement. If the reactor supervisor is in the NETL building and not acting as the Reactor operator at the controls, the Reactor Supervisor may act as the second.person.

Staffing required for performing experiments with the reactor will be determined by a classification system specified for the experiments. Requirements will range from the presence of a certified operator for some routine experiments to the presence of 'a senior operator and the experimenter for other less routine experiments.

,nalysis of Change

Page 26of 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change

6.1.3 Staffing

The minimum staffing when the reactor is not shutdown shall be:

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 direction of a senior reactor operator shall be:

a.

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

b.

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

c.

Recovery from an unscheduled shutdown or significant power reduction.

d.

Initial startup and approach to power.

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:

6.1 (c)

Whenever the reactor is not secured, the reactor shall be (1) under the direction of or (2) directiy operated bya (USNRC licensed) Senior Operator, designated as Reactor Supervisor. The Supervisor may be on call if cognizant of reactor operations and capable of arriving at the facility within thirty minutes.

No change The Reactor Supervisor shall directly supervise any INITIAL STARTUP.

No change; definition OF INITIAL STARTUP ei;ccmpasses previous specification.

a. Management personnel.

b. Radiation safety personnel.

c. Other operations personnel.

Not listed Implementing procedures of the USNRC approved Emergency Plan provides contact information.

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

-15.4Property "ANSI code" (as page type) with input value "ANSI/ANS</br></br>-15.4" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process.. Qualification and requalification of licensed operators shall be subject to an approved NRC (Nuclear Regulatory Commission) program.

6.5 Operator Requalification:

An NRC approved UT TRIGA Requalification Plan is in place to maintain training and qualification of reactor operators and senior reactor operators.

License qualification by written and operating test, and license issuance or removal, are the responsibility of the U.S. Nuclear Regulatory Commission. No rights of the license may be assigned or otherwise transferred and the licensee is subject to and shall observe all rules, regulations and orders of the Commission.

Requalification training maintains the skills and knowledge of operators and senior operators during the period of the license.

Training also provides for the initial license qualification.

6.2 Review and Audit The review and audit process is the responsibility of the Reactor Oversight Committee (ROC).

Editorial changes 6.2, Review and Audit

Page 27of 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change 6.2.1, Composition and Qualifications:

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

person for audit functions.

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

established charter, including provisions for:

a.

Meeting frequency (at least once each six months).

a.

Meeting frequency (at least twice each year, with approximately 4-8 month frequency).

b.

Quorums (not less than one-half the membership where the

b.

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

the operating staff does not contribute a majority).

c.

Dissemination, review, and approval of minutes.

c.

Dissemination, review, and approval of minutes.

d s

fsbrus

d.

Use of subgroups.

d. -'Use of subgroups,..'

Page 28of 39 Current Technical Specifications Supplemental Information, Table TS-1 Proposed Technical Specifications Analysis of Change 6.2.3 Review Function Review Function The review function shall include facility operations related to reactor and radiological safety. The following items shall be reviewed:

a.

Determinations that proposed changes in equipment, systems, tests, experiments, or procedures do not involve an unreviewed safety question.

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.

e.

Violations of technical specifications or license.

f.

Operating abnormalities or violations of procedures having safety significance.

g.

Other reportable occurrences.

The responsibilities of the Reactor Safeguards Committee to shall include but are not limited to review of the following:

a.

All new procedures (and major revisions of procedures) with safety significance

b.

Proposed changes or modifications to reactor facility equipment, or systems having safety significance

c.

Proposed new (or revised) experiments, or classes of experiments, that could affect reactivity or result inothe release of radioactivity

d.

Determination of whether items a) throough c) involve.

unreviewed safety questions, chang*:s i t

fac.ility as designed, or changes in Technical Specif'r,4mai-,s.

e.

Violations of Technical Specifications or the; facility operating licensee

f.

Violations of internal procedures or instr.ction 1i-,ving, safety significance

g.

Reportable occurrences

h.

Audit repot ts

h.

Audit reports.

Minor changes to procedures and experiments that do not change the intent and do not significantly increase the potential consequences may be accomplished following review and approval by a senior reactor operator and independently by one of the Reactor Supervisor, Associate Director or Director. These changes should be reviewed at the next scheduled meeting of the Reactor Oversight Committee.

