ML20065H204
| ML20065H204 | |
| Person / Time | |
|---|---|
| Site: | Dow Chemical Company |
| Issue date: | 10/15/1990 |
| From: | DOW CHEMICAL CO. |
| To: | |
| Shared Package | |
| ML20065H201 | List: |
| References | |
| NUDOCS 9010260014 | |
| Download: ML20065H204 (45) | |
Text
{{#Wiki_filter:, DOW TRIGA RESEARCH REACTE] Updated version of the Technical Specifications as it would appear with the proposed changes, s k 9010260014 901015 DR ADOCK 0500 g4 l i
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e TECHNICAL SPECIFICATIONS FOR THE DN1 TRI' 1ESEARCH REACTOR FACILITY LICENSE R-108 OCTOBER 1990 This document includes the Technical Specifications and the bases for the Technical Specifications. The bases provide the technical support for the individual Technical Specifications and are included for information purposes only. The bases are not part of the Technical Specifications and they do not constitute limitations or requirements to which the licensee must adhere.
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- 1. DEFINITIONS f
1.1. ALARA - The ALARA (As Low As Reasonably Achievable) program is a set of procedures which is intended to minimize occupational exposures to ionizing radiation and releases of radioactive materials to the environment. 1.2. Channel - A channel is a combination of sensors, electronic circuits, and output devices connected by the appropriate communications network in order to measure and dispisy the value of a parameter. 1.3. Channel Calibration - A channel calibration is an adjustment of a channel such that its output corresponds with acceptable accuracy to known values of the parameter which the channel measures. Calibration shall encompass the entire channel, including equipment, actuation, alarm, I or trip and shall include a Channel Test. 1.4. Channel Check - A channel check is a qualitative verification of acceptable performance by observation of channel behavior. The verification shall include comparison of the channel with other independent channels or systems. measuring the same variabae, whenever possible. 1.5. Channel Test - A channel test is the introduction of a signal into a channel for verification vi the operability of the channel. 1.6. Confinement - Confinement-is an enclosure of the facililty which controls the movement of air into and out of the facility through a' controlled path. 1.7. : Excess Reactivity - Excess reactivity is that amount of ! reactivity that would exist if all control rods were moved to the maximum reactive position.from the condition where the reactor is exactly critical. 1.8. Experiment - An experliaent is any device or material, not
- normally part of the reactor, which is' introduced into the reactor for the purpose of exposure to radiation, or any operation'which is designed to investigate non-routine i.- reactor characteristics.
1.9. Experimental Facilities include the rotary specimen rack, y; vertical tubes, pneumatic transfer systems, the central thimbio, and the area surrounding the core. Amendment No. 6 h h
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[. L 1.10. Limitino Conditions for operation - Limiting conditions for Operation (LCO) are administratively established constraints on equipment and operational characteristics l which shall be adhered to during operation of the reactor. 1.11. Limitino Stfety System Settino (LSSS) - An LSSS is the actuating level for automatic protective devices related to those variables having significant safety functions. 1.12. Measured value - A measured valuc is the value of a parameter as it appears on the output of a channel. 1.13. Modified Routine Experiments - Modified routine experiments are experiments which have not been designated am routine experiments or which havs not been performed previously, but are similar to routine experiments 1*. that the hazards are neither significantly c' 'arent fre.n nor greater than the hazards of the corre rout'ne experiment. 1.14. Movable Experiment - A movabl. .periment is an experiment intended to be moved in or near tre core or into and out of the reactor while the reactor is operating. 1.15. Operable - A component or system is operable if it is capable of performing its intended function. i i- 1.16.~QEgratino - A component or system is operating if it is performing its intended function. 1.17. Radiation Safety Committee (RSC) - The RSC is chartered by The Dow Chemical Company to be responsible for the license for the Dow TRIGA Research Reactor facility.
.1.18. Reactivity Limits - The reactivity limits are those limits imposed on reactor core excess reactivity.
referenced to a Reference _ Core Condition. . Quantities are-3 1.19. Reactivity Worth of an Experiment - The reactivity worth of 'j an experiment is the maximum absolute value of the .I reactivity change that would occur as a result of intended or anticipated changes or credible malfunctions that alter experiment position or configuration.
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1.20. Reactor operatino - The reactor is operating whenever it is. l not secured or' shutdown. -- 1.21. Reactor Safety Circuits - Reactor safety circuits are those circuits,. including the. associated input circuits, which - are designed to initiate a reactor scram. Amendment No. 6-L- l 1 SE
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1.22. Reactor Secured - The reactor is secured whenever: a) it contains insufficient fissile naterial precent in the reactor, adjacent experiments or control rods, to attain criticality under optimum available conditions of moderation and reflection, or b) the console switch is in the "off" position, the key is removed from the switch, and the key is in the control of a licensed reactor operator or stored in a locked storage areat and sufficient control rods are inserted to assure that the reactor is suboritical by a margin greater than $1.00 cold, without xenon; and no work is in progress involving core fuel, core structure, installed control rods or control rod drives unless those drives are physically disconnected from the control rods; and no experiments in or near the core are being moved or serviced that have, on movement,.a reactivity worth exceeding $0.75. 1.23. Reactor Shutdown - The reactor is shutdown if it is
- suberitical by at least one dollar.and the reactivity worth of all experiments is accounted for.
l 1.24'. Reactor Operations committee'(ROC) - The ROC is charged with direct oversight of the reactor; operations, inc3uding both review and-audit functions.
. 1.25' Reactor Safety Systems - Reactor Safety Systems are those systems, including associated input channels, which are designed to' initiate automatic reactor protection or to provide information for initiation of manual. protective action.
4 1.26. Reference Core Condition - The Reference Core Condition is n 'that condition when the core is at ambient temperature (cold) and the reactivity worth of xenon in the fuel is negligible (less than S.30), a e Amendment No. 6 9
w y 4 [ t 1.27. Research Reactor - A Research Reactor is a device designed to support a self-sustaining nuclear chain reaction for , recearch, development, education, training, or experimental purposes, and which may have provisions f or the production of radioisotopes. . 1.28. Reportable Occurence - A Reportable Occurence is any of the following which occurs during reactor operationt , a) Operation with actual safety-system settings for required systems less conservative than the limiting safety-system settings specified in Technical , Specification 2.2. b) Operation in violation of limiting conditions for operation established in the Technical Specifications. c) A reactor safety system component malfunction which renders or could render the reactor safety system incapable of performing its intended safety function unless the malfunction or condition is discovered during maintenance tests or periods of reactor shutdown. d)- Any unanticipatsd or uncontrolled change in reactivity : greater than one dollar. Reactor trips resulting from ( a known cause are excluded, t e) Abnormal and significant degradation in reactor fuel, cladding, or coolant boundary which could result in exceeding prescribed radiation exposure or release limits. f) An observed inadequacy in the implementation of either > administrative or procedural controls which could result in operation of the reactor outside the limiting conditions for operation. g) Release of radioactivity from the site above limits ~ specified in 10CFR20, 1.29. Rod,-Control - A control rod is a device containing neutron absorbing material which is used to control the nuclear fission chain reaction. The control rods are coupled-to: the control rod drive systems in a way that allows the.
