ML16197A421

TSAF50-00228 - Aerotest Radiography and Research Reactor (Arrr), Current Facility Operating License R-098, Tech Specs, Revised 01/28/1981

ML16197A421
Person / Time
Site:	Aerotest
Issue date:	10/22/1974
From:	Goller K US Atomic Energy Commission (AEC)
To:	Aerotest
References
Download: ML16197A421 (20)

Text

AEROTEST OPERATIONS, INC.

DOCKET NO. 50-228 AEROTEST RADIOGRAPHY AND RESEARCH REACTOR (ARRR)

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 5 License No. R-98

1. The Nuclear Regulatory Commission (NRC or the Commission), having previously made the findings set forth in Amended Facility Operating License No. R-98 issued on January 28, 1981, has now found that:

A. The application for indirect transfer of license and conforming amendments to Amended Facility Operating License No. R-98, filed by Aerotest Operations, Inc.,

and Nuclear Labyrinth, LLC, dated May 30, 2012, and supplemented on July 19 and October 15, 2012; January 10, 2013; and April 21, June 16, August 22, and October 10, 2016, complies with the standards and requirements of the Atomic Energy Act of 1954 (the Act), as amended, and the rules and regulations of the Commission as stated in Title 10, Chapter I, Nuclear Regulatory Commission, of the Code of Federal Regulations (10 CFR Chapter I).

B. Construction of the facility has been substantially completed in conformity with Construction Permit No. CPRR-86, and the application, as amended, the provisions of the Act and the rules and regulations of the Commission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; D. There is reasonable assurance: (i) that the activities authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the rules and regulations of the Commission; E. Aerotest Operations, Inc. is technically and financially qualified to possess, use, and operate the facility in accordance with the rules and regulations of the Commission; Amendment No. 5

F. The issuance of this operating license will not be inimical to the common defense and security or to the health and safety of the public, and does not involve a significant hazards consideration; G. The receipt, possession, and use of byproduct and special nuclear material as authorized by this license will be in accordance with the Commissions regulations in 10 CFR Parts 30 and 70, including Sections 30.33, 70.23, and 70.31; H. The licensee is qualified to be the holder of the license; and I. The transfer of the license is otherwise consistent with applicable provisions of law, regulations, and orders issued by the Commission pursuant thereto.

2. Facility Operating License No. R-98, issued to Aerotest Operations, Inc., is hereby indirectly transferred to Nuclear Labyrinth, LLC, and the license is amended to read as follows:

A. This license applies to the Aerotest Radiography and Research Reactor (ARRR),

a pool-type nuclear reactor owned by Aerotest Operations, Inc. The facility is located at the Aerotest Operations site near San Ramon, California, and is described in the application dated September 14, 1964 (the application), and in supplements thereto, including the application for transfer of license dated April 24, 1974, and the application for indirect transfer dated May 30, 2012.

B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Aerotest Operations, Inc.:

(1) Pursuant to Section 104c of the Act and 10 CFR Part 50, "Licensing of Production and Utilization Facilities, to possess, use, and operate the reactor at the designated location in San Ramon, California, in accordance with the procedures and limitations set forth in this license; (2) Pursuant to the Act and 10 CFR Part 70, "Special Nuclear Material," to receive, possess, and use up to 5.0 kilograms of contained uranium 235 in connection with operation of the reactor; and (3) Pursuant to the Act and 10 CFR Part 30, Licensing of Byproduct Material," (1) to receive, possess, and use a 2 curie americium-beryllium neutron startup source, and (2) to possess, but not to separate, such byproduct material as may be produced by operation of the reactor.

Amendment No. 5

C. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is authorized to operate the facility at steady state power levels not in excess of 250 kilowatts (thermal).

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 5, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

(3) Physical Security Plan The licensee shall maintain in effect and fully implement all provisions of the NRC-approved physical security plan, including amendments and changes made pursuant to the authority of 10 CFR Section 50.54(p). The approved security plan consists of the document withheld from public disclosure pursuant to 10 CFR 2.790(d), entitled Aerotest Operations, Inc. Security Plan dated August 10, 1976, submitted by letter dated October 4, 1976, as revised January 16, 1979.

