ML19309H098
| ML19309H098 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 04/30/1980 |
| From: | ARKANSAS POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML19309H096 | List: |
| References | |
| NUDOCS 8005080372 | |
| Download: ML19309H098 (14) | |
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'i REACTIVITY CONTROL SYSTEMS 8 005 080 N SHUTDOWN MARGIN - Tavg
- 200*F LIMITIfiG CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN !%RGIN shall be > 2.0% Ak/k.
I APPLICABILITY: MODE 5. .
ACTION: E" With the SHUTDOWN MARGIN < 2.0% ak/k. innediately initiate and continue l boration at > 40 gpm of 1731 ppm boric acid solution or equivalent until =
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the required SHUTDOWN IMRGIN is restored.
SURVEILLANCE REQUIREMENTS - 4.1.1.2 The SHUTDOWN MARGIN shall be determined to be > 2.0% ak/k: l _
- a. Within one hour after detection of an inoperable CEA(s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the CEA(s) is inoperable.
If the inoperable CEA is innovable or untrippable, the above required SHUTDOWN MARGIN shall be increased by an amount at least equal to the withdrawn worth of the immovable or untrip-pable CEA(s).
- b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration of at least the , au following factors:
- 1. Reactor coolant system boron concentration,.
- 2. CEA position,
- 3. Reactor coolant systent average temperature,
- 4. Fuel burnup based on gross thermal energy generation,
- 5. Xenon concentration, and
- 6. Samarium concentration. .
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REACTIVITY CONTROL SYSTEMS %::B' .f; BORON DILUTION t df _
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3 LIMITING CONDITION FOR OPERATION
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3.1.1.3 The flow rate of reactor coolant through the reactor coolant system shall be > 3000 gpm whenever a reduction in Reactor Coolant System" boron concentration is being made. ,
APPLICABILITY: ALL MODES.
ACTION: - $!! -
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With the flow rate of reactor coolant through the reactor coolant system }@. ,
< 3000 gpm, immediately suspend all operations involving a reduction b in boron concentration of the Reactor Coolant System. h; &
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SURVEILLANCE REQUIREMENTS }
4.1.1.3 The flow rate of reactor coolant through the reactor coolant system shall be determined to be > 3000 gpm within one hour prior to 'iz , . .
the start of and at least once per hour during a reduction in the " "E Reactor Coolant System boron concentration by either:
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- a. Verifying at least one reactor coolant pump-is in operation, g or UX r
- b. Verifying that at least one low pressure safety injection pump :
is in operation and supplying >_ 3000 gpm through the reactor 5 -
coolant system. .
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. REACTIVITY CONTROL SYSTEMS 3/4.1.2 B0 RATION SYSTEMS FLOW PATHS - SHUTDOWN 1
LIMITING CONDITION FOR OPERATION 3 .1. 2.1 As a minimum, one of the following boron injection flow paths 1 and one associated heat tracing circuit shall be OPERABLE:
- a. A flow path from the boric acid makeup tank via either a boric acid makeup pump or a gravity feed connection and charging pump to the Reactor Cooiant System if only the boric acid makeup tank in Specification 3.1.2.7a is OPERABLE, or
- b. The flow path from the refueling water tank via either a charging pump or a high pressure safety injection pump to the Reactor Coolant system if only the refueling water tank in Specification 3.1.2.7b is OPERABLE. =
APPLICABILITY: MODES 5 and 6.
ACTION:
With none of the above flow paths OPERABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until at least one injection path is restored to OPERABLE status.
5 SURVEILLANCE REQUIREMENTS 4.1.2.1 At least one of the above required flow paths shall be demon-strated OPERABLE:
- a. At least once per 7 days by verifying that the' temperature of the heat traced portion of the flow path is above the temperature limit line shown to Figure 3.1-1 when a flow path from the boric acid makeup tanks is used.
- b. At least once per 31 days by verifying that each valve (manual, iii power operated or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its ES correct position. .y..y 5
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FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION _
3.1.2.2 At least two of the following three boron injection flow paths ii and one associated heat tracing circuit shall be OPERABLE: h E=
- a. Two flow paths from the boric acid makeup tanks via either a $ .
boric acid makeup punp or a gravity feed connection, and a @
charging pump to'the Reactor Coolant System, and !)
