ML20210Q705

Proposed Tech Specs Re Triga Mark I Reactor,As Amended & Issued Through Amend 34

ML20210Q705
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Site:	General Atomics
Issue date:	08/31/1997
From:	GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER
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ML20210Q702	List: ML20210Q697 ML20210Q705
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NUDOCS 9709020111
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TRIGA Reactors Facility TECHNICAL SPECIFICATIONS TRIGA MARK I REACTOR Facility 1.icense No. R-38 As Amended & Issued through Amendment 34 August,1997 f00'$0Nk050000j9

O TAlli.E OF CONTENTS Pnge No.

1.0 D e fi n i t io ns . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I 2.0 Site ......................................... 5 3.0 Reactor Pool ................................... 5 4.0 Reactor Core . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 5.0 Control and Safety Systems ......................... 7 5.1 Control Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 5.2 Safety Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 l 5.3 Maintenance on Control and Safety Systems . . . . . . . . . . . . S 6.0 Fuel Storage ................................... 9 7.0 Reactor Operations .,............................. 9 8.0 Experiments ................................... 10 l 8.1 Experiment Approval Procedures . . . . . . . . . . . . . . . . . . 10 8.2 Experimental Limitations ........................ 10 9.0 Administrative Controls . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 9.1 Organization ................................ 16 9.2 Review Committec ............................ 17 9.3 Written Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . 18 9.4 Action to be Taken in the Event of a Reportable Occurrence . 19 9.5 Plant Operating Records ........................ 19 9.6 Reporting Requirements . . . . . . . . . . . . . . . . ,..... 20 Table 1: Minimum Reactor Safety System Scrams . . . . . . . . . . . . . . . . 23 Table 11: Minimum Interlocks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23

s APPENDIX A LICENSE NO. R 38 .

4 TECilNICAL SPECIFICATIONS FOR Tile TORREY PINES TRIGA MARK 1 REACTOR DATE: JANUARY 21,1972 1.0 DEFINITIONS l

1.1 Reactor Shutdown l Reactor shutdown shall mean that the reactor is suberitical at all times by at least one dollar of reactivity.

1.2 Reactor Secured Reactor secured shall mean that condition wherein:

(a) The reactor is shut down, and s

(b) no work is in progress involving handling of fuel, experiments or reactor core related maintenance operations.

1.3 Reactor Operation Reactor operation shall mean any condition wherein the reactor is not shutdown.

4 1.4 Standard Control Rod A standard control rod is a control rod having rack and pinion electric motor drive and scram capabilities. It may have a fueled follower section.

l.5 Transient Control Rod <

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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1.6. Operable A system or device shall be considered operable when it is capable of perfonning its intended functions in a nonnal manner.

l7 Cold Critical l

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 nonnal part of the reactor, or (b) any operation designed to measure reactor characteristics. (Nonnal control rod calibrations are not cansidered 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 thm the hazards are neither greater nor significantly different than those for the corresponding routine experiment.

c. Special Experiments. Special experiments are those which are not routine nor modified routine experiments.

1.9 Experimental Facilities Experimental facilities are facilities used to perform 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).

~ 1.10 Reportable Occurrence A reportable occurrence is any of the following which occurs during reactor possession:

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--% =_

_ ___ J

. a. delete;

b. delete;

c. delete;

d. Any unanticipated or uncontrolled change in reactivity greater that $1.00;

c. An observed inadequacy in the implementation of either 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 requirements of the Technical Specifications; and

f. Itelease of fission products from a fuel element.

1.11 Reactor Safety Systems Reactor safety systems are those systems, including their associated input circuits, which are deslLned 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.

1.12 Experiment Safety Systems Experiment safety systems are those systems, including their associated input circuits, which are designed to initiate a scram for the primary purpose of protecting 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 embedded in the fuel near the horizontal center plane of the fuel element at a point approximately 0.3 inch from the center of the fuel body.