D. Reports In addition to reports otherwise required under the license and applicable regulations:

(1) The licensee shall report in writing to the Commission within 10 days of its observed occurrence any incident or condition relating to the operation of the facility which prevented or could have prevented a nuclear system from performing its safety function as described in the Technical Specifications or in the Hazards Summary Report.

(2) The licensee shall report to the Commission in writing within 30 days of its observed occurrence any substantial variance disclosed by operation of the facility from performance specifications contained in the Hazards Summary Report or the Technical Specifications.

(3) The licensee shall report to the Commission in writing within 30 days of its occurrence any significant change in transient or accident analysis, as described in the Hazards Summary Report.

Amendment No. 5

( E. Records

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In addition to those otherwise required under this license and appli-cable regulations, the licensee shall keep the following:

(1) Reactor opera ting records, including power levels.

(2) Records of in-pile irradiations.

(3) Records showing radioactivity released or discharged -into the .air or water beyond the effective control of the licensee as measured at~the point of such release or discharge ..

(4) Records*of emergency reactor scrams, including reasons for emergency shutdowns.

F. This amended li" c

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ense is e ective as of the date of issuance and shall expire at midnight April 16, 2005.

FOR THE' ATO:-rrc E~mRGY co~nnssrm Karl R. Goller, Assistant Director for Operating Reactors Directorate of Lic~nsing

Attachment:

-Change No. 8 to the Technical Specifications Da*te of Issuance: October 22, 1974

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Trans. W/ Ch~nge No.

• APPENDIX A LICENSE NO. R-98 TECHNICAL SPECIFICATIONS FOR THE

. l!fWlm-1~ MlfcJIIEt(jr(Jfefs'- fIMrlrj~ !ItF/NcfJ/dii l(/JldNirt:j Name Changed to: Aerotest Radiography and Research Reactor (ARRR) 10-22-74 1.0 Definitions

1. 1 Shutdown

• The reactor, with fixed experiments in place, shall be con-sidered to be shut down (not in operation) whenever all of the following conditions have been met: (a) the console key is in the "off" position and the key is removed from

.the console.and under the control.of.a licensed ope~ator (or stored in a locked storage area); (b) sufficient control rods are inserted so as to assure the reactor is subcritical by a margin greater than 0.7% delta k/k cold, clean critical condition; (c) no work ~is in-progress involving refueling

• operations o~ maintenance of its control .rod . me~hanisms.

1.2

• Reactor Operation Reactor operation shall mean any condition wherein the reactor is not shut down.

1. 3 Operable A system or component shall be considered operable when it is capable :of performing its required function in its normal manner.*

1.4 Operating A component or system is operating if it is performing its

.required function in its* normal manner.*

1. 5

• Experiment Experiment shall mean any apparatus, device, or material installed in the core or experimental facilities (except for underwater lights, fuel storage racks and the like) which is not a normal part of these*facilities.

1.6 Experimental Facilities Exper.imentai facilities shall mean Glory Hole, vertical tubes, pneumatic transfer systems, central thimble, beam tubes, thermal column, and in-pool irradiation facilities.

1. 7 Reactor Safety Circuits

.Rea9tor-.safety.circuits shall mean those circuits, including their associated input circuits, which are designed to initiate a reactor scram.

2.1 The reac.tor and associated equipment is* located within an exclusion area, at Lhe Aefe"!.~ 13eue~m~n=R_jim~n-

• ~ c..J,1.-1"' 8~ io-CJ-Ol-7'-fx ltRRR}~gJ' 2.2 A steel, locked perimeter fence shall surround the~

facility, forming an exclusion area. The minimum distance from the center of the reactor.pool to the boundai:y of the exclus.ion area fencing shall be 50 feet. The restricted area,

.. as defined in 10 CFR 20, shall consist of the entire 'exclusion area.

2.3 The.principal activities carried on within the exclusion area t I shall be those associated with the operation of the'.~ARRR reactor and the use of a hot cell and chemistry laboratory.

3.0 Reactor Building 3.1 The reactor shall be housed in a steel building capable of meeting the following functional requirements:

3 .1.1 all circulating £ans and air cond:Ltioning systems except the system which supplies air to the control room shall have the capability to be ~hut off from a single control in the control room, j 3.1.2 ventilation shall be achieved by gravity ventilators located on the roof of the building, and \--

3.1:3 a positive air pressure shall be maintained in the 1

control room with respect to the reactor room.

