ML20138C614

Entire Revised TSs for Triga Mark I Reactor

ML20138C614
Person / Time
Site:	General Atomics
Issue date:	04/25/1997
From:	GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
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Shared Package
ML20138C595	List: ML20138C592 ML20138C614
References
NUDOCS 9704300152
Download: ML20138C614 (25)

Text

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1 TRIGA Reactors Facility l

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TECHNICAL SPECIFICATIONS l

TRIGA MARK I REACTOR i

l Facility License No. R-38 l

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9704300152 970425 PDR ADOCK 05000089 PDR, P

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. . t Technical Specifications - TRIGA Mark I . Amendment No. 34 '

i TABLE OF CONTENTS Page No. .

1.0 De fi n i t i on s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2.0 Site.................................................... 5

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3.0 Re ac tor Poo l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5  ;

4.0 Reactor Core ................................. .......... 6 5.0- Control and Safety Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 -

5.1 Control Systems ...................................... 7  ;

~ 5.2 Safety Systems ....................................... 7

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5.3 Maintenance on Control and Safety Systems . . . . . . . . . . . . . . . . 8 6.0 Fuel S torage . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9

' 7.0 ' Reactor Operations ....................................... 9 l t

8.0 Ex peri me nts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 8.1 Experiment Approval Procedures . . . . . . . . . . . . . . . . . . . . . . . . . 10 8.2 Experimental Limitations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 9.0 Administrative Controls . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 .

9.1 Organization . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 9.2 Review Committee . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16

9. 3 Wri t te n Proced u res . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 9.4 Action to be Taken in the Event of a Reportable Occurrence ... 18 l 9.5 Plant Operating Records . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 9.6 Reporting Requirements . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 Table I: Minimum Reactor Safety System Scrams . . . . . . . . . . . . . . . . . . . . . 22 +

Table II: Minimum Interlocks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 22 s e

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4 Technical Specifications TRIGA Mark i Amendment No. 34 APPENDIX A

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LICENSE NO. R-38 TEC11NICAL SPECIFICATIONS FOR 4

Tile TORREY PINES TRIGA MARK I REACTOR DATE: JANUARY 21,1972 l.0 DEFINITIONS 1.1 Reactor Shutdown Reactor shutdown shall mean that the reactor is subcritical at all times by at least one dollar of reactivity.

1.2 Reactor Secured .

The reactor is secured when all thefollowing conditions are satisfied:

- (a) The reactoris shut down, and (b) no work is in progress involving handling offuel, experiments or reactor core related maintenance operations.

1.3 Reactor Operation e

i Reactor operation is any condition wherein the reactor is not shutdown. i 1.4 Standard Control Rod A standard control rod is a control rod having rack and pinion electric motor drive 4

and scram capabilities. It may have a fueled follower section.

1.5 Transient Control Rod

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A transient control rod is any control rod operated pneumatically and with scram capabilities. It may have a fueled or non-fueled follower section and may also be adjusted with electric motor drive.

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Technical Specifications - TRIGA Mark i Amendment No. 34 1.6 Operable A :ystem or device shall be considered operab!c when it is capable of performing its intended functions in a normal mant.er.

1.7 Cold Critical The reactor is in the cold critical condition when it is critical with the fuel and bulk water temperatures both below 500C.

1.8 Experiment An experiment is (a) any device or material which is exposed to significant radiation from the reactor and is not a normal part of the reactor, or (b) any operation designed to measure reactor characteristics. (Normal control rod calibrations are not considered experiments.)

a. Routine Experiments. Routine experiments are those which have been previously tested in the course of the reactor program.

b. Modified Routine Experiments. Modified routine experiments are those which have not previously been performed but are similar to routine experiments in ,

that the hazards are neither greater nor significantly different than those for the i corresponding routine experiment.

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c. Special Experiments. Special experiments are those which are not routine nor modified routine experiments. i 1.9 Experimental Facilities Experimental facilities are facilities used to perforrn experiments and include the beam ports, thermal columns, void tanks, pneumatic transfer systems, in-core and out-of-core furnaces, out-of-core radiation racks, and the in-core facilities (including single-element positions, three-element positions, and flux measuring holes in the upper grid plate between the fuel elements).