1.14' Measured Value The measured value is the magnitude of that variable as it appears on the output of a measuring channel.

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

3

. 1.16 ChcnnelColibration 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 ad,iusted to respond, with acceptable accuracy, to known values of the measured variable.

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

i t

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. 2.0 SITl!

A minimum radius of 120 feet from the approximate center of the TRIGA Reactor

. Facility building shall define the exclusion area.

3.0 Rl! ACTOR p0OL 3.1 The reactor core shall be cooled by natural convective water flow.

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

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

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

5 am .' ... .. .--:u--------- - - "- -

. 4.0 Rl!ACTolt Coltti 4.1 'lhe 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, volds, 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 unitradiated fuel 20 %

c) llydrogen to zirconium ratio (in the 0.9 to 1.5411 atoms to 1.0 Zr atom Zrli) n (low hydride)

I 1.55 to 1.811 atoms to 1.0 Zr atom (high hydride) d) Cladding materials and minimum 0.020 inch 304 or 304L stainless thickness steel,incolay 800,llastelloy X, or 0.030 inch aluminum or Zirealoy 4.3 Any burnable poison used shall be an integral part of the as manufactured fuel I

element, A burnable poison is defined as a mmerial used for the specilie purpose of compensating for fuel burn up and/or other long term reactivity adjustments.

4.4 Fuel lilement inspection.

a. delete

b. delete e, delete 1

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4

. _ 5.0 CONTROL AND SAFETY SYSTEMS 5.1 Control Systems 4

5.1.1 The poison section of the control rods shall contain borated graphite or stainless steel, ll4 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 Dux traps and may be equipped with fuel or non fuel followers.

5.1.2 No reactor fuel elements or control elements with fuel followers shall be located in, stored in, or moved into, the reactor core structure 5.1.3 delete 5.1.4 delete 5.1.5 delete i

i 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 as follows:

a. An area radiatiun monitoring system capable of activating an

, acuation 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 monthly. For periods of time for maintenance or repair to the above systems, or during periods of other forced 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).

7 I

5.2.4 The reactor safety systems plus a startup channel shall be verined 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 te th. .'xtended operation.

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

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. 6.0 ' FUEL STORAGE 6.1 All fuel elements or fueled devices shall be stored in a safe geometry (ke rrless 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 of fuel.

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

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

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a. $5,00 during steady-state operations, or '

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b. $3.25 during transient operations, 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,

b. The maximum allowable fuel temperature shall be 5300C for standard low hydride fuel elements or aluminum-clad elements.

7.5 The maximum reactivity worth of any transient control rod shall be $3.00.

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8.0 EXPERIMENTS i i

8.1. Experirnent 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. Ile 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 that the hazards associated with the modified routine experiments are neither 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 and Radiation Safety Commiree.

8.1.5 Favorable evaluation of the protective measures prov'ded for an experiment

- shall conclude that failure of the experiment will not icad directly to a failure of a fuel element or other experiments or interfere with movement of a control rod.

8.2 Experimental 1. imitations 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.

b. The total absolute reactivity worth of a combination of experiments shall not exceed $4.00. This includes the potential reactivity which 10

might result from experiment malfunction, experiment flooding or voiding, removal or insertion of ex,- riments.

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 l 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 i:

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 airbome concentrations of radioactive gases or aerosols may be released to the reactor room,100 percent of the gases or aerosols will escape;

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

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 11

4 Specifications shall be controlled such that the total inventory ofiodine isotopes 131 through 135 in each experiment is no greater than 1.5 euries.

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 1015 fissions for materials containing fissionable materials subjected to a burn up of 1 percent or greater.

2, The helium purge from each fumace shall:

1. Vent through a liquid nitrogen-cooled charcoal trap, and

11. 11 ave 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 fumace pressure less than 11 psig, and l li. Set points 10 percent abov:: and below the operating current setting for the furnace,

b. Experiments involving solely nonfissionable material:

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

i. Internal furnace pressure less than 11 psig, and 12 l

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11. Set points 10 percent above and below the operating current setting for the furnace.