I "3. 2 An alarm system shall be installed to detect unau-thorized entry into the reactor building, The alarm system shall be monitored constantly and its annun-ciation shall be tested monthly."

( 4.0 Reactor Pool (Primary System) 4.1 The minimum depth of water above the top of the active core shall be i6 ft. The maximum bulk water temperature shall be 130°F and the minimum 60°F.

4.2 The pH and conductivity of the prima.ry coolant shall be measured at least once .. each month. Corrective action shall be taken to avoid exc::eeding a pH of 7 .:S* or a conductivity of 5 umho/cm.

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5.0 Reactor Core 5.1 . Fuel Elementi:(

5.1. l The reactor shall contain :no ...in6t:e:!than::. ;::*: 90 TRIGA type :fuef elem~nts. The core sh~l.l be loaded wi.th not. more::;than 3 .30 kg of **U-235.

5.1.2 The *maximum excess reactivity above cold~ clean critical, with. or. without experiments .in place, shall be 3 dollars.

5.1.3 The bath temperature coefficient and the prompt fuel temperature coefficient shall be negative at all operating temperatures and the minimum reactivity decrement at full power shall be 80 cents when measured with.respect to source power level.

5.1.4 The coola'.nt void coefficient shall be .negative across the active core. Maximum'in-core operating void"shall be 10% of the coolant ciore volumes as defined by a cylinder ...bounded by the grid plates.

5.2 Reflector *Elements 5.2.1. The overall reflector elements' dimensions shall be the same as the fuel ~lements.

5.3 Control Elements 5.3.1 The reactor shall be subcritical by a minimum margin of 0.50 dollar.: when the maximum worth rod is fully withdrawn from the core.

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i 5.3.2 The maximum rate of reactivity addition for the control I rods shall be 11 cents/second. There shall be a mini-mum of three operable control elements. I I

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5.3.3 The total time for insertion of the control rods fol-lowing receipt of a scram signal by the safety system shall be a maximum of *600 milliseconds.

6.0 Reactor Safety Systems 6.1 The reactor safety system shal~ include sensing devices and associated circuits which automatically actuate visual and audible alarms and, when certain pr*e-set limits are ex-ceeded, scram the reactor. The systems shall be fail-safe

. (de-energizing shall cause a. scram). Table 1 describes .the minimum requirements of* the safety system.

6.2 The nuclear, process and radiation monitoring instrumentation shall provide the functions and have the set point ranges and associated annunciations listed in Table 2 of these specificat1ons.

6.3 'The safety system shall be designed such that no single I

component failure or circuit fau'it shall simultaneously

. disable both the automatic.and manual scram circuits.

6.4 Reactor sequences, interlocks and safety circuits shall I

.1 remain operable while fuel is in the core except that one channel may be removed for maintenance purposes when the reactor is shut down.

6.5 Interlocks shall _prevent safety rod withdrawal unless all of the following conditions exist: I 6.5.1 The master switch is in *the ON position; 6.5.2 The safety system has been reset;.: '"

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6.5.3 All four nuclear instruments channels are in the OPERATE mode;

• 6.5.4 The startup channel count rate is greater than 2 cps.

It shall not be possible to withdraw more than the safety rod until it has reached the upper limit interlock, at which time either the shim or regulating rod may be moved, but only one at a time.

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6.6 During a critical experiment., subcritical multiplication plots shall be obtained from at least three instrumentation channels. These* channels may be used in addition to the normal operating instrumentation in Table 1.

6.7 Process instrumentation with readout in the control room shall be operating to permit continuous indication of pool water temperature and conductivity. Alarms shall be ppe:r-abted.. to indicate low water flow, low pool water and improper location of the crane bridge.

7. 0 -Radiation Monitoring - - **

"7. l r'A~~f7i=x'=e"'id=g=a=:mm==:a=m~o'"'n""i~*t~o:r=e::::m:;;:p=lf'o-o~y=-fi=n::;:;g;;;;;;::G;::;;:e~i;::;g;;;e;;;;r=t=u~b;;;;e;;:::d;;:e;;;t=e=c=t=o=r=s==::::o====~-~*1 shall be located on the wall connecting the control room and the reactor room. This monitor shall serve .

as both an area radiation monitor and a criticality*

alarm and will annunciate through an automatic monitoring* system to th.e San Ramon, California, Fire Department and actuate a siren within the reactor building on high radiation level. The monitor shall r-:-)'. have a minimum range of 0 to 20 mr/hr. The annun-

.J, l ciation and the siren actuation shall be tested monthly."