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Technical Specifications TRIGA Mark I ' Amendment No. 34 i

1.10 Abnormal Occurrence An abnormal occurrence is any of the following which occurs during reactor possession:

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a. delete;. .

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b. delete;

c. delete;

d. delete;  :

\. c. An observed inadequacy in the implementation ofeither administrative or

! procedural controls, such that the inadequacy could have caused the existence or development of a condition which could result in possession of the reactor -

outside the specified safety limits; and i j f. Release of fission products from a fuel element. I l

1.11 Reactor Safety Systems )

Reactor safety systems are those systems, including their associated input circuits, which are designed to initiate a reactor scram for the primary purpose of protecting

. the reactor or to provide information which requires manual protective action to be initiated.

I 1.12 Experiment Safety Systems Experiment safety systems are those systems, including their associated input j circuits, wh!ch are designed to initiate a scram for the primary purpose of protecting

.l an experiment or to provide information which requires manual protective action to  ;

be initiated.  !

1.13 Standard Thermocouple A standard thermocouple is a sheathed chromel-alumel or equivalent thermocouple 4

embedded in the fuel near the horizontal center plane of the fuel eternent at a point

[ approximately 0.3 inch from the center of the fuel body, i

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e Technical Specifications - TRIGA Mark i Amendment No. 34 1.14 Measured Value ,

l The measured value is the magnitude of that variable as it appears on the output of a measuring channel.

1.15 Measuring Channel l l

A measuring channel is the combination of sensor, interconnecting cables or lines, amplifiers, and output device which is connected for the purpose of measuring the value of a variable.

1.16 Channel Calibration A channel calibration consists of comparing a measured value from the measuring channel with a corresponding known value of the parameter so that the measuring channel output can be adjusted to respond, with acceptable accuracy, to known values of the measured variable.

1.17 Standard TRIGA Core A standard TRIGA core is an arrangement in water solely of standard TRIGA fuel which is an alloy of uranium zirconium hydride contained in a metal clad.

2.0 SITE A minimum radius of 120 feet from the approximate center of the TRIGA Reactor Facility building shall define the exclusion area.

3.0 REACTOR POOL 3.1 The reactor core shall be cooled by natural convective water flow.

3.2 During reactor operation, the minimum level of the pool water shall be at least 14 feet above the top grid plate.

3.3 The pool water outlet pipe shall not extend more than 8 feet below the top of the reactor 41 when fini is in the core.

3.4 The pool water shall be sampled for conductivity at least weekly. The 4

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+ i Technical Specifications - TRIGA Mark i Amendment No. 34 >

conductivity of the coolant shall not exceed 5 micro-mhos per centimeter averaged over any one calendar month.

3.5 The reactor shall not be operated while the bulk pool temperature exceeds 650C.

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ie Technical Specifications - TRIGA Mark i Amendment No. 34 4.0 REACTOR CORE 4.1 The core shall be an assembly of standard uranium zirconium hydride fuel elements placed in light water except for adjacent or nonadjacent positions occupied by startup sources, vertical thimbles, voids, control rods, in-core experiments, and rabbit facilities.

4.2 Standard fuel elements shall have the following characteristics:

- a) Maximum uranium content in unirradiated fuel 9.0 wt %

b) Maximum uranium enrichment in unirradiated fuel 20 %

c) Ilydrogen to zirconium ratio 0.9 to 1.5411 atoms to 1.0 Zr (in the ZrIIn) atom (Iow hydride) 1.55 to 1.81-1 atoms to 1.0 Zr atom (high hydride) d) Cladding materials and minimum 0.020 inch 304 or 304L )

thickness stainless steel, Incoloy 800, i 1-lastelloy X, or 0.030 inch ,

aluminum or Zircaloy )

4.3 Any burnable poison used shall be an integral part of the as manufactured fuel element. A humable poison is defined as a material used for the specific purpose of compensating for fuel burn-up and/or other long-term reactivity adjustments.

