ML14164A710
| ML14164A710 | |
| Person / Time | |
|---|---|
| Site: | Aerotest |
| Issue date: | 06/13/2014 |
| From: | NRC/OGC |
| To: | Atomic Safety and Licensing Board Panel |
| SECY RAS | |
| References | |
| RAS 26037, ASLBP 14-931-01-LT-BD01, 50-228-LT | |
| Download: ML14164A710 (16) | |
Text
Trans. W/ Ch9nge No. 15&
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APPENDIX A LICENSE NO. R-98 TECHNICAL SPECIFICATIONS FOR THE IJffiWft¥-IC/INftitii.JJ Mr1ctiiF1C/J1Jict~ /Jittiilf~ /JMNritmt /(/J/ritMtt 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 operator (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 or maintenance of its control rod mechanisms.
1.2 Reactor aperation 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.
,.
.
- - j 1.6 Experimental Facilities Experimental 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 Reactor safety circuits shall mean those circuits, including their associated input circuits, which are designed to initiate a reactor scram.
2.0 Reactor Site 2.1 The reactor and associated equipment is located within an exclusion area, at: the Aeroj&j: Gene~l C.e:r:poraM-Oa,-San=Rilm<m-
- Plant.. ~, 8'.1 I 0 c:l. -7 '{ J(
2.2 A steel, locked perimeter fence shall surround the ~~I~R}~g" facility, forming an exclusion area. The minimum distance from the center of the reactor.pool to the boundary of the exclusion 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 ! I shall be those associated with the op~ration 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 fans and air conditioning systems except the system which supplies air to the control room shall have the capability to be shut off from a single control in the control room, 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 control room with respect to the reactor room.
"3.2 An alarm system shall be installed to detect l,Jnau-thorized entry into the reactor building. The alaro system shall be monitored constantly and its annun-ciation shall be tested monthly."
i li.
- 4.0 Reactor Pool (Primary System) 4.1 The minimum depth of water above the top of the active core shall be 16 ft. The maximum bulk water temperature shall be 1300F and the minimum 60°F.
- 4. 2 The pH and conductivity of the primary coolant shall be measured at least once each month. Corrective action shall be taken to avoid exceeding a pH of 7.5 or a conductivity of 5 umho/cm.
5.0 Reactor Core 5.1 Fuel Elements*
5.1.1 The reactor shall contain :no more::than:.: .: 90 TRIGA type fuel elements. The core shall be loaded with 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 coolant void coefficient shall be negative across the active core. Maximum in-core operating void-shall be 10% of the coolant core 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 elements.
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.
5.3.2 The maximum rate of reactivity addition for the control rods shall be 11 cents/second. There shall be a mini-mum of three operable control elements *
- 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 shall include sensing devices and associated circuits which automatically actuate visual and audible alarms and, when certain pre-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 specifications.
6.3 'The safety system shall be designed such that no single component failure or circuit fault shall simultaneously disable both the automatic and manual scram circuits.
6.4 Reactor sequences, interlocks and safety circuits shall 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:
6.5.1 The master switch is in the ON position; 6.5.2 The safety system has been reset; 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 *
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 9per-abLed to indicate low water flow low pool water and improper location of the crane bridge. '
- 7. 0 Radiation Moni taring ----
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shall be located on the wall connecting the control room and the reactor room. This monitor shall serve .
1/ as both an area radiation monitor and a criticality alarm and will annunciate through an automatic monitoring*system to the San Ramon, California, Fire Department and actuate a siren within the reactor building on high radiation level. The monitor shall have a minimum range of 0 to 20 mr/hr. The annun-ciation and the siren actuation shall be tested J 1 (~()tfGl "ld.'-tW-jV 5 r.wn th l y. " ~e~ 3
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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 chamb~r 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 loop 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 console. 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 dose rates from 0.1 mrem/hr to 1.0 rem/hr *shall be~:,, ,.*,
- available.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 designed so that it can be placed no closer than 5 em 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. 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 and 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 reactor core position. The facility shall be operated with dry C~ and exhausted through a filter * . .. ...
ventilation system, which is monitored for radioactivity.
8.2.2 The in-core portion of the transfer facility shall have a maximum void volume of 34 cu. in. in the active fuel region. A manual control shall be provided which is capable of overriding the automatic timer control.
'
8.3 Glory Hole Facility 8.3.1 A dry glory hole facility may be located in any reactor 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
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 .
- *8.5 "8.4.3 Tl\*e beam catcher shield shall consist of a movable radiation shield."