7.2 During reactor operation, a gas sample shall be continuously withdrawn from the roof vent above .the reactor, or from the vicinity of the reactor bridge and glory hole over the reactor core, and pumped through a radioactive gas detection chamber.

The gas chamber shall be .monitored by a beta-gamma detector which shall hav~ a continuous readout in the control room.

An annunciator shall indicate when the gas exceeds 2 mr/hr.

7.3 A fission product water monitor shall be attached to the process water cleanup system 1oo*p adjacent to the deminer-alizer and shall provide continuous indication in the control room. High radiation levels within the demineralizer or

pool water shall annunciate an audible alarm on the reactor

~onsole. The range of the monitor shall be from 0.1 to 100 mr/hr.

7.4 Portable survey instruments for measuring beta-gamma dose rates *in the range of 0.01 mr/hr to 50 r/hr.shall be available at the facility.

7.5 Portable instruments for measuring fast and thermal neutron

L~---. 1 dose rates from 0.1 mrem/hr to 1.0 rem/hr *shall be*~.i *::

• I avai.lable.at the facility.

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7.6 Radiation detector packets.containing a series of threshold detectors shall be placed at several locations within the reactor building for post-accident radiation analyses.

8.0 Experimental Facilities

• 8.1 Large-Component Irradiation Box 8.1.1 A large-component irradiation box shall have a maximum volume of 20 cu. feet. The box shall encompass not more than 120° arc of the core and shall be design~d so that it can be placed no closer than 5 cm to the outer row* Of active fuel elements.

8.1.2 . The platform shall be positioned remotely relative to the reactor core by a positive drive and shall be captive to the stand which is bolted to the floor of the tank. Positive mechanical stops shall *prevent moving the experiment box into the active reactor core. 1 co2 .shall be used for purging and to maintain

• a slight positive pressure in::the box relative to* the

• pool water pressure.

8.1. 3 To remove or install the experiment box, the platform shall be moved two or more feet away from the _reactor core. The box shall then be lowered onto the platform arid bolted in place with remote handling equipment.

The voided box shall be purged of air prior to exposure to neutrons.

8.2 Pneumatic Transfer Facility 8.2.1 A pneumatic transfer facility may be located in any I reactor core position. The facility shall be operated with dry C02 and exhausted through a filter.:._,.: :: * .....

ventilation system, which is monitored for radioactivity.

I 8.2.2 The in-core,portion of the transfer facility shall I have a maximum void.volume of j4 cu. in. in the active fuel region. A manual control shall be provided which is capable of overriding the automatic timer control. f I

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l II 8.3 Glory Hole Facility 8.3.1 A dry glory hole facility may be located in any reactor I core position. The glory hole shall accept capsules to a maximum of 1.35 in. in diameter.

8.3.2 The glory hole shall be purged with co to prevent 2

I formation of excessive amounts of argon-41. Gas samples shall be taken near the pool when the glory hole facility is operated without a shield plug to insure adequate monitoring of radioactive gases.

8.4 Neutron .Radiography*: Facility 8.4.1 The beam tube shall consist of a two-section tapered tube having a rectangular cross section. The upper and lower sections of the tube shall be equipped with a fill and drain line.

8.4.2. All.components contacting the pool water shall be fabricated from aluminum or stainless steel.

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. 7 "8. 4. 3 Th*e beam catche::- shield shall consist of a movable radiation shield." c,Me:,,,1 o

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. 8. 5 Thermal Column * /

8.5.l The thermal column shall be positioned remotely on steel locating pins immediately adjacent to the reactor

• core.

8.5.2 The thermal column shall be composed of a three-foot cube of graphite encas~d in aluminum containing five rows of 1. 5 in. diameter irradiation holes. The rows shall be placed 6 inches apart and contain seven holes per row.

Slotted beams shall ,.be provided to allow experiments to be attached directly to the thermal column.

8.6 Vertical Tube 8~6.1 Vertical irradiation tubes, having diameters up to 6 in **

may be attached to the thermal column.

8.6.2 The ve'rtical tube shall be purged with co2 to prevent*

the formation of excess amounts of argon-41.

