ML20212G414

Amend 35 to License R-38,removing Authority from License to Operate Reactor,Authorizing Possessing Only of Reactor & Changing TSs to Remove Operational Requirements Not Needed for Possession Only Status

ML20212G414
Person / Time
Site:	General Atomics
Issue date:	10/29/1997
From:	Weiss S NRC (Affiliation Not Assigned)
To:
Shared Package
ML20212G407	List: ML20212G403 ML20212G414 ML20212G420
References
R-038-A-035, R-38-A-35, NUDOCS 9711060171
Download: ML20212G414 (29)

Text

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• Ct:0 i . p* lt UNITED STATES

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g NUCLEAR REGULATORY COMMISSION n WASHINGTON, D.C. em wi f

R ... .. p GENERAL ATOMlQ3 DOCKET NO. 50-89 6,MENDMENT TO AMENDED FACILITY LICENSE Amendment No. 35 License No. R 38

1. The U.S. Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to Amended Facility License No. R 38 filed by General Atomics (the licensee), dated December 17,1996, as supplemented on April 25, and August 18,26, and 29,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the regulations of the Commission as set forth in 10 CFR Chapter I; B. The facility will be possessed in conformity with the application, the provisions of the Act, and the rules and regulatlens of the Commission; C. There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public and (ii) that such activities will be conducted in compliance with the regulations of the Commission; D. This amendment will not be inimical to the common defense and security or to the health and safety of the public; E. This amendment is issued in accordance with 10 CFR Part 51 of the regulations of the Commission and all applicable requirements have been satisfied; and F. Prior notice of this amendment was not required by 10 CFR 2.105 and publication of notice for this amendment was not required by 10 CFR 2.106.

i 9711060171 971029 PDR ADOCK 05000089 P PDR

o 2-j 2. Accordingly, the license is amended by changes to the following paragraphs, which are

, hereby amended to read as follows:

1.C. The facility will be possessed in conformity with the application as amended, the

provisions of the Act, and the nales and regulations of the Commission; 1.D. There is reasonable assurance that the reactor facility can be possessed (i) without endangering the health and safety of the public and (ii) in compliance with the j regulations in this chapter, 1.E. General Atomics is technically and financially qualified to possess the facility in

, accordance with the regulations in this chapter, 2.B. Subject to the conditions and requirements incorporated herein, the Commission herebylicenses General Atomics:

1 (1) Pursuant to Section 104c of the Act and 10 CFR Chapter I, Part 50 " Licensing of Production and Utilization Facilities", to possess, but not operate, the reactor at the designated location at San Diego, Califomia, in accordance with the procedures and limitations described in the application and in this license.

1 (2) Pursuant to the Act and 10 CFR Chapter I, Part 70 " Domestic Licensing of Special Nuclear Material", to receive and possess up to 5.0 kilograms of i contained uranium 235 in connection with possession of the facility, and to possess but not separate special nuclear material such as may have been produced by past operation of the reactor.

1 (3) Pursuant to the Act and 10 CFR Chapter 1, Part 30 " Rules of General Applicability to Domestic Licensing of Byproduct Material", to possess but not to separate such byproduct material as may have been produced by past operation

, of the reactor.

3. Accordingly, the license is amended by deleting paragraph 2.C.(1) in its entirety.

4. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the enclosure to this license amendment, and paragraph 2.C.(2) of Facility License No. R-38 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 35, are hereby incorporated in the license. The licensee shall possess the facility

in accordance with the Technical Specifications, i

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5. Accordingly, the license is amended by adding paragraph 2.C.(4) which reads as follows:

' (4) Fuel Storace So long as General Atomics possesses the reactor in accordance with the Technical Specifications as amended, no fuel shall be stored in, or moved into, the reactor core structure.

6. This license amendment is effective 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION l [

M '".

Seymour H. Weiss, Director Non Power Reactors and Decommissioning Project Directorate

Division of Reactor Proje

t Management j Office of Nuclear Reactor Regulation

Enclosure:

l- Appendix A Technical j Specifications Changes 4 Date of Issuance: October 29, 1997 i

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ENCLOSURE TO LICENSE AMENDMENT NO. 35 AMENDED FACILITY UCENSE NO. R 38 DOCKET NO. 548g Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised pages are identified by amenoment number and contain vertical lines indicating the areas of change.

1 Remwe 1011d 1 17 Cover Page Table of Contents 1 ?3 i

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TRIGA Reactors Facility TECHNICAL SPECIFICATIONS TRIGA MARK I REACTOR Facility License No. R 38 As Amended & Issued through Amendment 35 October,1997

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TABLE OF CONTENTS Page No.