4.4 Fuel Element Inspection.

a. delete

b. delete

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Technical Specifications - TRIGA Mark i Amendment No. 34 5.0 CONTROL AND SAFETY SYSTEMS 5.1 Control Systems 5.1.1 The poison section of the control rods shall contain borated graphite or stainless steel, B4 C powder or boron or its compounds in solid form, cadmium, or the rare earth poisons in solid form clad with the materials ;

authorized for fuel-element cladding. The control rods may contain flux '

traps and may be equipped with fuel or non-fuel followers.

5.1.2 The number and configuration offuel elements and control rods in the reactor shall be such as to maintain the reactor shut down by at least one dollar of reactivity at all times, even if all the control rods were removed.

delete-5.1.3 5.1.4 delete l

5.l.5 delete 5.2 Safety Systems 5.2.1 The reactor safety systems and the associated instruments necessary to provide the scrams listed in Table I shall be operable during reactor operation.

5.2.2 During reactor operation, the applicable interlocks shown in Table 11 shall be operable.

5.2.3 Radiation monitoring systems shall be operable asfollows:

a. An area radiation monitoring system capable of activating the evacuation alarm.

b When the reactor is not secured, a continuous monitoring system for airborne activity having a readout and audible alarm which can be heard in the reactor and control rooms.

c. delete These systems shall be calibrated annually and their setpoints verified 7

. Technical Specifications - TRIGA Mark i Amendment No. 34 monthly. For periods of time for maintenance or repair to the above systems, or during periods of otherforced outages, the intent of this specification shall be satisfied if the installed system (s) is replaced with appropriate alternate or portable radiation monitoring system (s).

i 5.2.4 The reactor safety systems plus a startup channel shall be verified to be operable at least once each day the reactor is operated, unless the operation extends continuously beyond one day, in which case the operability of the reactor safety system need only be verified prior to the extended operation. -

i 5.2.5 delete 5.3 Following maintenance or modification of the control or reactor safety systems, the affected system shall be verified to be operable before commencing a reactor operation.

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Technical Specifications TRIGA Mark 1 Amendment No. 34 6.0 FUEL STORAGE 6.1 All fuel elements or fueled devices shall be stored in a safe geometry (ke rr less than 0.8 under all conditions of moderation).

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

6.3 Not more than 19 standard fuel elements or equivalent shall be stored in any one storage well.

6.4 Fuel handling tools or devices shall be stored in a secure manner such that their use can be limited to authorized movements offuel.

7.0 REACTOR OPERATIONS 7.1 The operating power level shall not be intentionally raised above 250 kW except for pulsing operation.

7.2 The maximum available excess reactivity (cold with experiments, if any, in place) shall be:

a. $5.00 during steady-state operations, or

b. $3.25 during transient operations. l 7.3 The maximum reactivity insertion during transient operations shall be $3.00.

7.4 Maximum fuel temperature:

a. The maximum fuel temperature as measured by a standard thermocouple shall be 8000C for standard high hydride fuel elements.

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b. The maximum allowable fuel temperature shall be 5300C for standard low j hydride fuel elements or aluminum-clad elements. j 7.5 The maximum reactivity worth of any transient control rod shall be $3.00.

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Technical Specifications - TRIGA Mark l Amendment No. 34 8.0 EXPERIMENTS 8.1 Experiment Approval Procedures 8.1.1 Routine experiments may be performed at the discretion of the Physicist-in Charge or his designated alternate, without the necessity of any further review or approval.

8.1.2 Prior to performing any reactor experiment which is not a routine experiment, the proposed experiment shall be evaluated by a person or persons appointed by the Physicist-in-Charge to be responsible for reactor safety. He shall consider the experiment in terms ofits effect on reactor operation and the possibility and consequences ofits failures, including, where significant, consideration of chemical reactions, physical integrity, design life, proper cooling, interaction with core components, and reactivity effects.

8.1.3 Modified routine experiments may be performed at the discretion of the Physicist-in-Charge without the necessity of any further review or approval provided that the evaluation performed in accordance with Section 8.1.2 results in a determination thtt the hazards associated with the modified routine experiments are nehher greater nor significantly different than those involved with the corresponding routine experiment which shall be referenced.

8.1.4 No special experiment shall be performed until the proposed experiment or type of experiment has been reviewed and approved by the Criticality Safeguards Committee.