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8.7 Other Irradiation Facilities 8.7~1 The central 7 fuel elements of the reactor may be removed from the core and a central irra~iation facility installed provided the cross-szctional area-of the facility does not exceed 16 in *

8. 7 .2 Two triangular exposure facilities are available which shall allow the insertion of circular experiments to a maximum of 2.35 in. diameter or triangular experiments to a maximum of 3..0 in. on aside.

8.7.3 Irradiation capsules in the shape of dummy fuel elements shall have a maximum inner void volume of 34 cu. in.

in the active fuel region.

9.0 Experiment Limitations 9.1 Experiments *shall be evaluated in the most reactive condition.

9.2 The documentation of experiments, which shall be reviewed and approved prior to insertion in the reactor, shall include at least:

9.2.1 The purpose of the experiment; 9.2.2 A description of the experiment; and .

9.2.3 An analysis of the possible hazards asso_datedwith the performance of the experiment.

9.3 The value of the reactivity worth of any single ind~pendent experiment shall not exceed 2 d.ollars. If such experiments are connected or otherwise related so that their combined reactivity could be added to the core simultaneously, their combined reactivity shall not exceed 2 dollars.

9.4 The reactivity worth of any single independent experiment not.rigidly fixed in place shall not exceed 1 dollar~ If such experiments are connected or otherwise related so that their combined reactivity could be added to the core simul-taneously, their combined reactivity worth shall not exceed 1 dollar.

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. 9.5 No experiment shall be installed .in the reactor in such a manner that it could shadow the nuclear instrumentation system monitors.

9.6 No experiment shall be installed in the reactor in such a manner that a failure could in.terfere with the insertion

• of a reactor control element.

9.7 No experiment shall be performed involving materials which coulfi: .f

• 9.7.1 Contaminate the reactor pool causing corrosive action on the reactor components or experiments; 9.7.2 Cause excessive production of airborne radioactivity; or 9.7.3 Produce an uncontained violent chemical reaction.

9,8 Experiments shall not be perforined involving eq~ipment whose failure could result in fuel element damage.

9.9 The amount of special nuclear material contained in an experi-ment shall be limited to 5 grams in the form of solid samples or 3 g*7ams in the form .of liquid. Liquid 'special nuclear materii ls shall be doubly encapsulated.

9 .10 Experin. mts having moving parts shall be designed to have reactiv'ty insertion rates less than 10 cents/sec except that mo~ ing parts worth less than 5 .cents may be oscillated

-- or removed at higher frequencies.

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119.11* Solid e:-.plosive materials may be brought int:o the facility for the.purpose of being radiographed in the neutron radiography facilities located above the pool, provided that the following conditions are met:

9 .11. l Individual explosive devices shall be limited to 1000 grains equivalent TNT encased in metallic sheathing.

9.11. 2 The maximum quantity of explosive material that*may be possessed at.one time shall be limited to 50 pounds equivalent TNT.

9 .11.) :Sxplosive material shall be stored in

'.esignated areas within the reactor facility.

. 9.11.3.1 Only the explosive devices to be radiographed within 4 hrs, not to*

exceed a maximum of ten pounds j~f; 411 ...

. q)1.1 equivalent TNT, may be removed from the storage area at one time for radio graphing, including preparation but excluding.packaged shipments.

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9.11.3.2 .An accountability log shall be maintained to show the amount of explosive material in the reactor facility tft all times' and shall contain a description of the explosive, and the location within the facility (e.g., storage; radiographing facility, or shipping dock).

9.11.4

• The maximum amount of explosive material contained in devices that may be placed in the radiography facilities a.t .a time shall be limited to five pounds equivalent TNT.

9.11.4.1 Explosive material in the radiation

(~ field at one time shall be limited . .

to 1 pound equivalen~ TNT.

9 .11. 4. 2 Explosive material cot tained in

• 1ong device(s) shall b ~ limited to 0,5 pound. equivalen TNT per.

• foot."

"9.12 Personnel handling the explosive devices shall be trained and familiar with the devices being radiographLd.

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9.12.l Personnel handling the explosive devices shall c~~

use *special equipment, such as no;isparking .tools. it\;. \

()": ~111 and shoes, protective clothing, safety shields and grounded benches as required for. the explosives being handled.

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9.12.2 Vnshielded high frequency generating e~uipment shall not be operated within 50 feet of any e ..;:plosi've device.