1.0 De finitions . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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 Safe ty Systems . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 5.3 Maintenance on Control and Safety Systems . . . . . . . . . . . . 8

! 6.0 Fuel Storage ................................... 9 4

7.0 Reactor Operations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 8.0 Experiments ................................... 10 8.1 Experiment Approval Procedures . . . . . . . . . . . . . . . . . . . 10

, 8.2 Experimental Limitations . . . . . . . . . . . . . . . . . . . . . . . . 10 9.0 Administrative Controls . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 9.1 Organization . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 9.2 Review Comminee ............................ 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 Reponing Requirements . . . . . . . . . . . . . . . . . . . . . . . . . 20 Table 1: Minimum Reactor Safety System Scrams . . . . . . . . . . . . . . . . 23 Table II: Minimum Interlocks . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 23 I

Amendment No. 35

APPENDIX A LICENSE NO. R 38 TECHNICAL SPECIFICATIONS FOR THE TORREY PINES TRIGA MARK 1 REACTOR DATE: JANUARY 21,1972 1.0 DEFINITIONS ,

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

1.2 Reactor Secured Reactor secured shall mean that condition wherein:

(a) The reactor is shut down, and (b) no work is in progress involving hudling 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.

l 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 r,ection.

1.5 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.

1 Amendment No. 35

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1.6 Operable l,

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! A system or device shall be considered operable when it is capable of performing its

intended functions in a normal manner.

I 1.7 Cold Critical i

i *Ihe reactor is in the cold critical condition when it is critical with the fuel and bulk

! water temperatures both below $00C, c

) 1.8 Experiment  !

i An experimer* 4 (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.)

l 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 l corresponding routine experiment. j

! c. Special Experiments. Special experiments are those which are not routine nor l modified routine experimems.  ;

l 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 j out-of core furnaces, out-of-core radiation racks, and the in-core facilities (including j single-element positions, three element positions, and flux measuring holes in the

! upper grid plate between the fuel elements).

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j 1.10 Reportable Occurrence i

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~A reportable occurrence is say of the following which occurs during reactor -

possession

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c. deletet i

b. delete; i

c. delete; I

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

, e. An observed inadequacy in the implementation of either administrative or l 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 1

! f. Release of fission products from.a fuel element.

1 1.11 Reactor Safety Systems i

' Reactor safety systems are those systems, including their associated input circuits, 1

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.

j 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 requ!res reanual protective action to j be initiated.

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! l.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 ,

i approximately 0.3 inch from the center of the fuel body.

l.14 Measured Value l The measured value is the magnitude of that variable as it appears on the output of a '

, measunng chennel.

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_l.15 Measuring Channel ,

A measuring channel is the combination of sensor, interconnecting cables or lines, -

2 amplifiers, and output device which is connected for the pumose of measuring the value of a variable.

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1.16 ChannelCalibration 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 TRIG A core is an arrangement in water solely of standard TRIGA fuel which is an alloy of uranium zirconium hydride conte ined in a metal clad.

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o Amendment No. 35

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2.0 SITE A minimum radius of 120 feet from the approximate center of the TRIO /. 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,11e 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 pool when fuelis in the core.

3.4 *Ihe pool water shall he 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 Amendment No. 35

4.0 REACTOR CORE i 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, volds, control rods, in core experiments, and rabbit facilities. ,

4.2 Standard fuel elements shall have the fu awing characteristics:

a) Maximum uranium content in unitradiated fuel 9.0 wt %

b) Maximum uranium enrichment in unirradiated fuel 20%

c) Hydrogen to zirconium ratio (in the 0.9 to 1.54 H atoms to 1.0 Zr atom ZrHn) (Iow hydride) 1.55 to 1.8 H atoms to 1.0 Zr atom (high hydride) d) Cladding materials and minimum 0.020 inch 304 or 304L stainless thickness steel,Incoloy 800, Hastelloy X, or 0.030 inch aluminum or Zircaloy 4.3 Any bumable poison used shall be an integral part of tne as manufactured fuel element. A burnable 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

c. delete 6

Amendment No. 35 1

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1 5.0 CONTROL AND SAFETY SYSTEMS l 5.1 Control Systems l 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, j cadmium, or the rare earth poisons in solid form clad with the materials j authorized for fuel-element cladding. The control rods may contain flux j traps and may be equipped with fuel or non fuel followers, i

5.1.2 No reactor fuel elements or control elements with fuel followers shall be j located in, stored in, or moved into, the reactor core structure.

i l 5.1.3 delete I

5.1.4 delete 4

5.1.5 delete i

5.2 Safety Systems j 5.2.1 The reactor safety systems and the associated instruments necessary to i

provide the scrams listed in Table I shall be operable during reactor

{ operation.

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

l i 5.2.3 Radiation monitoring systems shall be operable as follows:

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

l l b. When the reactor is not secured, a continuous monitoring system for

! airborne activity having a readout and audible alarm which can be .

l heard in the reactor and control rooms.