Page 29of 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change Audit Function 6.2.4 Audit Function: The audit function shall be a selected The audit function shall be a selected examination of operating records, logs, or other documents. Audits will be by a Reactor examination of operating records, logs, or other documents. An Oersight o

r o rhby an individual a

i by Oversight Committee member or by an individual appointed by audit will be by a person not directly responsible for the records, the committee to perform the audit. The audit should be by any and may include discussions with cognizant personnel or individual not directly responsible for the records and may observation of operations. The following'items shall be audited and include discussions with cognizant personnel or observation of a report made within 3 months to the Director and Nuclear Reactor operations. The following items shall be audited and a report made within 3 months to the Director and Reactor Committee:

Committee:

a.

Conformance of facility operations with license and-

a.

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

specifications at least once each calendar.year.

b.

Results of actions to correct deficiencies that may occur

b.

Results of actions to correct deficiencies that may occur in in reactor facility equipment, structures, systems, or reactor facility equipment, structures;systems: or methods of

-methods of operation that affect safety at least once per operation that affect safety at least once per calendar year.,

calendar year.

c.

Function of the retraining and requalification program for F

o

c.

Function of the retraining and requalification program reactor operators at least once every Othercalendaryear.

for reactor operators at least once every other calendar

d.

The reactor facility emergency plan and physical security year.

plan, and implementing procedures at least once every other

d.

Thereactor facility emergency plan and physical security year.

plan, and implementing procedures at least once every other yea*r.

Page 30of 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change 6.3 Operating Procedures: Written operating procedures shall be prepared, reviewed and approved by the Director or a supervisory Senior Reactor Operator and the Nuclear Reactor 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 an effect on reactor safety.

d.

Surveillance calibrations and tests required by the technical.

specifications or those that could have an effect on reactor safety.

e.

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

f.

Personnel radiation protection, consistent with applicable regulations 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 Nuclear Reactor Committee. Minor modifications to the original procedures which do not change the original intent may be made by a senior reactor operator but the 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.

6.3 Procedures Written procedures shall govern many of the activities associated with reactor operation. Activities subject to written procedures will include:

a.

Startup, operation, and shutdown of the reactor

b.

Fuel loading, unloading, and movement within the reactor.

c.

Control rod removal or replacement.

d.

Routine maintenance, testing, and calibration of control rod drives and other systems that could have an effect on reactor safety.

e.

Administrative controls for operations, maintenance, conduct of experiments, and conduct of tours of the Reactor Facility.

f.

implementing procedures for the Emergency Plan or Physical Security Plan.

Control rod removal or replacement added Minor changes to procedures and experiments that do not change the intent and do not significantly increase the potential consequences may be accomplished following review and approval by a senior reactor operator and independently by one of the Reactor Supervisor, Associate Director or Director. These changes should be reviewed at the next scheduled meeting of the Reactor Oversight Committee.

Substantive changes addressed explicitly; Associate Director added to list of positions that can independently review minor changes

Page 31of 39 Current Technical Specifications Supplemental Information, Table TS-1 Proposed Technical Specifications Written procedures shall also govern:

a.

Personnel radiation protection, in accordance with the Radiation Protection Program as indicated in Chapter 11

b.

Administrative controls for operations and maintenance

c.

Administrative controls for the conduct of irradiations and experiments that could affect core safety or reactivity A master Procedure Control procedure specifies the process for

creating, changing,

editing, and distributing procedures.

Preparation of the procedures and minor modifications of the procedures will be by certified operators. Substantive changes or major modifications to procedures, and new prepared procedures will be submitted to the Reactor Oversight Committee for review and approval. Temporary deviations from the procedures may be made by the reactor supervisor or

• designated senior operator provided changes of substance are reported for review and approval.

,nalysis of Change Split from "Operating Procedures" for emphasis Proposed experiments will be submitted to the reactor oversight committee for review and approval of the experiment and its safety analysis2, as indicated in Chapter 10. Substantive changes to approved experiments will require re-approval while insignificant changes that do not alter experiment safety may be approved by a senior operator and independently one of the following, Reactor Supervisor, Associate Director, or Director.

Experiments will be approved first as proposed experiments for one time application, and subsequently, as approved experiments for repeated applications following a review of the results and experience of the initial experiment implementation.

Associate Director added as independent reviewer 2 ANSI/ANS 15.6, op. cit.

Page 32of 39 Current Technical Specifications Pr(

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 shail 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 pplemental Information, Table TS-1

• posed Technical Specifications Ar Review of Proposals for Experiments a)

All proposals for new experiments involving the reactor shall be reviewed with respect to safety in accordance with the procedures in (b). below and on the basis of criteria in (c) below.

b)

Procedures:

1.