Thermal Column /
8.5.1 The thermal column shall. be positioned remotely on steel locating pins immediately adjacent to the reacto,r core.
8.5.2 The thermal column shall be composed of a three-foot cube of graphite encased 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 a.. 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 C02 'to prevent.--
the formation of excess amounts of argon-41 *
- . 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 irradiation facility installed provided the cross-s~ctional 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 a side.
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 associated with the performance of the experiment.
9.3 The value of the reactivity worth of any single independent experiment shall not exceed 2 dollars. 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 *
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 interfere with the insertion of a reactor control element.
9.7 No experiment shall be performed involving materials which could: _,
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 performed 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*~ams in the form of liquid. Liquid special nuclear materi< 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 roo* ing parts worth less than 5 cents may be oscillated or removed at higher frequencies *
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"9.11* Solid e~.plosive materials may be brought J.nr: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:
9.11.1 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;3 ?.xplosive material shall be stored in
-~esignated areas within the reactor facility *
9.11.3.1 Only the explosive d~vices to be radiographed within 4 hrs, not to exceed a maximum of ten pounds equiv~lent TNT, may be removed from the storage area at one time for radiographing, including preparation but excluding packaged shipments.
9.11.3.2 An accountability log shall be maintained to show the amount of explosive material in the reactor facility at all times, arid 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 £acilities at a time shall be limited to five pounds equivalent TNT.
- 9.11.4.1 9.11.4.2 Explosive material in the radiation field at one time shall be limited' to 1 pound equivalent TNT.
Explosive material cot tained in long device(s) shall b1 limited to 0.5 pound. equivalen TNT per
- foot."
"9.12
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Personnel handling the explosive devices shall be trained and familiar with the devices being radiographtd.
' !1 9.12.1 Personnel handlin~ the'explosive devices shall C~9 .
use special equipment, such as no~sparking tools . ttl_ / 11 and shoes, protective clothing, safety shields and grounded benches as required for the explosives being handled
- v"
~ ~1
- 9.12.2 Pnshielded high frequency generating e~uipment shall not be operated within 50 feet of any L{plosive
- device.
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- ll 9.12.3 The explosive dev~ces shall be subjected to a total exposure no*: to exceed 3 x loll neutrons/cm2 and 3 x 103 roent,.-~ns of gammas.
~ *~
9.12.4 Explosive devices that, upon ignition, have or provide a thrust :en a definite direction shall be positioned so as ~o be.aimed a~ay~from the reactor and components. 11 ' ~ .
.~~:===-==============~;
1 0.0 General Operating Limitations 10,1 Reactor operation shall be pe;: :*itted only when two or more personnel are in the reactor LJilding, at least one of whom is a licensed Operator.
10.2 The rc_a_c tor shall not be oper: ::cd wherever there are fl ignificant defects in fuel elements, con:col rods or control circuitry.
10,3 Upon occurrence of abnormal or~r~;i~n of the* reactor, including its controls, safety systems ~~d auxiliary systems, action shall be taken immediately to jecure the safety of the facility and determine the cause of th* abnormal behavior. I
. 11.0 Fuel Storage and Transfer 11.1 The fuel storage pits located *.n the floor of the reactor room shall acconwodate a maxir: m of 19 fuel elements (700 gm U-235) in storage racks dr) or flooded with water. The fuel storage pits shall be set* red with a lock and chain except during fuel transfer Of *,rations.
11.2 Additional fuel storage racks may be located in the rea~tor tank. Each of these storage facilities shall be so des1gned thatpfor all conditions of moderation keff shall not exceed a va1ue of 0. 8.
11.3 A fuel handling tool shall be used in transferring fuel ele-ments. of low radioactivity bev~*aen the storage pits and the reactor; a shielded fuel tran:i~r cask shall be used for the transfer of highly radioactive fuel elements. The fuel handling) tool shall remain in a locked ;:..1binet under the cognizance of '
the Reactor Supervisor when net authorized for use.
(~
I )
,
Amendment No. 4
.... JAN 2 8 198'1 r
~*--
- 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 me~bers 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 snall be allowed in the facility which is not in storage or in the core lattice.
12.0 Administrative Requirements 12.1 Organization I
12 .1.1 The Reactor Supervisor shall have responsibility of the reactor facility. In all matters.pertaining to ~
9
- reactor operations and to these Techn1cal Specifications, *AI the Reactor Supervisor shall be responsible to the ~1 :.- A".