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l These systems shall be calibrated annually and their setpoints verified monthly. For l . periods of time for maintenance or repair to the above systems, or during periods of

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other forced outages, the intent of this specification shall be satisfied if the installed system (s) is replaced with appropriate attemate or portable radiation monitoring L system (s).

r Amendment No. 33 l

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5.24 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 ufety system need only be verified prior to the extended operation.

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

Amendment No. 35

6.0 FUEL STORAGE 6.1 All fuel elements or fueled devices shall be stored in a safe geometry (kejy 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 1 permit sufficient natural convection cooling by water or air such that the temperature I of the fuel element or fueled device will not exceed design values.

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

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6.4 Fuel handling tools or devices shall be stored in a secure manner such that their use l 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.

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

r.. 55.00 during steady. state operations, or

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.

9 Amendeent No. 35

8.0 EXPERIMENTS 1 Experiment Approval Procedures 8.1.1 Routine experiments rnay be perfonned at the discretion of the Physicist in Charge or his designated attemate, 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.11e shall consider the experiment in ter.ns ofits effect on reactor operation and the possibility and consequences ofits failures, including, where significant, consideration of chemical reactions, physical integrity, design ur e, proper cooling, intern: tion with core components, and reacthity efrects.

8.1.3 Modified routinc experiments may be performed at the discretion of the Physicist in Charge withovt the necessity of any further review or approval provided that the evrduation performed in accordanc, 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 experimmt or type of experiment has been reviewed and approved by the Criticality .ind Radiation Safety 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,

b. The total absolute reactivity worth of a combination of experiments shall not exceed $4.00. This includer the potential reactivity which 10 Amendment No. 35

might result from experiment malfunction, experiment flooding or vsiding, removal or insertion of experiments.

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

8.2.2 Explosive materials such as gunpowder, dynamite TNT, nitroglyceria, 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 quantitles 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 ace! dent 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 altbome 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 effluent exhausts through a filter installat ion designed for greater than 99 percent efficiency for 0.3 n eto particlN s east 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 Amendment No. 35

Specifications shM1 be controlled such that the total inventory oflodine isotopes 131 through 135 in each experiment is no greater than 1.5 curies.

8.2.5 One or more in core electrically heated fumaces 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 fumaces in use during steady state or transient operations shall not exceed 2 x 1016 for materials containing fissionable material subjected to a bum up ofless than 1 percent, or 2 x 10 15 fissions for materials containing fissionable materials subjected to a burn up of 1 perccut or greater.

2. The helium purge from each fumace shall:

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

11. Have a rate within the range of approximately 0.2 and 10!) liters per minute.

3. The fumace temperature shall not exceed 20000C.

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

1. Intemal fumace pressure less than 11 psig,'and

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

b. Experiments involving solely nonfissionable material:

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

1. Intemal fumace pressure less than 11 psig, and 12 knen&ent No. 35

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ii. Set points 10 percent above and below the operating current setting for the fumace.

8.2.6 He in core assemblies from one or more pneumatic transfer systems may be used in conjunction with the irradiation of materials. Rese units may remain in the core during other reactor operation. De 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 b radiated under conditions which lead to a total inventory ofiodine isotopes 131 135 in excess of 5 curies but no greates than 16 curies per specimen, provided that the specimens are doubly encapsulated or, if singly encapsulated, placed in a sealed sample container, ne capsules shall be located at least 16 fect below the pool surface during irradiation.

8.2.8 If an experiment fails and releases material which in the judgment of the Physicist in Charge or his designated attemate, 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 she.ll 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 w:re 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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b. Explosive Jevices (such as canridges or shaped charges) whose discharge could produce a thmst in a definite disection shall be positioned so as to be aimed away from the re

ctor and its components.

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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 4

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 stond

outsHe the reactor building in a storage magazine or magazines for j radiography with the Mark I reactor is 100 pounds of propellent (low 1 explosive). Type 2 magazine (s) shall be used for Clus B or Class C

explosives. The new high energy piopellants may be detonable and should be handled as high explosives.

! e. All vertical neutron radiography beam pons shall be sealed to prevent explosive devices from falling inside to the bottom of the pon. 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 l region.

f. Blast shields shall be mounted on the bridge or other suppun structure l 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 goveming 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 radiation may increase the possibility of energy release from the devices, such

exposure shall be minimized.

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Amendment No. 35 l.

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3. Personnel handling explosive devices shall be provided .

with and shall use special equipment as required, such as nonsparking .

j tools, conductive footwear, personnel protective equipment, and ,

grounded workbenches. Explosive devices shall be mounted on a j grounded tray during radiography.

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

5. Appropriate WARNING ed CAUTION notes, which 4 identify potential hazards to personnel, siall be incorporated into the l work procedures and similar documents for the intended operation.  ;

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

I 7. Personnel handling explosives shall not b:: permitted to l carry spark producing or flame producing items in their pockets.