-control rods to perform a safety' function.
I Amendment No. 6. i y
4 b v 1* a. l 1.30. Routine Experiment - A routine experiment is an experiment which involves operations under conditions which have been extensively examined in the course of the reactor test prograne and which is not defined as any other kind of experiment. Experiments and classes of experiments which I- are to be considered as routine experiments must be so defined by the Reactor Operations Committee, 1.31. Safety Limit - A Safety Limit is a limit on an important process variable which is found to be necessary to reasonably protect the integrity of certain of the physical barriers which guard against the uncontrolled release of l radiaoctivity. The principal physical barrier is the fuel elenent cladding. 1,32. Scram Time - Scram Time is the tine required to fully insert the control rods following the actuation of a Limiting. Safety System Setting. 1.33. Secured Experiment - A Secured Experiment is any expe rinent, experimental facility, or component of an experiment that is held in a stationary position relative to the reactor by mechanical means. The restraining forces must be substantially greater than those to which the experinent might be subjected by hydraulic, pneumatic, buoyant, or other forces which are normal to the operating environment of the experiment, or by forces which can arise as the result of credible nelfunctions. 1.34. Shall, should, and May - The word "shall" is used to denote a requirement, the word "should" denotes a recommendation, and the word "may" denotes permission, neither a requirement nor a recommendation. 1.35. Shutdown Marcin - Shutdown' Margin is the reactivity existing when the most. reactive control rod is-fully withdrawn from the core and the other control rods are fully inserted into the core. 1.36. Special Experiments - Special experiments are experiments-which are neither routine experiments nor modified routine experiments. ~
.1.37. TRIGA Fuel Element - A TRIGA fuel element is a sealed unit
'containing (U, Zr) Hx fuel for the reactor. The uranium is enriched to less than 20% in 235-U and the fraction of hydrogen'is in the range of 1.0-1.1 for aluminum-clad TRIGA elements and in the range of 1.6-1.7 for stainless-steel-clad TRIGA elements.
Amendment No. 6
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- 2. SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 2.1. Safety Limit (SL)
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Applicability , This specification applies to the temperature of the . reactor fuel. : Obiective ! The objective of this specification is to define the maximum fuel temperature that can be permitted with confidence that no damage to the fuel element will result. Specification
. .The temperature in any fuel element in the Dow TRIGA Research Reactor shall not exceed 500 C under any conditions of operation.
Beste ! A loss in the integrity of the fuel element cladding could arise from a buildup of excessive pressure i between the fuel and the cladding if the fuel ) temperature exceeds the safety limit. The pressure is caused by the heating of air, fission product gases, and hydrogen from the dissociation of the fuel- i moderator. .The magnitude of this pressure is determined by the temperature of the fuel element and by the hydrogen content._ Data indicate.that the stress in.the cladding due to, hydrogen pressure from the dissociation of ZrHl.6 will remain below the ultimate ; stress provided.that the fuel temperature does not exceed 1050 C and the fuel cladding temperature does not exceed 500 C. . When the cladding temperature can . equal'the fuel temperature the' fuel temperature design .t limit is 950 C (M. T. Simnad,,G.A. Project No.'4314, y Report e-117-833, 1980). Experience with: operation'of TRIGA-fueled reactors-at' power levels up to 1500 kW shows no damagesto the fuel [ due to thermally-induced pressures.
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The thermal characteristics of aluminum-clad TRIGA fuel elements using ErHg,1 moderator have been analyzed (S. C. Hawivy and R. L. Kathren, NUREG/CR-2387, PNL- , 4028, credible Accident Analyses for TRIGA and TRIGA-fueled Reactors, 1982). A loss-of-coolant analysis ) showed that in a typical graphite-reflected Mark I , TRIGA reactor fueled with 60 aluminum-clad fuel l elements (Reed College) the maximum fuel temperature would be less than 150 C following infinite operation l at 250 kilowatts terminated by the instantaneous loss l of water. These temperatures are well below the region t where the a + 6 + 7' to a + 6 phase change occurs in trH1,1 (560 C). 2.2. Limitino Safety System Settinos (tSSS) f boplicability
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This specification applica to the reactor scram setting which prevents the reactor fuel temperature from
- reaching the safety limit.
i obiective , The objective of this specification is to provide a < reactor scram to prevent the safety limit from being reached. Specification
'The LSSS shall not exceed 300 kW as measured by the calibrated power channels. ,
l Basis The LSSS which does not exceed 300 kW provides a considerable safety margin. One TRIGA reactor (General i Atomics, Torrey Pines) showed a maximum fuel temperature of 350 C during operation at 1500 . kilowatts, while a 250-kilowatt TRIGA reactor (Reed l College) showed a maximum fuel temperature of less than 1 150 C (reported by S. C. Hawley, R. L. Kathren, ll NUREG/CR-23B7, PNL-4028 (1982), credible Accident ! I Analyses for TRIGA and TRIGA-Pueled Reactors). A :
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for variations of flux level (and thus the power density) at various parts of the core. The safety
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, otherwise steady-state operation, and should be adequate to protect aluminum-clad fuel elements from cladding failure due to temperature and pressure offects.
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- 3. LIMITING CONDITIONS FOR OPERATION (LCO) l F ,
3.1. Reactivity Limits h Applicability i . 3 These specifications shall apply to the reactor at all i tines that it is in operation. ,
, Obiective !
o The purpose of the specification is to ensure that the reactor can be controlled and shut down at all times and that the safety lindt will not be exceeded, f Specifications ! The reactor shall be shutdown by more than $.50 with
'the most reactive control rod fully withdrawn, the i other two control rods fully inserted, cold, no xenon, ,
including the reactivity worth of all experiments. i The excess reactivity measured at less than 10 watts in , the reference core condition, with or without ' experiments in place, shall not be greater than $3.00. i' q
; E8.212. 1 The value of the udnimum shutdown margin assures .that !
the reactor can be safely shut down using only the two least reactive control rods..
-The assigriment of a specification to the maximum excess _;
reactivity serves as an additional restriction on the- , shutdowr margin and limits ~the maximum power excursion
-i that could take place in the event of failure of all of the power level safety circuits and administrative .l controls.
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1 J -y2 f . 10 -- l h 3 ~. 2 . .C*re Conficuration Applicability , i~ This specification applies to-the core configuration. Obiectd.ve The objective of this specification is to assure that the safety limit will not be exceeded due to power peaking effects.