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9.12.3 The explosive dev:'.ces shall be subjected to a

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9.12.4 total exposure no:: to exceed 3 x loll neutrons/ cm 2 and 3 x 10 3 roen t :.-. ens of gammas.

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Explosive de~ices that, upon ignition, have or provide a thrus.t ~en a definite direction shall be positioned so as :..o be. aimed a1Na"j from the reactor and components. 11 ' * ~

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i 10.0 General 0perating Limitations

10. l Rea.c tor operation shall be pei:::1i tted only when two or more personnel are in the reactor l~ilding, at least one of whom is a licensed Operator.

10. 2 The rca-ctor shall not be op er: ::cd wherever there are: significant defects in fuel elements, control rods or control circuitry.

l 10.3 l!pon occurrence of abnormal or,::r~;.i.on of the* reactor, including its controls, safety systems ~~d auxiliary systems, action shall be taken irnmed:i.ately *to secure the safety of the facility and determine the cause of *th* abnormal behavior. I 11.0 Fuel Storage and Transfer

11. l The fuel storage pits located '.n the floor of the reactor room shal 1 accommodate a maxir:. m of 19 fuel elements (700 gm U-235) in storage racks dr) or flooded with water. The fuel storage pits thall be SCt!red with a lock and chain except during fuel transfer o~;rations.

11.2 Add~tional fuel st6rage racks may be located in the rea~tor tank. Each of these storage facilities shall be so des1 gned thatpfor .all conditions of moderation keff shall not exceed a value of 0.8.

11. 3 A fuel handling tool shall be used in transferring fuel ele-ments. *of low radioactivity bet;..*een ::he storage pits and the reactor; a shielded fuel tranrf~r cask shall be used for the transfer of highly radioactive fuel elements. The fuel handling) tool shall remain in a locked .:..lbinet under the cognizance of  !

the Reactor Supervisor when nc~ authorized for use.

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)<r Amendment. No. 4

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11.4 All fuel transfers in the reactor tank shall be conducted by a minimum staff of three men, and shall include a licensed Senior Operator and a licensed Operator. The staff members shall monitor the operation using appropriate radiation monitoring instrumentation. Fuel transfers outside the reactor tank but within the facility shall be supervised by a licensed Operator.

11.5 Not more than one fuel element shall be allowed in the facility which is not in storage or in the core lattice.

12.0 Administrative Requirements 12.1 Organization 12.1.1 The Reactor Supervisor shall have responsibility of the reactor facility. In all matters pertaining to reactor operations and to these Technical Specifications, the Reactor Supervisor shall be responsible to the President, Aerotest Operations, Inc. The President, Aerotest Operations, Inc. shall report to the Board of Directors of Aerotest Operations, Inc.

12.1.2 The Radiological Safety Officer shall review and approve all procedures and experiments involving radiological safety. He shall enforce rules, regulations and procedures relating to radiological safety, conduct routine radiation surveys and is responsible to the Manager, Aerotest Operations.

12.1.3 The Reactor Safeguards Committee shall be composed of not less than five members, of whom no more than three are members of the operating organization. The committee shall meet on call of the chairman and they shall meet at least annually. The committee shall be responsible for, but not limited to the following:

12.1.3.1 Reviewing and approving nuclear safety standards associated with the use of the facility; 12.1.3.2 Reviewing and approving all proposed experiments and procedures and changes thereto, and modifications to the reactor and its associated components; Amendment No. 5

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12.1.3.3 Determining whether proposed experiments, procedures or modifications involve unreviewed safety questions; as defined in 10 CFR 50, Part 50.59(c), and are in accordance with th~se Technical Specifications; 12.1.3.4 Conducting periodic audits of procedures, reactor operations and maintenance, equipment performance, and records; 12.1.3.5 Reviewing all reported abnormal occurrences arid violations of these Technical Specificationsp evaluating the causes of suc.h events and the corrective action taken and recommending measures to prevent reoccurrence and; 12.1.3.6 Reporti~g their findings and recommendations cha .*-5 concer~ing ~he above to the Manager, Aerotest .u.i+~').O:{O Op er a tions .  ;.{'}A/-  : I 12.1.4 The Reactor Supervisor shall have a Bachelor's degree