8.1.5 Favorable evaluation of the protective measures provided for an experiment shall conclude that failure of the experiment will not lead directly to a failure of a fuel element or other experiments or interfere with movement of a control rod.

8.2 Experimental Limitations 8.2.1 The following limitations on reactivity shall apply to all experiments:

a. The reactivity worth of any individual experiment shall not exceed

$3.00.

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Technical Specifications - TRIGA Mark i Amendment No. 34

b. The total absolute reactivity worth of a combination of experiments shall not exceed $4.00. This includes the potential reactivity which might result from experiment malfunction, experiment flooding or voiding, removal or insertion of experiments.

c. Experiments having reactivity worths greater than $1.00 shall be securely located or fastened to prevent inadvertent reactivity changes during reactor operations.

8.2.2 Explosive materials such as gunpowder, dynamite, TNT, nitroglycerin, or PETN may be irradiated in the reactor core or reactor pool subject to the following conditions:

a. The explosive materials shall be limited to quantities of 25 mg or less; and

b. 1. The pressure produced in the experiment container upon detonation of the explosive shall be less than the design ,

pressure of the container, or

2. An out-of-core test involving the same quantity of material to be irradiated indicated that the integrity of the container has been maintained (i.e., with the containment provided no damage to the reactor or its components shall occur upon detonation of the explosive).

8.2.3 Experiment materials, except fuel materials, which would off-gas, sublime, volatilize or produce aerosols under normal operating conditions of the experiment or reactor, credible accident conditions in the reactor, or possible accident conditions in the experiment, shall be limited in activity so that failure of the experiment will not exceed the appropriate limits of 10 CFR 20. In evaluating such experiments, the following assumptions shall be used:

a. If the possibility exists that airborne concentrations of radioactive gases or acrosols may be released to the reactor room,100 percent of the gases or aerosols will escape;

b. If the effluent exhausts through a filter installation designed for greater than 99 percent efficiency for 0.3 micron particles, at least 10 percent of the particulates will escape; and i1

Technical Specifications - TRIGA Mark i Amendment No. 34

c. For a material whose boiling pointy is above 6010C and where vapors formed by boiling this material could escape only through a column of water above the core, at least 10 percent of these vapors will escape.

8.2.4 Fueled experiments which are not covered elsewhere in the Technical Specifications shall be controlled such that the total inventory of iodine isotopes 131 through 135 in each experiment is no greater than 1.5 curies. y 8.2.5 One or more in-core electrically heated furnaces may be used in conjunction with the irradiation of materials with the following limitations:

a. Experiments involving fissionable material:

1. The total fissions produced in all in-core furnaces in use during steady-state or transient operations shall not exceed 2 x 1016 for materials containing fissionable material subjected to a burn-up ofless than 1 percent, or 2 x 10 15 fissions for materials containing fissionable materials subjected to a burn-up of 1 percent or greater.

2. The helium purge from each furnace shall:

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i. Vent through a liquid nitrogen-cooled charcoal trap, and l ii. Ilave a rate within the range of approximately 0.2 and 10.0 liters per minute.

3. The furnace temperature shall not exceed 20000C.

4. Experiment safety systems to provide the following scrams shall be operable:

i. Internal furnace pressure less than i1 psig, and ii. Set points 10 percent above and below the operating current setting for the furnace,

b. Experiments involving solely nonfissionable material:

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Technical Specifications - TRIGA Mark i Amendment No. 34

1. Experiment safety systems to provide the following scrams shall be operable:

1. Internal furnace pressure less than 1i psig, and j i

ii. Set points 10 percent above and below the operating l current setting for the furnace, l

8.2.6 The in-core assemblies from one or more pneumatic transfer systems may be used in conjunction with the irradiation of materials. These  !

units may remain in the core during other reactor operation. The pneumatic transfer systems may be actuated by underpressure or  !

overpressure of gas propellant. Any in-core pneumatic assembly l tenninus may be shielded with absorber of thermal neutrons provided the neutron absorber is an integral part of the assembly construction.