' Speed fications Ji -: i F The critical core shall be an assembly of standard NRC-approved stainless-steel-clad or aluminum-clad TRIGA fuel elements in light water. l i
1 The fuel shall be arranged in a close-packed array for ) operation at full licensed power except for (1) . , 9 ceplacement of single individual fuel elements with in-core irradiation facilities or control rod guide tubes and (2) the start-up neutron source.
'The aluminum-clad fuel element shall be placed in the E }
. ., or F ring.of the core.
Ranal 44
, Operation with standard NRC-approved TRIGA fuel in the standard configuration ensures a conservative t$ limitation with respect _to the Safety Limit. .
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Placement of the' aluminum-clad fuel element in-the- y
'\f outer rings of the reactor core willl help ensure.that :!
i' n: this element is not. exposed to higher' titan average power' levels, thus providing a. greater degree of .
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-conservatism with respect to the Safety Limit for this-i 1 one element.
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lK , ' n :n ^i 3p je - - 11 . 3.3. Reactor' Control and Safety ' Systems Applicability These specifications apply to the reactor control and safety systems and safety-related instrumentation that must be operating when the reactor is in operation.-
=Obiective The objective of these specifications is to assure that=
; all reactor' control and safety _ systems and safety- i
," related instrumentation are operable to minimum acceptable standards during operation of the reactor.
Specifications There shall be a minimum of three operable control rods
; in-the reactor core.
l.' Each of the three control rods shall drop from the fully withdrawn position to the fully Jnserted position , c
-in a time not to exceed one second.- !
4 The reactor safety channels and the interlocks shall be operable in accordance with table 3.3A. The reactor shall not be operated unless the measuring m , channels' listed in Table 3.3B'are operable.
, Positive reactivity insertion rate by control rod- l j
1 motion shall not exceed 0.20 per-second. o; Bases: j The.requirementLfor three operable: control rods ensures-that the reactor can meet the shutdown specifications. ! i 4 The control rod drop time specification assures that-
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the: reactor can be: shutdown promptly whenta-scram L
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signal is initiated. 'The!value of the controlcrodtdrop- -
- time is-adequate'to assure safety of the-reactor.
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.Use;of the specified' reactor safety 1 channels,Lset yl;
, points,:and interlocks given in table 3.3A assures.
3 . protection againstLoperationLof;the reactor outside the-
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la , 4 parameters.can.be monitored during-operation. The, specification of maximum positive' reactivity w insertion 1 rate helps assure that the Safety Limit is-
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l TABLE 3.3A. . 6 MINIMUM REACTOR SAFETY CIRCUITS, INTERLOCKS, AND SET POINTS l ! r-Scram Channels
- s Scram Channel Minimum Operable Scram Setooint- 1 Reactor Power-Level 2 Not to exceed maximum
- licensed power '
' Reactor Period 1 Not less than 7 seconds
- Wide-Range Linear Channel l' Failure'of the detector Detector Power Supply high-voltage power supply Wide-Range Log Channel. 1 Failurelof the detector !
high-voltage power supply _ i
- g. Manual Scram ,
1 Not applicable i-t Interlocks .. g Interlock / Channel ' Function Startup Countrate Prevent control rod;
! withdrawal when the neutron count rate is l'ess. !
'E -than=2 cps 17 C + . 1,l
-Rod Drive. Control 4
/ Prevent simultaneous' , f- 4 manual withdrawal of two- d control elementa by the: control rod drive motors, l V '
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TABLE 3.3A n n BASES FOR REACTOR' SAFETY CHANNELS AND INTERLOCKS Scram Channels 4 Scram Channel Bases
'ME Reactor Power Level Provides assurance that the reactor will be shut down automatically before the safety limit can be exceeded Reactor Period Prevents operation in a regime in which transients could cause the safety limit to be exceeded i
c4 Reactor Power Channel Provides assurance that the reactor Detector Power Supplies cannot be operated wiLhent power to
,, g the neutron detectors which provide
, input.to the wide-range linear power
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channel and the wide-range log power. t channel
. Manual Scram Allows the operator tol shut the reactor down at.any' indication.of sunsafe or abnormal conditions p
Interlocksi p Interlock / Channel Bases ae l 4
;j ' Startup Countrate Provides assurance that'the: signal
'in:the' log power channelsie adequate-to, allow reliable' indication of the' ;
j state of the neutron, chain-reaction, it ,
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1"- l Rod. Drive' Control Limits-the; maximum positive l di h, . reactivity insertion l rate-
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/ ,, Measuring channel Minimum Number Operable Wide-range Log N 1 and Period Channel
, Power-Level Channel 1 (Linear) t t
I Power-Level Channel 1 (Percent Power) r i Water. Radioactivity 1 s Monitor: < i Water Temperature 1 Monitor TABLE 3,3B t-r
-BASES FOR MEASURING CHANNELS Measurina Channel Basis Wide-Range Log N Provides-assurance that the
- and - Pe'riod ' Channel reactor power' level ~and period canJ be adequately monitored.
-V Power-level Channel Provides assurance that'the reactor
- (Linear) power level _can be adequately-monitored.. , .;
or r Si! ' Power-level Channel- Provides. assurance that the reactor- 1
;s '(Percent Power) . power level can be: adequately y
m ,o s * ' monitored..
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' Water? Radioactivity-m? .Provides assurance that the water
,,g (Monitor; radioactivity level can~be n; -adequately; monitored.
l Water Temperature' Provides assurance that-the water Monitor. temperature can be adequately li . monitored. [ Amendment No. 6 i i b I t qu Xb+ r \. s-
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t 3.4. Coolant System Applic' ability These specifications apply to the quality of the a coolant in contact with the fuel cladding, to the level-of:the coolant in the pool, and to the bulk temperature -j
't of the coolant.
E Obiectives- f The objectives of this specification aret - to minimize corrosion of the cladding of the fuel elements and minimize neutron activation of -
. dissolved materials, to detect releases of radioactive materials to the coolant before such releases become significant, to ensure the presence of an adequate quantity of-cooling and shielding water in the pool, and 1
~to prevent thermal degradation ~of.the ion exchange ll resin in the purification. system. .
Specifications -{ The. conductivity;of the pool water shall not exceed 5 pmhos/cm averaged over one month, t The pool water pH shall be in theLrange of 4 to 7.5.
~I LThe amount of radioactivity in.the pool water shall not;
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. exceed 0.1 pCi/mL.