' ( in Engineering or Physical Science and shall have a minimum of 4 years experience in the operation of a nuclear facility during which he shall have demonstrated I

.t'l comRetence in supervision and reactor operations. He shall hold a Senior Reactor Operator license for the facility. I I 12 .* 1.5 The Radiological Safety Officer shall hav*e a Bachelor 1 s degree in 'Biological or Physical Science and shall '!

have a minimum of 2 years experience in personnel and envirorimental radiation monitoring programs at a J nuclear facility. Certification as a Health Physicist by the Health Physics Society is acceptable in lieu of the education and experience requirements given above, I

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12.2 Procedures

I 12.2.1 Detailed written procedures shall be provided and -!

followed for the following reactor operations: J:1 12.2.1.l Normal startup, operation and shutdown of the complete facility and of all systems and components involving nuclear safety of the facility.

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12~2.l.2 Refueling operations.

12.2.1.3 Actions to be taken to correct specific and foreseen potential malfunctions of systems or components, including responses to alarms, suspected primary system leaks and abnormal reactivity changes.

12.2.1.5 Preventive or corrective maintenance opera-tions which could have an effect on the safety of the reactor. I

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12.2.2 Temporary procedures which do not change the intent of previously approved procedures may be utilized on approval by a licensed Senior Reactor Operator and one other qualified individual. Such procedures shall be subsequently reviewed by the Reactor Safe-guards Committee.

12.3 Records In addition to those records required under the facility license and applicable regulations, the following records shall be kept when explosive materials are to be irradiated or radiographed:

12.3.1 Ahe type and quantity of material ir~adiated.

12.3.2 ~ate, time of day, and length of exposure.

12.3.3 Total neutron and gamma exposure level.

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TABLE .l NUCLEAR INSTRUMENTATION Channel Detector *- Minimum Information Mii1imum Range Infotma t ion to (No.) Sensitivity Logic Element (scram)

Startup BF3 4.5 counts/sec per Neutron flux, source lev_el to Peri~~ s.cram; (a)*

{l) Proportional n/cm 2 -sec *. period* 1 watt low count rate Counter scran Log N Compensated 4 x 10-14 amp/n/ Pm~er level, 10-2 watts to Period scram (2) ion chamber cm 2 -sec

• period- 120% full power.

Linear Uncompensated 4.4 ~ 10-14 amp/* Poiler*level 30 watts to. High Cnd low Level ion chamber n/cm -sec 120% full power level b) scrams Safety (3)

Linear Compensated 4.4 x 10-14 amp/ Power* level 10-1 watts to High and low Level ion chamber n/cm 2 -sec 120% .full power level scram Safety (4)

(a) Scram8 on Channel 1 are by-passed when signal on Channel 2 exceeds a fixed setting similarly the high voltage is removed from the detector and the detector is shorted. ** -'7-(b) Low level scram is bypassed o.n Channel 3 and 4 when Channel 2 is below**& fixed setting

• i I

I TABLE 2 .r SAFETY SYSTEM FUNCTIONS I!

t.

No. of Switches Annunciator a~d Annunciator and I Sensor or Tri Device or Sensors Scram Set Poi*t Alarm Set Point "I

Short Period; .Chs. l. 2

• High Neutron Flux

• 2 > 3 sec.

r r*.

_'. l Level; Chs. 3, 4 2 ~ 98'7. ~f full scale and not greater than 1201.

full power

• High Temperature of

• Coolant Water l 1

Low Pool Water Level l <1 ft max decrease *

• j Seismic Disturbance l IV on modified Mercalli Sc;ile

• Briczo Crane Location 1 max.

When located of£ i I

• storage poa i tion i I

\ t Lo._~ :~eu tr on De tee tor Voltage; Chs. 2, 3, 4 3 > 500 volts rI I

I

)

Low* Source Level; Ch. l 1  !  ;::. 2 cps 1

)

Loss of Instrument Power; )

I r

Ch. 2, l II x l

Low Neutron Flux; Ch. 3 ~5% of full

&4 2 ) *scale

\,

.,I

( ....

Area Radiation Monitor 1 I S 10 mr/hr Water Radioactivity 1 S20 mr/hr

.Demineralizer Water Flow l ~4 gpm Building Gas Effluent Monitor 1 ~ 2 mr/hr Master Key Switch 1 Not on "ON

position Manual Scram Button l Button .Depressed