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 terminus 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 total inventory 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 releasas material which in the judgment 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 and Radiation Safety 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 and Radiation Safety 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:

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.

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.D

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 TNT in the reactor room housing the reactor. This one pound shall be an aggregate composed ofitems none of which shall exceed 91 grams.' in the event of temporary interruption 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 />,

d. The maximum quantity of explosive material that may be stored outside the reactor building in a storage magazine or magazines 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.

e. 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 fal'.ing through the tank water to the reactor core region.

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:

1. Explosive devices shall be handled in accordance with Chapter 2 of Ref.1.

2. Since exposure to excessive heat or high energy radiatien may increase the possibility of energy release from the devices, such exposure shall be minimized.

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p .

.,s . . .. . . . ..

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

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

5. Appropriate WARNING and CAUTION notes, which identify potential hazards to personnel, shall be incorporated into the work procedures and similar documents for the intended operation.

6. During presence of explosives in the reactor room, no smoking or opcn flame shall be permitted within the room in which the L radiography is being done.

7. Personnel handling explosives shall not be permitted to

{ carry spark-producing or llame-producing items in their pockets.

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

9. Minimum personnel shall be present during radiography of 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.

I1. The suitability of safety measures shall be as determined by the Company Explosive Supervisor.

Ref.1. Air Force Manual" Explosives Safety Manual" AFM 127-100, Department cf the Air 15 l

.. s.

9

.4 Force,2 December 1971, I

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4 9.0 ADMINISTRATIVE CONTROLS 9.1 Organization The facility shall be under the supervision of the Physicist-in-Charge or his designated alternate, both of whom shall be licensed senior operators of the facility.

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. lie shall be responsible to a Vice President whose duties include responsibility for research and development, or his designated alternate, for safe possession 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:

Vice President Cognizant Vice President or Vice President designated alternate Director Licensing, Safety and Nuclear Compliance llealth Criticality & Radiation Physicist Physicist-in-Charge Safety Committee Facility Staff Direct Reporting Functional Support / Oversight 17 l

l 9.2 Criticality and Radiation Safety Committee

a. There shall be a Criticality and Radiation Safety Committee (CRSC) which shall review activities of the facility to assure criticality and radiation safety.

The Committee shall be composed of at least four members selected by the cognizant Vice President, or a designee, considering their experience and education with regaru to the various aspects of nuclear 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 Chainnan of the CRSC. The subcommittee assigned the responsibility for reviewing facility operations shall not have thereon person (s) who are directly involved with that facility.

I

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

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

2. 1 lave a quorum when a majority of the members attend.

3. Prepare minutes or audit fmdings 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. deletc

6. delete

c. The Criticality and Radiation Safety Committee, or subcommittee, shall review and approve safety standards associated with possession of the Facility. The CRSC or a subcommittee thereof shall audit the Facility annually, but at intervals not to exceed fifteen (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 8.1;

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

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

4. Review of Facility records;

5. Review of abnormal performance of plant equipment and other anomalies; and

(

f l 6. Review of unusual or abnormal occurrences and incidents which may L

be Reportable Occurances 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 l be adequate to assure the safe possession of the reactor but shall not preclude the use ofindependent judgment and action should the situation require such,

a. Testing and calibration ofinstrumentation, controls and radiation monitors necessary to meet the requirements of the Technical Specifications.

b. delete

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

d. Fuel element and experiment loading or unloading,

e. delete

f. Maintenance of systems necessary for assuring the integrity of the fuel or otherwise maintaining the reactor in POLA status.

g. Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms and abnormal reactivity 19

changes, 1

Changes which alter the original intent of the above procedures shall be made only with the approval of the Criticality and Radiation Safety Committee (CRSC).