8.2.7 Specimens of U-235 dispersed in graphite or in the form of coated carbide particles may be irradiated under conditions which lead to a totalinventory ofiodine isotopes 131-135 in excess of 5 curies but no greater than 16 curies per specimen, provided that the specimens are doubly encapsulated or, if singly encapsulated, placed in a sealed sample container. The capsules shall be located at least 16 feet below the pool surface during irradiation.

8.2.8 If an experiment fails and releases material which in thejudgment of the Physicist-in-Charge or his designated alternate, could damage the reactor fuel or structure by corrosion or other means, 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 Criticality Safeguards Committee and determined to be satisfactory before reactor operation is resumed.

8.2.9 Any additions, modifications, or maintenance to the core and its associated support structure, the pool or its penetrations, the pool coolant system, 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 or to the specifications approved by the Criticality Safeguards Committee. A system shall not be considered operable until after it is successfully tested.

8.2.10 Explosive materials may be radiographed using neutron beams from the ,

reactor subject to the following conditions: i 13 7

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Technical Specifications - TRIGA Mark i Amendment No. 34

a. The radiography of explosives present in the beam at any one time shall be limited to devices containing in aggregate no more than 1 pound equivalent TNT with no individual device containing more than 0.2 pound (91 gram) equivalent TNT encased in a metal case.

b. Explosive devices (such as cartridges or shaped charges) whose discharge could produce a thrust in a definite direction shall be positioned so as to be aimed away from the reactor and its components.

c. At any one time there shall be no more than one pound equivalent i

TNT in the reactor room housing the reactor. This one pound shall be an aggregate composed of items none of which nall exceed 91 grams. In the event of temporary interruptioa of NR operation, the explosives shall not remain in the reactor room for more than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4 d. The maximum quantity of explosive material that may be stored outside the reactor building in a storage magazine or magazines i for radiography with the Mark I reactor is 100 pounds of propellent (low explosive). Type 2 magazine (s) shall be used for Class B or Class C explosives. The new high energy propellants may be detonable and should be handled as high explosives.

c. All vertical neutron radiography beam ports shall be sealed to prevent explosive devices from falling inside to the bottom of the port. In addition, appropriate regions at the top of the reactor tank shall be covered to prevent explosive devices from falling through the tank water to the reactor core region.

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f. Blast shields shall be mounted on the bridge or other support structure to protect the vital control rod components and reactor power monitor detector channels for the radiography of explosives in amounts greater than 10 g.

g. The radiation beam stop shall be positioned over the objects being radiographed.

h. Controls governing the handling of explosives shall be in accordance with the following general requirements:

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. Technical Specifications eTRIGA Mark i Amendment No. 34 1-J

- 1. Explosive devices shall be handled in accordance with )

. Chapter 2 of Ref.1. l q

2. Since exposure to excessive heat or high energy radiation may increase the possibility of energy release from the l l

devices, such exposure shall be minimized.

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3. ' Personnel handling explosive devices shall be provided with and shall use special equipment as required, such as nonsparking tools, conductive footwear, personnel protective l equipment, and grounded workbenches. Explosive devices q shall be mounted on a grounded tray during radiography.

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4. Unshielded, high-frequency generating apparatus shall not be j operated within 50 feet of any type of detonators.

t l 5. Appropriate WARNING and CAUTION notes, which ,

identify potential hazards to personnel, shall be incorporated L into the work procedures and similar documents for the intended operation. -l t i

6. During presence of explosives in the reactor room, no ,

smoking or open flame shall be permitted within the room in 'l which the radiography is being done. l

7. Personnel handling explosives shall not be permitted to carry spark-producing or flame-producing items in their pockets.  ;

8. No hazardous materials such as solvents, paints, gasoline, or i other volatile substances shall be located in working areas.

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9. Minimum personnel shall be present during radiography of l explosives.

10. Personnel who will perform the neutron radiography shall ,

have training in the hazards of explosive handling and shall be approved by the Company Explosives Supervisor. I i

[ l 1. The suitability of safety measures shall be as determined by the Coinpany Explosive Supervisor.

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Technical Specifications - TRIGA Mark i Amendment No. 34 Ref.1. Air Force Manual " Explosives Safety Manual" AFM 127-100, Department of the Air Force,2 December 1971.