Proposed reactor operations by an experimenter are reviewed by the Reactor Supervisor, who may determine that the operation is described by a previously approved EXPERIMENT or procedure.

If the Reactor Supervisor determines that the proposed operation has not been approved by the Reactor Oversight Committee, the experimenter shall describe the proposed EXPERIMENT in written form in sufficient detail for consideration of safety.

aspects.

If potentially hazardous operations are involved, proposed procedures and safety measures including protective and monitoring equipment shall be described.

2.

The scope of the EXPERIMENT and the procedures and safety measures as. described in the approved proposal, Including any amendments or conditions added by those reviewing and approving it, shall be binding on-

-He experimenter and the OPERATING personnel.

Minor deviations shall be allowed only in the manner described in Section 6 above. Recorded affirmative votes on proposed new or revised experiments or procedures must indicated that the Committee determines that the proposed actions do not involve changes in the facility as designed, changes in Technical Specifications, changes that under the guidance of 10 CFR 50.59 require prior approval of the NRC, and could be taken without endangering the health and safety of workers or the public or constituting a significant hazard to the integrity of the reactor core.

nalysis of Change Rewritten to reflect current practice

Page 33of 39 Current Technical Specifications Supplemental Information, Table TS-1 Proposed.Technical Specifications A

3.

Transmission to the Reactor Supervisor for scheduling.

c)

Criteria that shall be met before approval can be granted shall include:

1. The EXPERIMENT must meet the applicable Limiting Conditions for Operation and Design Description specifications. '

2.: It must not involve violation of any condition of the facility license or of Federal, State' University, or Facility regulations and procedures.

3.

The conduct of tests or experiments not described in the safety analysis report (as updated) must be evaluated in accordance with 10 CFR 50.59 to determine if the test or experiment can be accomplished without obtaining prior NRC approval via license amendment pursuant to 10 CFR Sec. 50.90.

4.

In thesafety review the basic criterion is that there shall be no hazard to the reactor, personnel or public. The review SHALL determine that there is reasonable assurance that the experiment can be performed with no significant risk to the safety of the reactor, personnel or the public.

nalysis of Change

Page 34of 39 Current Technical Specifications Supplemental Information, Table TS-1 Proposed Technical Specifications Analysis of Change 6.5.1 Action to be Taken in Case of a Safety Limit Violation In the event of a safety limit violation, the following action shall be taken:

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

b. The safety limit violation shall be promptly reported to the Director of the facility or a designated alternate.

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 Nuclear Reactor 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 Nuclear Reactor Committee at the next regularly scheduled meeting.

6.8 Action to be Taken in the Event that a Safety Limit is Exceeded In the event that a Safety Limit is not met,

a.

The reactor shall be shutdown and secured.

b.

The Reactor Supervisor, Associate Director, and Director shall be notified

c.

The safety limit violation shall be reported to the Nuclear Regulatory Commission within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone, confirmed via written statement by email, fax or telegraph

d.

A safety limit violation report shall be prepared within i4 days of the event to describe:

1.

Applicable circumstances leading to the violation including (where known) cause and contributing iactiors

2.

Effect of the violation on reactor facility components, systems, and structures

3.

Effect of the violation on the health aiic saeq of the' personnel and thepublic

4.

Corrective action taken to prevent recurrence

e.

The Reactor Oversight Committee shall review the report and any follow-up reports

f.

The report and any follow-up reports shall be submitted to the Nuclear Regulatory Commission.

g.

Operations shall not resume until the USNRCupproves resumption.

No significant thange b)

In the event of a reportable occurrence, as defined in the Technical Specifications, and in addition to the reporting requirements,

1.

The Reactor Supervisor, the Associate Directcr and the Director shall be notified

2.

If a reactor shutdown is required, resumption.of normal operations shall be authorized by the Associate Director or Director

3.

The event shall be reviewed by the Reactor Oversight Committee during a normally scheduled meeting

Page 35of 39 Supplemental Information, Table TS-2 Current Technical Specifications Proposed Technical Specifications Analysis of Change 6.6.2 Special Reports A written report within 30 days to the NRC of:

A.

Permanent changes in the facility organization involving Level I or Level 2 personnel.

B.

Significant changes in transient or accident analysisas.

described in the Safety Analysis Report.

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 anyof the.

following:

a. Violation of fuel element temperature safety limit.

b. Release of radioactivity above allowable limits..

c. Other reportable occurrences.

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.(N6te: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 specifiedor req~uired perform their intended reactor safety function.)

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

6.11 There shall be a written report within 30 days of:

a.