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

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

! 10. Perr.onnel who will perFrm the neutron radiography shall +

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

l 11. 'The suitability of safety measures shall be as determined by

[ the Company Explosive Supervisor.

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j Ref.1. Air Force Manual " Explosives Safety Manual" AFM 127100, Department of the Air 3 j Force,2 December 1971, i

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9.0 ADMINISTRATIVE CONTROLS 9.1 Organization

ne facility shall be under the supenision of the Physicist in Charge or his designated attemate, both of whom shall be licensed senior operators of the facility.

The mirdmum 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 allemate, for safe possession of the reactor and its associated equipment and for l l limiting exposure of personnel and dispersal of radioactive material. De reactor shall be related to the Corporate structure as shown in the following chart:

Vice President Cognizant i Vice President or Vice President 1

j designated attemate

! Director

. Licensing, Safety and j Nuclear Compliance 4

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Health Criticality & Radiation Physicist - - - - -

Physicist in Charge -----

Safety Committee Facility Staff Direct Reporting 1 -------- Functional Support / Oversight

f 16 Amendment No. 35

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9.2 Criticality and Radiation Safety Committee

a. There shall be a Criticality and Radiation Safety Committee (CRSC) which

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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 regard 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 Chairman 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,

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

1. Hold 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. Have a quorum when a majority of the members attend.

3. Prepare minutes or audit Gndings 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 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:

1. Review and approval of experiments utilizing the reactor facilities in accordance with Section 8.1; 17 Amendment No. 35

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

6. Review of unusual or abnormal occurrences and incidents which are Reportable Occurances under 10 CFR 20 and 10 CFR 50. l 9.3 Written Procedures Written instructions shall be in effect for the following items. The instructions shall be adequate to assure the safe possession of the reactor but shall not preclude the use j of independent judgment and action should the situation require such.

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

b. delete -

c. Emergency :.nd abnormal conditions inclub.; p.svisions for evacuation, reentry, recovery, and medical support,

d. Fuel element and experimerit loading or unloading,

c. delete

f. Maintenance of systems necessary for assuring the integrity of the fuel or dierwise 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 changes.

18 Amendment No. 35

4 Changes which alter the original intent of %c (bove procedures shall be made only with the approval of the Criticality and I; awn Safety Committee (CRSC).

Temporary changes to the procedures that 1, 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 alternate 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 attemate, l

identified in Section 9.1.

c. A report shJl be made to the CRSC which shall include an analysis of the cause l 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, recorn 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 Techr<ical Specifications;

e. Gaseous and liquid radioactive effluents released to the environs; Amendment No. 35 1

f. Off site environmental monitoring surveys;

g. Fuelinventories 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 fo'r the lifetime of the facility).

9.6 Reporting Requirements In addition to the requirements of.pplicable regulations, and in no way substituting therefor, repons 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, personalinjury, or exposure;

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

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 propeny damage, personal injury, or exposure; the written repon (and, to the extent possible, the preliminary telephone or facsimile report) shall describe, analyte and [

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

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

Specifications.

20 Amendment No. 35

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O

1

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 safe:y<onnected operating characteristics occurring during operation of the reactor;

2. Any significant changes in the transient or accident analyses as

described in all Safety AnrJysis Reports; and l 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 l receipt of a new facility license or an amendment to the license authorizing an 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,

e. By Ap:il 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.

I

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

3. The number of emergency shutdcwns 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 the reasons for any corrective maintenance required.

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

21 Amendment No.35

_ m . _ . _ ,,. .,, . . . , . , - , . _ _ - - - - .

i

6. A summary of the nature and amount of radivactive 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 time of significant exposure and a brief sununary of the results of radiation and contamination surveys performed within the facility. -

f. Commencing in 1999, a routine report in writing to the Document Control Desk, U.S. Nuclear Regulatory Ccmmission 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 the reasons for any cornetive 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 Pan 50,

4. A summary of the nature and amount of radioactive effluents released or discharged to the environs beyond 2.:.cHective control of the licensee as measured at or prior to the point of such release or discharge.

5. A dextiption 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. ,

22 7- mdment No.35

TABLEI hDNIMUM REACTOR SAFETY SYSTEM SCRAMS Originating Mode in Which Channel Set Point _

Effective I SS Pulse

1. PowerLevel 275 kW or lower X (2 independent channels)m

2. FuelElementTemperature As specified in Section X (2 independent channels) 7.4 or lower 4

3. Console Scram Manual X X

4. Facility Power Supply Supply Failure X X

5. Magnet Current Key Sv cch Manual X X

6. Watchdog Timer

• Software Failure X X (1) Of ti,e 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 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

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23 Amendment No.35

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