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Technical Specifications - TRIGA Mark i Amendment No. 34 9.0 ADMINISTRATIVE CONTROLS 9.1 Organization Thefacility shall be under the supervision of the Physicist-in-Charge or his

. designated alternate. The minimum qualification for the Physicist-in-Charge ,

shall include a Bachelor's degree or equivalent academic education and three years experience in activities related to reactor operations. He shall be responsible to a Vice_ President whose duties include responsibility for research

, and development, or his designated alternate, for safe operation of the reactor and its associated equipment and for limiting exposure of personnel and dispersal of radioactive material. The reactor shall be related to the Corporate structure as shown in the following chart:

4 11ealth Vice-President Criticality & Radiation Physicist or Safeguards designated alternate Committee i 1 I i  !

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l----------- Physicist-in-Charge ---------8 1

- Facility Staff 9.2 Criticality and Radiation Safeguards Committee

u. There shall be a Criticality and Radiation Safeguards Committee (CRSC) l which shall revit w activities of thefacility to assure criticality and radiation safety. This Committee shall be composed of at leastfour members selected by the Vice President, or a designee, considering their i experience and education with regard to the various aspects ofnuclear physics, chemistry, radiological health and statistics, as well as

, appropriate experience in other disciplines such as metallurgy and engineering. Subcommittees shall be appointed by the Chairman of the CRSC. The subcommittee assigned the responsibilityfor reviewingfacility operations shall not have thereon person (s) who are directly involved with l thatJacility.

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Technical Specifications - TRIGA Mark I . Amendment No. 34 i

b. The Criticality and Radiation Safeguards Committee shall be in accordance with a written charter including provisions for:

1. Hold sneetings or audits at least annually; special meetings may be called by subcommittees of the CRSC or by the Chainnan of the CRSC at times when such meetings are deemed appropriate.

2. Have a quorum when a majority of the members attend.

3. Prepare minutes or auditfindings of the CRSC meetings by Chairman or his designee. Evidence of approval of the participating members of the CRSC shall be obtained before distribution.

4. delete

5. delete

6. delete

c. The Criticality and Radiation Safeguards Committee, or subcommittee, shall review and approve safety standards associated with possession of the Facility. The CRSC or a subcommittee thereofshall audit the Facility annually, but at intervals not to exceedfifteen (15) months..

d. The responsibilities of the Committee or designated subcommittee thereof include, but are not limited to, the following:

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1. Review and approval of experiments utilizing the reactor facilities in accordance with Section 8.!;

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

3. Determination of whether a proposed change, test, or experiment would constitute an unreviewed safety question or a change in the Technical ,

Specifications; I

4. Review ofFacility records; l l

5. Review of abnormalperfonnance ofplant equipment and other anomalies; and 18 l

Technical Specifications TRIGA Mark l Amendment No. 34

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

9.3 Written Procedures '

Written instructions shall be in effect for the following items. The instructions  !

shall be adequate to assure the safety of operation of the reactor but shall not preclude the use of independent judgment and action should the situation require such.

a. Testing and calibration ofreactor operating instrumentation and controls necessary to meet the requirements of the Technical Specipcations.

6. delete

c. Emergency and abnormal conditions including provisions for evacuation, reentry, recovery, and medical support.

d. Fuel element and experiment loading or unloading.

c. delete

f. delete

g. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms and abnormal reactivity changes.

Changes which alter the original intent of the above procedures shall be made only with the approval of the Criticality and Radiation Safeguards Committee (CRSC). Changes to the procedures that do not change their originalintent may be made by the Physicist-in-Charge; all such changes -

shall be documented and subsequently reviewed by the CRSC.

9.4 Action to be Taken in the Event of a Reportable Occurrence In the event of a reportable occurrence, as defined in Section 1.10 of the Specifications, the following action shall be taken:

a

a. The Physicist-in-Charge or designated alternate shall be notified and corrective action taken with respect to the operation involved.