Temporary changes to the procedures that do not change their original intent and do not constitute an unreviewed safety question (as defined in 10 CFR 50.59) may be made by the Physicist-in Charge. All such temporary 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. The Physicist in-Charge or designated attemate shall be notified and corrective action taken with respect to the operation involved.

b. The Physicist in-Charge or other person 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 shall include an analysis of the cause of the occurrence, efficacy of corrective action, and recommendations for measures to prevent or reduce the probability of 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;

e. Reportable occurrences;  ;

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[

(

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

c. Gaseous and liquid radioactive efiluents released to the environs;

f. Off-site environmental monitoring surveys;

g. Fuel inventories and transfers;

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).

9.6 Reporting Requirements in addition to the requirements of applicable regulations, and in no way substituting therefor, reports shall be made to the NRC as follows:

a. A report within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone or facsimile to the NRC Operations Center:

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;

2. Any reportable occurrences as defined in Section 1.10 of these Specifications.

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

Washington, D.C. 20555:

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 or facsimile report) shall describe, analyze and -

evaluate safety implications, and outline the corrective measures taken or planned to prevent reoccurrence of the event.

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

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

Washington, D.C. 20555:

1. 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 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.

d. A report within 60 days after criticality of the reactor in writing to the Document Control Desk, USNRC , Washington, D.C. 20555 resulting from a receipt of a new facility license or an amendment to the license authorizing an I.

increase in reactor power 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.

c. By April 15,1998, a routine report in writing to the Document Control Desk, U.S. Nuclear Regulatory Commission providing the following information:

1. A brief narrative summary of: (1) operating experience (including:

experiments performed); (2) changes in facility. design, performance -

characteristics, and operating procedures related to reactor safety occurring during the reporting period; and-(3) results of surveillance tests and inspections.

2. A : tabulation showing the energy generated by the reactor (in megawatt hours). ,

3. The number of emergency shutdowns and inadvertent scrams, including the reasons therefor and corrective action, if any.

4. Discussion of the major maintenance operations performed during the period including the effects,'if any, on the safe operation of the reactor, and 22 1

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.e the reasons for any corrective maintenance required.

5. A summary of each change to the facility or procedures, tests, and experiments carried out under the conditions of Section 50.59 of CFR Part 50.

6. A summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective control of the licensee as -

measured at or prior to the point of such release or discharge.

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

8.

A summary of radiation exposures received by facility personnel and visitors, including the dates and tirae of significant exposure, and a brief l summary of the results of radiation and contamination surveys performed within the facility.

4

f. Commencing in 1999, 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:

1. A brief narrative summary of: (1) possession and storage and (2) changes in facility storage design.

2. Discussion of the major maintenance operations performed during the period, including the effects, if any, on the safe possession of the reactor,-

and th:, reasons for any corrective maintenance required.

3. A summary of each change, if such changes have been made, to the facility, or procedures, tests, and experiments carried out under the conditions of Section 50.59 of CFR Part 50.

4. A summary of the nature and amount of radioactive effluents released or discharged to the environs beyond the effective control of the licensee as measured at or prior to the point of such release or discharge.

5. A description of any environmental surveys performed outside the facility.-

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

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

2. Fuel Element Temperature As specified in Section (2 independent channels) 7.4 or lower

3. Console Scram Manual

4. Facility Power Supply Supply Failure

5. Magnet Current Key Switch Manual

6. Watchdog Timer m Software Failure t

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44 TABLEI MINIMUM REACTOR SAFETY SYSTEM SCRAMS Originating Channel Set Point

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

2. Fuel Element Temperature As specified in Section (2 independent channels) 7.4 or lower

3. Console Scram Manual

4. Facility Power Supply Supply Failure

5. Magnet Current Key Switch Manual

6. Watchdog Timer m Sonware 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.

TABLE II MINIMUM INTERLOCKS Action Prevented Mode in Which EfTective SS Pulse

1. Withdrawal of more than one standard rod -X

2. Withdrawal of any standard rod X I

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

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