The water:must cover the core of the reactor to a
;-minimumidepth of 15 feet during operation of-the
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The bulk. temperature of the: coolant shall not exceed =60 C during operation of the~ reactor.. ; ii l' i m
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h .3 , 1 Bases Increased levels of conductivity in aqueous systems ; indicate the presencelof corrosion products and promote .! more corrosion. Experience with water quality control at many reactor facilities,, including the past 19 years l of operation of the Dow TRIGA Research Reactor, has shown that maintenance within the specified limit provides acceptable control. Maintaining low levels of p diocnived electrolytes in the pool water also reduces the amou't of induced radioactivity, in turn decreasing the exposure of personnel to ionizing radiation during-1. operation and aaintenance. Both of these results are q in accordance'with the ALARA program. (1
, Monitoring the pH of the pool water provides early detection of extreme values of pH which coo'_d enhance corrosion. ;
Monitoring the radioactivity in the pool water serves l to provide early detection of possible c4 adding ; failures.- Limitation of the radioactivity according to this specification decreases the exposure of personnel to ionizing radiation during operation and maintenance 7, in accordance with the ALARA program.
. Maintaining the specified depth,of water in the pool provides shielding of'the radioactive core which '
reduces the exposure of-personnel to ionizing radiation. In accordance with the ALARA program. , MaintainincLine bulk temperature of the coolant below the specified limit assures; minimal thermal degradation. " of?the ion exchange, resin. n
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, 3.5. Confinement-l Applicability QU[w :lH ' '
l I ia :- >J This specification applies to the reactor room confinement. obiective
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The objective of this specification is to mitigate the
'T -consequences of possible release of radioactive materials to unrestricted areas.
LE Specification j
.g. The ventilation system shall be operable and the external 4" door shall be' closed whenever the . reactor is operated, fuel l is nanipulated, or radioactive-materials with the potential. -!
',' < of airborne releases are handled in the reactor room. ! o Basis This specification ensures:that the confinement is
' configured to control any releases of radioactive material p during fuel handling, reactor; operation, or the handling of
.possib1'e airborne radioactive material in the reactor' room. .
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, 19 3.6. Radiation Monitorino Systems Applicability-These specifications apply to the radiation monitoring information'available to the reactor operator during operation of the reactor.
< I Obiective The objective of these specifications is to ensure that the reactor operator has adequate information to assure safe operation of the reactor.
Specifications A Continuous Air Monitor (CAM) (with readout meter and-audible alarm) in the reactor room must be operating during operation of the reactor. The Area Monitor (AM) (with readout meter and- audible. q alarm) in the reactor room must be operating during h operation of the reactor or when work is being done on
;l or around the reactor core or' experimental facilities.
. .During short periods of repair to this monitor, not to
, exceed thirty days,. reactor. operations or work on or around the-core or experimental facilities may continue gn while a portable gamma-sensitive ion chamber is
' utilized as a temporary: substitute, provided thet the _
. substitute can be monitored by the reactor operator; ;-
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'The. radiation' monitors provide information of-existing.
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, levels oferadiation-and air-borne radioactive materials-
'D ' 9lf which could: endanger _ operating personnelior which could h;jf.' f _w arn offpossibleLmalfunctions of the reactor or the: ' q g L' experiments'in the reactor. l
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l 3.7.- Experiments Applicability
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These specifications apply to experiments installed in the reactor and.its experimental facilities. ; Obiective f The objective of these specifications is to prevent damage to the reactor or excessive release of radioactive materials in case of failure of an experiment. Specifications i
- 1. Operation of the reactor for any purpose shall j require the review and approval of the appropriate -
persons or groups of persons, except that operation of the reactor for the purpose of performing routine checkouts, where written procedures exist for those. operations, shall be authorized ~by the written procedures. An operation shall not be approved unless the evaluation allows the conclusion that the failure of an. experiment will !
'h not lead to the direct failure of a fuel element or
, oof any other experiment.
p
- 2. The total abs 0 lot eaactivity worth of in core experiments shall not exceed $1.00. This includes M- the potential reactivity which might result 1 from i experimental malfunction, experiment flooding or ,l voiding, or the removal or insertion of l experiments.
3. Experiments.having reactivity worths of-greater- l than $0.75 shall be securely located or fastened to
- p -prevent inadvertent movement during reactor. <
operation. y.
' "o 4.' Experiments containing materials corrosive to
- reactor. components, compounds highly reactive with
+
water, potentially1 explosive materials or-liquid-
; fissionable materials shall be doubly encapsulated. .;
h, .
- gi !
J, 7g Amendment No. 6
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{l11 M fif , l4-QI % l[ fN W;Y
,y 5. Materials which could react in a way which could
.i
, damage the components of the reactor (such as ;
~
jj , gunpowder, dynamite, TNT, nitroglycerin, or PETN) oL shall- not be irradiated in quantities greater than i -f ? 25 milligrams in the reactor or experimental- l facilities without out-of-core tests which shall indicate that, with the containment provided, no damage to the reactor or its components shall occur upon reaction. Such materials.in quantities less than 25 milligrams may be irradiated provided that V .the pressure produced in the experiment container ' upon reaction shall be calculated and/or
, experimentally demonstrated to be less.than the design pressure of the container. Such materiale
=i must be packaged in the appropriate containers i before being brought into the reactor room or must i be in the custody of duly authorized local, state, i or federal officers.
jj : 6. . Experiment materials, except= fuel materials, which. Q could off-gas, sublime, volatilize or produce aerosols under (a) - normal operating conditions of the experiment or the reactor, (b) credible a; accident conditions in the reactor or (c) possible , a .- accident conditions in the3 experiment shall bel t
% limited in activity such that if 100%'of the gaseous activity or radioactive' aerosols produced
,g., escaped to the reactor room or the atmosphere, the Wl q airborne concentration of, radioactivity would not W exceed the' limits of' Appendix B of 10 CFR Part 20. };
# The following; assumptions:should be used'inc calculations regarding experiments:-
l Th
<m , a. - If the. effluent 1fromLan experimental-facility f(
exhausts through a holdup tank which~ closes. automatically on1high radiation levels, the assumption shall :be used -that 10% . of the
*s .
. gaseous activity or'~ aerosols produced will
.p@ = escape.
Wh ll7 b. If the effluent-from an experimental facility-l i \gg exhausts through a filter'installationi I g ;ipf designed for greater than 99%' efficiency for k4 i 0.3 micron particles, the assumption shall be-ff/ ( , used that 10% of the' aerosols produced escape.
- .;y 1 D] \ .,,
Amendment No. 6
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7 Nbd 8,, I j . -. 7
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. .y c. For materials whose boiling point.is above 55 C and where vapors formed by boiling this material could escape only through an ,
undisturbed column of water above the core, ' s the assumption shall be used that 10% of these vapors escape.
- 7. Each fueled experiment shall be controlled such that the total inventory of iodine isotopes 131 ,
i through 135 in the experiment is no greater than 1.5 curies and the maximum strontium-90 inventory is no greater than 5 millicuries.