P res:"d ~nt, Aerotcst Operations, Inc., a wholly-0\,'ned 1't'\~'\*
li '> 1
(
\ subs1d1ary of Explosive Technology, Inc. The President, \0.1- I 1
Aerotest Op~rations, Inc. shall report to the Board of Directors of Aerotest Operations, Inc. which includes the Presidents of both OEA, Inc. and Explosive Technology I
11 1
- rnc. ' J.
The Radiological Safety Officer shall review and approve all procedures and experiments involving radiological safety. He shall.enforce rules, regulations and procedures relating to radio-logical safety, conduct routine radiation sur-veys and is responsible to the hanager, Aerotest Operations."
12 .1. 3 The Reactor Safeguards Committee silall 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 corr~ittee 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; I
12.1.3.2 Reviewing and approving all proposed experi-
' ments and procedures and changes thereto, and modifications to the reactor and its associated components;
12.1.3.3 Determining whether proposed experiments, procedures or modifications involve unreviewed safety questions, as defined in 10 CFR SO, Part 50.59(c), and are in accordance with these 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 <~
and violations of these Technical Specifications, \. f;j (
evaluating the causes of such events and the 1? ~
corrective action taken and recommending e~~P'o measures to prevent reoccurrence and; ~ 1 12.1.3.6 Reporting their findings and recommendations rJa .*-5 concerning the above to the Manager, Aerotest u} J.,.'J.o:f 0
\ Operations." * .,IU-i'l 12.1.4 The Reactor Supervisor shall have a Bachelor's degree
/*(A 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 comP.etence in supervision and reactor operations. He shall hold a Senior Reactor Operator license for the /
/ facility.
12.1.5 The Radiological Safety Officer shall have a Bachelor!s degree in Biological or Physical Scierice and shall have a minimum of 2 years experience in personnel and environmental radiation monitoring programs at a 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'**
12.2 Procedures 12.2.1 Detailed written procedures shall be provided and followed for the following reactor operations:
12.2.1.1 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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- 12.2.1.2 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.
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 Date, time of day, and length of exposure.
12.3.3 Total neutron and gamma exposure level *
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TABLE .1
- NUCLEAR INSTRUMENTAnON Chan:1el Detector - Minimum Information Minimum Range Information to (No.) Sensitivity Logic Elem~nt (Scram)
Startup BF3 4.5 counts/sec per Neutron flux, source lev_el to Peri~d s~ram;(a)
(1) Proportional n/cm2-sec period 1 watt low count rate Counter scre.m Log N Compensated 4 x 10-14 amp/n/ Power level, lo- 2 watts to Period scram (2) ion chamber cm2 -sec period- 120'7. full power Linear Uncompensated 4.4 ~ lo-14 amp/ Po*,..er level 30 watts to High {nd low Level ion chamber n/cm -sec 120% full power level b) scrams Safety (3)
Linear Compensated 4.4 X 10-l4 amp/ Power level 10-l watts to High and low Level ion chamber n/cm 2 -sec 120'7. full power level scram Safety (4)
(a) ScramS 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. -- rc--
(b) Low level scram is bypassed on Channel 3 and 4 when Channel 2 is below a fixed setting.
TADLE 2 SAFETY SYSTEM FUNCTIONS No. of Switches Annunciator a~d Annunciator and Sensor or Tri Device or Sensors Scram Set Poi*t Alarm Set Point Short Period; Chs. 1, 2 2 > 3 sec.
High Neutron Flux Level; Chs. 3, 4 2 ~ 987. of full scale and not greater than 1204 full power High Temperature of Coolant Water 1 Low Pool Water Level 1 <1 ft max decrease Seismic Disturbance 1 IV on modified Mercalli Scale max.
Bricz~ Crane Location 1 When located off storage position LO'.! :\eu tron De tee tor Voltage; Chs. 2, 3, 4 3 ~ 500 volts f
(
Low Source Level; Ch. 1 1 I ~ 2 cps Ii Los~ of Instrument Power; ?
!
Ch. 2, 1 X Low Neutron Flux; Ch. 3 ~54 of full
&4 2 scale
.,
Area Radiation Monitor 1 ~ 10 mr/hr
\-later Radioactivity 1 .S20 mr/hr Demineralizer Water Flow 1 ~4 gpm Building Gas Effluent Monitor 1 ~ 2 mr/hr
- Master Key S*..ritch 1 Not on "ON" position Manual Scram Button 1 Button Depressed