Permanent changes in the facility organization involving Director or Supervisor.

b.

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

6.11 Other or Special Reports There shall be a report not later than the following working day by telephone. and confirmed in writing by facsimile or similar

. conveyance of any reportable occurrence identified in 6.9.

There shall be a written report describing the circumstances of any. reportable., occurrence identified in 6.9 within 14 days of

, occurrence.

6.9 a) A reportable occurrence is any of the following conditions:

sý

1.

Any actual safety system setting less conservative than specified in Section 2.2, Limiting Safety System Settings;

Page 36of 39 Current Technical Specifications

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

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

Supplemental Information, Table TS-1 Proposed Technical Specifications

2.

VIOLATION OF SL, LSSS OR LCO; NOTES Violation of an LSSS or LCO occurs through failure to comply with an "Action" statement when "Specification" is nol met; failure to comply with the "Specification" is not by itself a violation.

Surveillance Requirements must be met for all equipment/componehts/conditions to be considered operable.

Failure to perform a surveillance within the required tirMIF interval or failure of a surveillance test shall result in the

/component/condition being inoperable Analysis of Change or ts Incidents or conditions that prevented or cou!d have oremte*

the performance of the intended safety. funct'ors of an engineered safety feature or the REACTOR SAFETY SYSTEM;

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.

An uncontrolled or unanticipated change in reactivity gyreater than $1.00; Release of fission products from the fuel that cause airberne.

contamination levels in the reactor bay to exceed 10CFR20 limits for releases to unrestricted areas; An observed inadequacy in the implementation of either administrative or procedural controls, such that the inadequacy has caused the existence or development of an unsafe condition in connection with the operation of the reactor; 6.11 Routine annual reports covering the activities of the reactor facility during the previous calendar year shall be submitted to licensing authorities within three months following the end of each prescribed year. Each annual operating report shall include the following information:

Page 37of 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change

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.

d.

Tabulation of major changes in the reactor facility and-procedures, and tabulation of new tests or experiments, or both, that are significantly different fromthose, 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 shfall 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. 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.

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.

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 new or unanalyzed safety questions were identified.

e.

A summary of the nature and amount of radioactive

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

f.

A summarized result of environmental surveys performed outside the facility.

g.

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

Page 38of 39 Su pplemental Information, Table TS-1 oposed Technical Specifications Current Technical Specifications Pr 6.6.2.3 A written report within 90 days after the completion of startup tests or 9 months after initial criticality, whichever is earlier, of the startup test program, to the NRC of:

Characteristics of the reactor such as critical mass, excess reactivity, power calibration, control rod calibrations, shutdown margin and experiment facility worths, describing the measured values of the operating conditions including:

a. Total control reactivity worth and reactivity of the rod of highest reactivity worth.

b. Minimum shutdown margin of the reactor both at ambient and operating temperatures.

c. An evaluation of facility performance to date in comparison with.

design conditions and measured operating characteristics, and a reassessment of the safety analysis when measurements indicate that there may be substantial variance from prior analysis submitted with the license application.

Analysis of Change Deleted Does not apply 6.7 RECORDS 1.3 Plant Operating Records: Records of the following activities shall be maintained and retained for the periods specified below 3. The records may be in the form of logs, data sheets, electronic files, or other suitable forms. The required information may be*contained in single or multiple records, or a combination thereof.

' "Records and Reports for Research Reactors", ANSI/ANS - 15.3-1974 (N399).

Page 39of 39 Supplemental Information, Table TS-1 Current Technical Specifications Proposed Technical Specifications Analysis of Change 6.7.1 Lifetime of the Facility 6.7.2 Five Years or the Life of the Component 6.7.3 One Licensing Cycle CONT.

Lifetime Records : Lifetime records are records to be retained for the lifetime of the reactor facility. (Note: Applicable annual reports, if they contain all of the required information, may be used as records in this section.)

a.

Gaseous and liquid radioactive effluents released to the environs.

b.

Offsite environmental monitoring surveys required by Technical Specifications.

c.

Events that impact or effect decommissioning of the facility

d.

Radiation exposure for all personnel monitored.

1.3

e.

Updated drawings of the reactor facility CONT.

Five Year Period: Records to be retained for a period of at least five years or for the life of the component involved whichever is shorter.

a.

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

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.

One Training Cycle Training records to be retained for at least one license cycle are the requalification records of licensed operations personnel.

Records of the most recent complete cycle shall be maintained at all times the individual is employed.

Incorporated in specifications Appendices