- 8. If an experiment container fails and releases-material.which could damage the reactor. fuel or structure by corrosion or other means,~ physical ,
inspection shall'be performed to determine the' consequences and the need for corrective action. .;
- 9. Experiments shall not occupy adjacent ~ fuel-element q positions in the B- and C-rings.
Bases [{
~1. . This specification is intended to provide at least one level of review of any proposed' operation of j the reactor in' order to minimize the possibility of operations of-the reactor which could be dangerous
-or in violation of administrative procedures or-the
,A . technical specifications. The exception is made.in-i the casecof those few very well characterized' operations which are necessary for routine checkout
~
l lof the reactor and=1ts; systems, provided that those. } operations have been defined by written procedures
- which have beenLreviewed.and approved by the Reactor Supervisor and the Reactor Operations j
- Committee.
=2. This specification is. intended to limit the
. reactivity of.the system.so.that the Safety Limit-l '" "*
would not be exceeded even if the contribution to / the'totalLreactivity by.the experiment reactivity' i [ should be suddenly removed.. , a , ; i +
, Amendment No. 6 i J.
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- 33 -
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.3. -This specification is intended to limit the power excursions which might be induced by the changes in reactivity due to inadvertent motion of an unsecured experiment. Such excursions could lead j to an inability to control the reactor within the limits imposed by the license.
- 4. This specification is-intended'to reduce the ,
possibility of damage to the reactor or the ! experiments.due to release of the listed materials. l 1
- 5. This specification-is intended to reduce the L{
possibility of damage to the reactor in case of (' accidental detonation of the listed naterials. 1
- 6. This specification is intended to reduce the i severity of the results of accidental release of airborne radioactive materials to the reactor room or the atmosphero.
- 7. This specification is intended to reduce the severity of any possible release of these fission
- products which pose the greatest hazard to workers-and-the general public. q
- 8. This specification requires specific actions to l determine the extent of damage following releases
-of materials.- No theoretical calculations or 4'
evaluations are allowed. r p 9. This specification prevents serious modification.of
'.t' the neutron distribu' tion which could affect the j
- abilityfof'the control rods'to perform their- 1
- intended; function -of maintaining safe control of .
othe reactor.
~4.-SURVEILLANCE REQUIREMENTS i
' Allowable surveillance intervals shall not exceed the'following:
biennially _- not-to, exceed 30'monthe
, l annually.- not'to' exceed 15 months semi-annually - notitoiexceed seven and one-half months-monthly: .not.to. exceed six weeks i
l sweekly-- notLto exceed 10 days j
' daily - must be donelbefore the commencement of operation' ,
each-day ofcoperation l .
- I Amendment No.-6 l i
4 b 'f
~
f Established frequencies shall be maintained over the long term, so,-for example, any monthly surveillance shall be performed at i I least 12 times during a calendar year of normal operation. If the reactor is not operated for a period of time exceeding any j required surveillance interval, that surveillance task shall be , performed beforeLthe next operation of the reactor. Any f surveillance tasks which are missed more than once during such a shut-down interval need be performed only once before operation of the reactor. Surveillance tasks scheduled daily or weekly which cannot be performed while the reactor is operating may be postponed during continuous operation of the reactor over extended times. Such postponed tasks shall be performed following shutdown after the extended period of continuous operation before any fuather operation, where each task shall be performed only once no n atter how many times that task has been ; postponed. i 4.1. Reactor Core Parameters Applicability j These specifications apply-to surveillance requirements I for reactor core parameters. Obiective d The objective of these specifications is to ensure that-the specifications of section 3.1 are satisfied. l
-Specification The reactivity worth of each control rod, the reactor- f core excess, and the reactor shutdown margin shall be_ _l measured at least annually and after each time the core j fuel is moved. j
-a ~
Basis
. Movement of the core fuel could change the reactivity !
of tho' core and thus affect'both the core excess- -i reactivity and the shutdown margin, as well as-affecting the worth of the. individual control rods.
! Evaluation of-these parameters is therefore required.
after any such movement. 'Without any such movement the. : changes of these parameters'over an extended period of ! time'and operation of the reactor have been shown to be veryssmall so that an annual measurement is-sufficient d to ensure compliance with the specifications of section ., 3.1. I I I E Amendment No. 6 i .i
- } '
n
3
.. 4
^
l 17 l i P 4.2. Reactor Control ~and Safety Systems Applicability 4 These specifications apply to the surveillance requirements of the reactor safety systems. Obiective .i The objective of these specifications is to ensure the L operability of the reactor safety systems as described -! in section.3.3. { Specifications i
- 1. Control rod drive withdrawal speeds and control rod drop times shall be measured at least annually and ,
whenever maintenance is performed or repairs are l made that could affect the rods or control rod drives.
- 2. A channel calibration shall'be performed for the 3 wide-range linear power channel by thermal power calibrat'on at least annually. >
- 3. A channel test shall be performed at least daily I
and after any maintenance or repair for each-of the six scram channels and each of the.two interlocks q listed in table 3.3A, 'and the log power channel. .[
- 4. The control rodsLahall be visually inspected at
~
-least biennially.
Bases = ai
- 1. Measurement of the control rod drop time and' i compliance with the specification indicates that :
the control rods can" perform the safety function : j properly. Measurement ~of-the control rod withdrawal-speed ensures that the maximum reactivity addition rate specification will.not be exceeded.- t i 4
'l Amendment No. 6 L
l'
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f 4 . pr .
- 4 2.- Variations of the indicated power level due to minor' variations of any one of the three neutron ,
i detectors would be readily evident during day-to-y day' operation. The specification for thermal calibration of the wide-range linear channel i provides assurance that long-term drift of all three neutron detectors would be detected and that the reactor will be operated within the authorized i' power range.
- 3. The channel tests performod daily before operation i
-and after'any repair or maintenance provide timely assurance that the systems will operate properly.
during operation of the reactor. ..; l
- 4. Visual inspection of the control rods provides l opportunity to evaluate any corrosion, distortion, )
or damage that might occur in time to avoid j malfunction of the control rods. Experience at the j Dow TRIGA Reactor Facility over the past 19 years ; indicates that the surveillance specification is adequate to assure proper operation of the control
]
cl rods. .This surveillance complements the rod drop . !, time measurements. : l 4 4.3. Coolant System o Applicability -
.i
~ These specifications shall apply to the surveillance j requirements for the reactor coolant system. E Obiective The objective of these. specifications.'is to ensure that
- il the specifications of section'3.4 are satisfied.-
t 3 Soecifications
- 1. The' conductivity, pH,.and the radioactivity of the-' ,
pool water shall be measured at=least monthly. f L .2. The level of tho' water in,the pool shall be
-determined to'be adequate-on a-weekly' basis.