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e Technical Specifications - TRIGA Mark l Amendment No. 34

b. The Physicist-in-Charge or otherperson notified under Section 9.4a shall notify the Chairman of the CRSC and the Vice President, or his designated alternate, identified in Section 9.1.

c. A report shall be made to the CRSC which shallinclude an analysis of the cause of the occurrence, efficacy of corrective action, and recommendationsfor measures to prevent or reduce the probability of recurrence.

d. A report shall be made to the NRC in accordance with Section 9.6 of these Specifications.

9.5 Plant Operating Records In addition to the requirements of applicable regulations, and in no way substituting therefor, records and logs shall be prepared of at least the following items and retained for a period of at least five (5) years.

a. Normal plant operation;

b. Principal maintenance activities;

c. Reportable occurrences;

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

e. Gaseous and liquid radioactive effluents released to the environs; j l

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f. Off-site environmental monitoring surveys, l l

g. Fuel inventories and transfers; j

h. Facility radiation and contamination surveys; I. Radiation exposures for all personnel;

j. Experiments performed with the reactor; and

k. Updated, corrected, and as-built drawings of the facility (these shall be retained for the lifetime of the facility).

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9.6 Reporting Requirements i

. In addition to the requirements of applicable regulations, and in no way substituting therefor, reports shall be made to the NRC as follows

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a. A report within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone orfacsimile to the NRC Operations Center and Region IV, USNRC of:

4' l. Any accidental release of radioactivity above permissible limits in

unrestricted areas, whether or not the release resulted in property

damage, personal inj ury, or exposure;

2. Any abnormal occurrences as defined in Section 1.10 of these

Specifications.

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b. A report within 10 days in writing to the Document Control Desk, USNRC ,

Washington, D.C. 20545 and Region IV, USNRC of:

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1. Any accidental release of radioactivity above permissible limits in unrestricted areas, whether or not the release resulted in property damage, personal injury, or exposure; the written report (and, to the extent possible, the preliminary telephone orfacsimile report) shall describe, analyze and evaluate safety implications, and outline the i corrective measures taken or planned to prevent reoccurrence of the F event.

2. Any abnormal occurrence as defined in Section 1.10 of these ,

Specifications, j

c. A report within 30 days in writing to the Document Control Desk, USNRC ,

Washington, D.C. 20545 and Region IV, USNRC of

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

2. Any significant changes in the transient or accident analyses as a described in all Safety Analysis Reports; and

3. Any significant changes in facility organization or personnel for which minimum qualifications are specified in these specifications.

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• l Technical Specifications - TRIGA Mark i Amendment No. 34

d. A report within 60 days after criticality of the reactor in writing to the Document Control Desk, USNRC , Washington, D.C. 20545 and Region IV, USNRC resultingfrom a receipt of a newfacility license or an amendment to the license authorizing an increase in reactorpower level or the installation of a new core, describing the measured values of the operating conditions or characteristics of the reactor under the new  ;

conditions. j

c. A routine report in writing to the Document Control desk, U.S. Nuclear Regulatory Commission by April 15 of each year, providing the following information:

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2. delete

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4. delete

5. A summary ofeach change, ifsuch changes have been made, to the facility, orprocedures, tests, and experiments carried out under the conditions ofSection 50.59 of10 CFR Part 50. [

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7. delete

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Technical Specifications - TRIGA Mark i A;Teendment No. 34 TABLEI MINIMUM REACTOR SAFETY SYSTEM SCRAMS Originating Mode in Which Channel Set Point Effective SS Pulse

1. Power Level 275 kW or lower X (2 independent channels) U)

As specified in Section 7.4 or X

2. Fuel Element Temperature lower (2 independent channels)

X X

3. Console Scram Manual X X

4. Facility Power Supply Supply Failure X X

5. Magnet Current Key Switch Manual X X

6. Watchdog Timer (2) Software Failure (1) Of the minimum required two independent channels, no more than one channel shall utilize digital processing of power detector signals.

(2) These scrams are only applicable when computers are utilized to perform reactor control functions.

TAllLE II MINIMUM INTERLOCKS Action Prevented Mode in Which Effective SS Pulse

1. Withdrawal of more than one standard rod X

2. Withdrawal of any standard rod X

3. Application of air to transient rod unless its X movable cylinder is fully down 23