3 3.. The temperature of the coolant:shall.be monitored during operation of the reactor. _f Amendment No. 6 . 1 a
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- 1. Experience at the Dow TRIGA Research Reactor shows that this. specification is adequate to detect the onset.of degradation of the quality of the pool water in a timely fashion. Evaluation of the
-radioactivity in the pool water allows the detection of fission product releases from damaged fuel elements or damaged experiments. ,
p
- 2. Experience indicates that this' specification is 7 adequate to detect losses of pool' water by <
evaporation. '
- 3. This specification will enable operators to take ;
appropriate action when the coolant temperature approaches the specified limit. 4.4. Radiation Monitorino Systems Applicability.
~
These-specifications apply to the surveillance I
. requirements for the Continuous Air Monitor (CAM). and et the Area Monitor (AM), both~ located in the reactor
. room.
Obiective t The objective of these-specifications is to ensure the quality =of the data presented by.these two instruments.
-Specifications' l
- 11. A channel calibration shall be made for the CAM and' j
.g .the AM at least annually. 3 1
2.- A channel test shall be made for the CAM and the AM. at least' weekly. Bases. These.-specificationajensure that'the. named equipment.
- can perfoon the required ' functions when the. reactor is : ,
operating-and.that deterioration'of'the' instruments
will~be detected'in-a timely manner. 'Experienc'e with these instruments has shown that the surveillance
, intervals are adequate to provide the required .
assurance. ! l i LNnendment No. ~ 6 y l t l . s l 3 ; ',
4.5. Facility Specific Surveillance Applicability This specification shall apply to the fuel elements of the Dow TRIGA Research Reactor. Obiective The objective of this specification is to ensure that the reactor is not operated with damaged fuel elements. Specification Each fuel element shall be visually examined annually. The reactor shall not be operated with damaged fuel except to detect and identify damaged fuel for removal. A TRIGA fuel element shall be removed from the core ift a) The transverse bend exceeds 0.125 inch over the length of the cladding. b) The length exceeds the original length by 0.125 inch, c) A clad defect exists as indicated by release of fission products. Basis Visual examination of the fuel elements allows early detection of signs of deterioration of the fuel elements, indicated by signs of changes of corrosion patterns-or of swelling, bending, or elongation. Amendment No. 6 l
- - - - . . . . . . . . . . a- -.- . - . .. --m.m.-.n
- = - -
1 y ;,- ;
~
29.- I 4.6. ALARA Applicability e This specification applies to the surveillance of all reactor operations that could result in occupational [ exposures to ionizing radiation or the release of ; radioactive naterials to the environment. i
-obiective ,j s
--The objective of this specification is'to provide I surveillance of all operations that could lead to occupational exposures to ionizing radiation or the release of radioactive materials to the' environs.
Specification l The review of all operations shall include consideration of reasonablee alternate operational n' odes. which might reduce-exposures to' ionizing radiation or releases of radioactive ;{ materials, j Basiss. Experience has shown that experiments and operational
-requirements, in many. cases, may be satisfied with a varietyrof combinations of facility options,_ power levels, time delays, and effluent or staff radiation exposures.:
The ALARA (As' Low As Reasonably Achievable) _ principle shall .. be a part of-overall reactor = operation and detailed; l experiment planning.~ j m
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0' > l ! Amendment No. 6 j i-j L ,a o
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.5.- DESIGN FEATURES l j 5.1.. Reactor Site and Buildino l Applicability These specifications shall apply to the Dow TRIGA Research Reactor.
Obiectives The objectives'of these specifications are to define
.' the exclusion area and characteristics of the confinement.
i- Specifications-s
-The minimum distance from the center of the reactor
'i o ' ~ pool to the boundary of the exclusion area shall be 75 f eet'. I
.The reactor shall be housed in'a room'of about 6000 .j Lcubic feet volume designed to restrict leakage. j
-All-air or other gas exhausted from the reactor room and from associated' experimental facilities during g '
reactor operation _shall be released to the environment o l at:a minimum of 8 feet above ground level. Bases The minimum' distance from the pool to the boundary _ y
-providesifor' dilution of effluents and for control of .
'z access to the reactor area.
Restriction of leakage, in~the event of a release of radioactive 1 materials, canicontain the materials and reduce exposure of the public. j 1
-Release _:of gases at a minimum height,of 8 feet' reduces s the possibility of exposure of personnel to such gases. .
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wr .. f. l,_ Amendment No.16 . N~ i s I; .
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1 5.2. Reactor Coolant System Applicability 4 This specification applies to the Dow TRIGA Research c: Reactor. i y if obiective 4;. The objective of this specification is to define the characteristics of the cooling system of this reactor. ' Specification The reactor core shall be cooled by natural. convective-
- water flow.
Basis i
. Experience has shown that TRIGA reactors operating at p . ,
power levels up to;1000 kilowatts can be cooled by: natural convective water flow without damage of;the fuel-elements, q i
'5.3.
Reactor Core and Fuel _ j Applicability- ! (? 'l
;These specifications.shall be applicable to~the Dow ]
b, TRIGA.Research Reactor. j l Obiective :; 1 The. objective.of these specifications is:to define certain~ characteristics of the reactor in order'to- :)
, ' assure that_the design and accident analysesLwill be-correct. ,
-j
' Specification ~ j s .
=)
<- .The fuel will be standard NRC-approved TRIGA. fuel.' j
# --a q 36 The control elements shall have scram capability;and 'j shallicontain borated graphite, boron-carbide' powder,. j
, OU >
'or boron and its components'.in solid form ae a: poison- 'l 3;:n y' in,an aluminum or. stainless steel cladding.. -
, t
, Amendment No.f6 -l
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The reflector (excluding experiments and experimental facilities) shall be a combination of graphite and water. Bases The entire' design and accident analysis is based upon 'i the characteristics of TRIGA fuel. Any other. material -l would invalidate the findings of these analyses. .; The control elements perform their function through'the! l absorption of neutrons, thus affecting the reactivity of the system. . Boron his been found to be a stable and ,
-effective material for this control.
The reflector serves to conserve neutrons and to reduce the amount of-fuel that must be in the core to maintain. j the chain reaction. : 5.4. Fuel Storace i
' Applicability' !
This specification applies to the Dow TRIGA ResearchJ Reactor fuel storage facilities. Obiective The' objective of this specification is the safe storage of fuel. Specification i: All fuel and fueled' devices not'in the-core of the reactor'shall be' stored in such'a way that k gg shall' be less than 0.8 under all conditions of moderation, and'that.will permit sufficient cocling by natural' .; convection of water or air that temperatures'shall'not j exceed the Safety Limit. I Basis-
'A value cf kegg of-less.than 0.8 precludes any j
~ possibility of inadvertent. establishment of a self-
~
sustaining nuclear chain reaction. -Cooling which , maintains temperatures lower than the Safety Limit. '4 prevents possible-danage to the devices ~with subsequent 1 release of radioactive materials. Amendment No. 6 q
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- 6. ADMINISTRATIVE CONTROLS 6.1, Oroanization The'Dow TRIGA Research Reactor is owned and operated by The l Dow Chemical Company. The reactor is administered and operated through the Analytical Laboratory of the Michigan ,
Division'of Dow Chemical USA and is located in 1602 Building of the Analytical Laboratory at the Midland, Michigan location of the Michigan Division. 6.1.1. Structure The structure of the administration of the reactor is shown in figure 6.1. This structure cuts across the lines of management of The Dow Chemical Company. The individual responsible for radiation safety is the Radiation Safety Officer for the reactor who reports on matters of radiation safaty to the Radiation Safety Committee and to the
. Reactor Operations Committee. The review and audit functions are performed by the Reactor Operations i Committee which is composed of at least four persons including.the Analytical Laboratory Research Manager, the Radiation Safety Officer, and the Reactor Supervisor.
6.1.2. Responsibility The day-to-day responsibility for the safe operation of the reactor rests with the Reactor Supervisor who is a licensed Senior Reactor ->
- Operator appointed by the' Facility Director. The
- Reactor Supervisor may appoint equally-qualified-individuals, upon notification of the Facility Director and the Reactor Operations. committee, to assume the responsibilities of the Reactor Supervisor. The Reactor" Supervisor-reports in a -!
management sense to the_ Facility Director and
~
f within'the reactor organization to the Reactor Operations Committee. h- ' l 1 Amendment No. 6
]
1 - I F Ts -P r f
fi , I - -34 Figure 6.1. Administration Otrect:r. -- Corporate Otrector, Michigan Olvision
.i. R&D R&D i
Manager. _ Olrector, industrial Hygiene Analytical Cor: crate Laboratory ! Radiation Safety Research Manager, Officar. Analyticci Corcerate Laboratory i Radiation safety Officer, Licensed TRIGA SRos anc R0s i l
, i l
l
. Rectauen
. Safety Ccmmsttat Raciauen safety Officer TRIGA ~ '
React 0r C0er20Cn3 Ca?!Ptttee Review I AUCit l Re.cter h i SRO. a Seemser . and Ros Amendment No. 6 l l l I'
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5 6.1.3. Staffing U- - The minimum staffing when the reactor is not i secured shall be:
- a. a licensed Reactor Operator or Senior Reactor Operator in the. control room., and
-v
- b. a second person present at the facility ;
'able to carry out prescribed written instructions, and
- c. a licensed Senior Reactor Operator in the facility or readily available on call and able to be at the facility within 30 minutes. '
1 The following operations require the presence of
- the Reactor Supervisor or a designated alternates
- a. manipulations of fuel-in-the core;
- b. manual removal of control rods; 3 4
c.-maintenance performed on the core or the control rods; e
- d. recovery from unexplained scrama, and e, movement.of any in-core experiment having
- an estimated reactivity value greater than
-$0.75.
a ' A list of_ reactor facility personnel by name.and
- telephone number.shall be.readily availablefin the.
control-room.for use by the operator, including
* ' management, radiation safety,Jand other operations personnel. ---
^
b , t i i ! k 1
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Amendment No. 6 R. , .m N
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- d. Id,
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;c a-6 l.4- . Selection and Training of Personnel l
.The Reactor Supervisor is responsible for the training and requalification of the facility Reactor Operators and Senior Reactor Operators.
The selection, training, and requalification of operations personnel shall be consistent with all current regulations. ; Day-to-day changes in' equipment, procedores, and. specifications shall be communicated to the l facility staff as the changes occur. ; 6.2. . Review and Audit l The review and audit functions shall be the responsibility of the Reactor Operations Committee (ROC).
' 6. 2. l ', Charter and Rules
- a. This Committee shall consist of the Facility- !
Director, who shall be designated the chair of this committee; the Radiation Safety Officer; the Reactor Supervisor; and one.or more persons who are-competent in the field of reactor operations, radiation science, or reactor / radiation, [ engineering.
.in A quorum shall consist of a. majority of the. '
members of the ROC. No'more than one-half of'the 5 voting members present shall be members of the day- , to-day; reactor operating staff.
}
c.cThe Committee shall. meet quarterly and aa often ' as required to transact business.
- d. Minutes of the meetings shall be kept as roccads for the facility.' ,
- e. In cases where quick action is necessary members; of the ROC.may be polled by telephone.for-guidance and approvals.
m ,
"f. The ROC.shall. report at least twice per year to
'! Jthe Radiation Safety Committee'.
f.,-s I Amendment No. 6'
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W: A i ! 4 6.2.2. Review.runctions
.The ROC shall. review and approve: [
a..every experiment involving fissionable materials
.b. experiments or operations which would require a change of core configuration, or a change in the- 4 equipment or apparatus associated with the reactor core or its irradiation facilities,;or a new piece of apparatus'being mounted in the reactor well; t except that movement of the neutron source for the purpose.of routinely checking the instrumentation, or the movement of the neutron detectors to establish the proper calibration of the associated '
channels shall not require review by the ROC;
- c. any other experiment or operation which is of a >
stype not previously approved by the Committee;
'i
- d. proposed changes in operating' procedures, technical specifications, license, or charter; e
yl e.Eviolations of technical specifications, of the , license, of-internal procedures,:and of-
. instructions having safety significance;-
.f.. operating abnormalities'having safety
-significance;
+
- g. reportable occurrencos's
.h.-proposed changesJin' equipment,' systems, testsA or: experiments with respect to unreviewed safety- J
; questions;=and- A h mu !
% 1.Laudit reports. : p- < l t t n . i s. 'l
- s: I Amendment No. 6
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6.2.5. Audit Funct.on
- a. The ROC shall direct an annual audit of the facility operations for conformance to the technical specifications, license, and operating procedures, and for the results of actions taken to correct those deficiencies which may occur in the reactor facility equipment, systene, structures, or nethods of operations that affect reactor safety.
This audit may consist of examinations of any facility records, review of procedures, and interviews of licensed Reactor Operators and Senior Reactor Operators. The audit shall be performed by one or more persons appointed by the ROC. At least one of the auditors shall be familiar with reactor operations. No person directly responsible for any portion of the op3 ration of the facility shall audit that operation. A written report of the audit shall be submitted to the ROC within three months of the audit. Deficiencies that affect reactor safety e til be reported to the racility Director immediately.
- b. The ROC shall direct an annual audit of the facility emergency plan, security plan, and the reactor operator requalification program. This audit may consist of the annual review of these plans for the requalification program.
Amendment No. 6
l J 6.3. Procedures Written procedures shall be reviewed and approved by the ROO fort
- a. reactor startup, routine operation, and shutdown;
- b. emergency and abnormal operating events, including shutdowns
- c. fuel loading or unloading;
- d. control rod removal cr installationi
- c. checkout, e.alibration and determinetion of operability of reactor operating instrumentation and controle, control rod drives and area radiation and air particulate monitorsi and
- f. preventive maintenance procedures.
Temporary deviations from the procedures may be made by the responsible Senior Reactor Operator or higher individual in order to deal with special or unusual circumstances. Such deviations shall be documented and reported immediately to the Reactor Operations Committee. 6.4. Experiment Review and Approval
- a. Routine Experiments (as reviewed and defined by the ROC) shall have the written approval of the Reactor Supervisor or a designated Assistant Reactor Supervisor,
- b. Modified Routine Experiments shall have the written approval of the Reactor Supervisor or a designated Assistant Reactor Supervisor. The written approval shall include documentation that the hazards have been considered by the reviewer and been found appropriate for this form of expetiment.
- c. Special Experiments, those experiments that are neither Routine Experimente nor Modified Routine Experiments, shall have the approval of both the Reactor Supervisor (or designated Assistant Reactor Supervisor) and the ROC. Experiments which require the approval of the ROC through sections 6.2.2.a., 6.2.2.b., or 6.2.2.c. of the
' Technical Specitications are always Special Experiments.
Amendment No. 6
m _, _ r- q c-A.
- A V,
t 6.5. Required Actient 6.5.1. In case of Safety Limit violations
- a. the reactor shall be shut down until resumed operations are authorized by the US NRCs
- b. the Safety Limit violation shall be immediately reported to the Facility Director or to a higher L' level;
- c. The Safety Limit violation'shall be reported to
! the US NRC in accordance with section 6.6.2.s and
- d. a report bhall be prepared for the ROC describing the applicable circumstances leading to the violation including, when known, the cause and contributing factors, describing the effect of the violation upon reactor facility components, systems, or structures and on the health.and safety.
of personnel and the public, and describing corrective action taken to prevent recurrence of a the violation. 6.5.2. In case of a Reportabic Occurrence of the type L identified in section 1.20s
- a. reactor conditions shall be. returned to normal j > or the reactor shall be shut downs if the reactor is shut down operation shall not be resumed unless authorized by the racility Director or designated-alternate;
, y b. the occurrence shall be reported to'the Facility Director and to the US NRC as required per section 6.6.2.;;and
+ .s
- c. the occurrence shall be reviewed by.the ROC at the next scheduled meeting.
4 p, , i (
, . Amendment No. 6 I
el[ 3;
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- q-
((t; e 2 L ., ! -,
p ig o L 6.6.. Reports 6.6.1. Operating Reports A report shall be submitted annually, within 90 days of the anniversary of the license, to the t Radiation Safety Committee and to the Director,
! Office of Nuclear Reactor Regulation, US NRC,
- Washington, DC, with a copy to the Regional E Administrator, US NRC Region III, which shall ,
include the following: i
;' a) status of the facility staff, licenses, and .
, training; b) a narrative summary of reactor operating ;
F experience, including the total megawatt-days of j operation; ; c) tabulation of major changes in the reactor facility and procedures, and tabulation of new tests and experiments that are significantly different from those performed previously and are t not described in the Safety Analysis Report,. ; including a summary of the analyses leading to the ,;
, conclusions that no unreviewed safety questions were involved and that 10 CFR 50.59 (a) was .[
! applicables.
]
!. d) the unscheduled shutdowns and reasons for them- .! int,1uding,-where applicable, corrective action t taken to preclude recurrence;
, e) tabulationofmajor)preventiveandcorrective 1 maintenance operations having safety significance; [
f) a summary of *+= ns.ure and amount of c radioactive efflue:.L. mleased or discharged to environs beyond the ef fr etive control of the owner-b 1 operator as.determineri at.or before the point of' , such release or discharge -(the summary shall' include to the extent practicable an estimate of. individual radionuclides present'in the effluent;- g , if the estimated ~ average' release'atter dilution or' j diffusion is~1ess than 25% of the concentration- !? [ allowed or recommended,-only a statement:to this
'effect is needed); ande Amendment'No. 6' t
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I0 42 - l I 5 5 i g) a summar', of the radiation exposures received by [ facility personnel and visitors where such } exposures are greater than 25 % of those alleved or : recommended in 10 CFR 20. I i G.6.2. Special Reports
- a. There shall be a report to US NRC Region III not ,
later than the following working day by telephone l and confirmed in writing by telegraph or similar : conveyance to the Director of Nuclear Reactor f Regulation, US NRC, with copy to the Regional Administrator, Region III, US NRC to be followed by I a written report that describes the event within 14 !
. days of: i 5
H a violation of the Safety Limit; or !' a reportable occurence (section 1.28) . I
- b. There shall be a written report presented within
- 30. days to the Director of Nuclear Reactor Regulation, US NRC, with copy to the Regional Administrator, Region III, US NRC, of: 1 permanent changes in the facility involving level'1 [
or level 2 personnels or ! significant changes in the transient or accident analysis report as described in the Safety Analysis Report. t
- c. A. written report!shall be submitted to the '
Director of the Office of Nuclear' Reactor Regulation, US NRC, with copy to the Regional Administrator, Region III, US NRC, within 60 days p after criticality of the reactor under. conditions i p; of a new facility license authorizing an' increase , in reactor power level, describing the measured values of the operating conditions or
~ characteristics of the reactor under.the new 4 conditions; -
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.i Amendment No. 6 i
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i i L' -jy' , i E 6.7. Records I 6.7.2. The following records shall be kept for a minimum period of five yearst- ;
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- a. reactor operating logs; t' !
- b. irradiation request cheetsi 3
- c. checkout sheets;
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- d. raintenance recordat f f
- e. calibration records; M
- i. f. records of reportable occurrences; !
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- g. j g. fuel inventories, receipts, and shipments; i
- h. minutes of ROC meetings; _
c- 1. recos.ds of audites
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- j. facility radiation and contamination surveyst. j and l
- k. surveillance activities as required by the ~i Technical Specifications. _!
. 6.7.2 Records of the retraining and requalification of.
ksactor Operators and Senior. Reactor Operators shall be retained for at'least one complete , requalification-schedule. ; ~ . l(J 6.7.3. The following records shall be retained for'the F 31fetime of the reactort- l 9
- a. reco'rds of
- gaseous'and liquid radioactive effluents released to the environments
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- b. records of the radiation exposure of all f i ,
individuals monitored; and 5,
- c. drawings of the reactor' f acility.'
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i = Amendment'No. 6
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