- b. The flow path from the refueling water tank via a charging Dump to the Reactor Coolant System.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION: -
With only one of the above required boron injection flow paths to the Reactor Coolant System OPERABLE, restore at least two baron injection flow paths to the Reactor Coolant Sistem to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least H0T STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least 2". ak/k at 200*F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore l at least two flow paths to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. .
SURVEILLANCE REQUIREMENTS _
4.1.2.2 At least two of the above required flow paths shall be demonstrated OPERABLE:
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- a. At least once per 7 days by verifying that the temperature of '
the heat traced portion of the flow path from the boric acid makeup tanks is above the temperature limit line shown on Figure 3.1-1, i
- b. At least once per 31 days by verifying that each valve (manual, power operated or automatic) in the flow path that is not locked, 9 sealed, or otherwise secured in position, is in its correct ~
position.
! c. At least once per 18 months during shutdown by verifying that .
l each actuated valve in the flow path actuates to its correct gut::::
position on a SIAS test signal. !!!
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REACTIVITY CONTROL SYSTEMS ;m CHARGING PUMP - SHUTDOWN H. 8 LIMITING CONDITION FOR OPERATION ..!
3.1.2.3 At least one charging pump in the boron injection flow path -
is required OPERABLE pursuant to Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency bus.
111 APPLICABILITY: MODES 5 and 6. .
ACTION:
With no charging pump OPERABLE, suspend all operations involving CORE . .. u ALTERATIONS or positive reactivity changes until at least one gf the required pumps is restored to OPERABLE status.
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4.1.2.3 No additional Surveillance Requirements other than those required by Specification 4.0.5. y t
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REACTIVITY CONTROL SYSTEMS J.0.'""U" CHARGING PUMPS - OPERATING N m:
3.g LIMITING CONDITION FOR OPERATION ;91!)
iii 3.1. 2 . 4 At least two charging pumps shall be OPERABLE. ...,I!
M APPLICABILITY: MODES 1, 2, 3 and 4. ...' ..!!.w.
ACTION: .
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us 2.Wr With only one charging pump OP'ERABLE, restore at least two charging ' a pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY ;;;g and borated to a SHUTDOWN MARGIN equivalent to at least R% ak/k at 200'F l 'jjjjj; within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least two charging pumps to OPERABLE . . . . . .
status within the next 7 days or be in COLD SHUTDOWN within the next 30 "' y hours. h i
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i mii, 4 .1. 2. 4 No additional Surveillance Requirements other than those required ,..""y by Speci fication 4.0.5.
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REACTIVITY CONTROL SYSTEMS BORIC ACID MAKEUP PUMPS - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.5 At least one boric acid makeup pump shall be OPERABLE and capable of being powered from an OPERABLE emergency bus if only the flow path through the boric acid makeup pump in Specification 3.1.2.la above, is OPERABLE.
APPLICABILITY: MODES 5 and 6.
ACTION:
With no boric acid makeup pump OPERABLE as required to complete the flow path of Specification 3.1.2.la, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until at least one boric acid makeup. pump is restored to OPERABLE status.
SURVEILLANCE REQUIREMENTS 4.1.2.5 No additional Surveillance Requirements other than those required by Specification 4.0.5.
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REACTIVITY CONTROL SYSTEMS sF e E BORIC ACID MAKEUP PUMPS - OPERATING _
E LIMITING CONDITION FOR OPERATION g 3.1.2.6 At least the boric acid makeup pump (s) in the boron injection s
flovi path (s) required OPERABLE pursuant to Specification 3.1.2.2a shall be OPERABLE and capable of being powered from an OPERABLE emergency bus .
3 if the flow path through the boric acid makeup pump (s) in Specification j; 3.1.2.2a is OPERABLE.
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APPLICABILITY: MODES 1, 2,'3 and 4.
ACTION: ;;)
With one boric acid makeup pump required for the boron injection flow ,
path (s) pursuant to Specification 3.1.2.2a inoperable, restore the boric acid makeup pump to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a SHUTDOWN MARGIN m equivalent to at least 2% Ak/k at 200'F; restore the above required l boric acid pump (s) to OPERABLE status within the next 7 days or be in ....
COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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SURVEILLANCE REQUIREMENTS 4 .1. 2. 6 No additional Surveillance Requirements other than those required by Specification 4.0.5.
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REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING ,
i LIMITING CONDITION FOR OPERATION 3.1.2.8 Each of the following borated water sources shall be OPERABLE:
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- a. At least one boric acid makeup tank and one associated heat
- cracing circuit per tank with the contents of the tank in accordance with Figure 3.~1-1, and
- b. The refueling water tank with:
- 1. A contained borated water volume of between 464,900 and 500,500 gallons (equivalent to an indicated tank, level of between 91.7% and 100%, respectively),
- 2. Between 1731 and 2250 ppm of boron,
- 3. A minimum solution temperature of 40 F, and
- 4. A maximum solution temperature of 100 F.
APPLICABILITY: MODES 1, 2, 3 and 4.
ACTION:
- a. With the above required boric acid makeup tank inoperable, restore the make up tank to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and borated to a SHUTDOWN MARGIN equivalent to at least 2 % ok/k at 200*F; l "I restore the above required boric acid makeup tank to OPERABLE ;=3 status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />,
- b. With the refueling water tank inoperable, restore the tank to OPERABLE status within one hour or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.1. 2. 8 Each of the above raquired borated water sources shall be 3
demonstrated 00ERABLE: -
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REACTIVITY C0fiTROL SYSTEMS "".. i ::\ ma il: m SURVEILLANCE REQUIREMENTS (Continued) ... ES .. .. .
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- 1. Verifying the boron concentration in each water source, 7,.,,
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- 2. Verifying the contained borated water volume in each p~
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- 3. Verifying' the boric acid makeup tank solution temperature. ${! "'
- b. At least once per 24 hours by verifying the RWT temperature, fi.( . . . . .
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3/4.1.1 BORATION CONTROL c~ E 3/4.1.1.1 and 3/4.1.1.2 SHUTOOWN MARGIN 3
- 4 A sufficient SHUTDOWN MARGIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity transients h "
associated with postulated accident conditions are controllable within e acceptable limits, and 3) the reacto." will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition. 17; g e .@ SHUIDOWN MARGIN requirements vary throughout core life as a function :... nii?j of fuel depletion, RCS boron concentration, and RCS T . The most N ti restrictive condition occurs' at E0L, with T at no M d operating g@ temperature, and is associated with a postuMEed steam line break accident ~ and resulting uncontrolled RCS cooldown. In the analysis of'this accident, a minimum SHUTDOWN MARGIN of 5.0i, ak/k is required to control the reactivity transient. Accordingly, the SHUTOOWN MARGIN requirement is ... m-based upon this limiting condition and is consistent with FSAR safety piii,f analysis assumptions. With T ing from any postulated accid $XE Fre minimal and a 2% ak/k shutdown < 2 margin provides adequate protection. 3/4.1.1.3 BORON DILUTION . A minimum flow rate of at least 3000 GPM provides adequate mixing, prevents stratification and ensures that reactivity changes will be gradual during boron concentration reductions in the Reactor Coolant B System. A flow rate of at least 3000 GPM will circulate an equivalent E 4 Reactor Coolant System volume of 9,975 cubic feet in approximately c!r :s 25 minutes. The reactivity change rate associated with boron concen- ... !M tration reductions will therefore be within the capability of operator
- recognition and control.
3/4.1.1.4 MODERATOR TEMPERATURE COEFFICIENT (MTC) :/.figif:
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- Wb The limitations on MTC are provided to ensure that the assumptions ,
used in the accident and transient analysis remain valid through each' fuel cycle. The surveillance requirements for measurement of the MTC during each fuel cycle are adequate to confinn the MTC value since this !!!.
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coefficient changes slowly due principally to the reduction in RCS boron
- si concentration associated .fith fuel burnup. The confirmation that the measured MTC value is within its limit provides assurances that the d
R coefficient will be maintained within acceptable values throughout each
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{ 19 3/4.1.1.5 MINIMUM TEMPERATURE FOR CRITICALITY _ g This specification ensures that the reactor will not be made is . ... critical with the Reactor Coolant System average temperature less than ,
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a 525'F. This limitation is required to ensure 1) the moderator temperature - coefficient is within its analyzed temperature range, 2) the protective . instrumentation is within its normal operating range, 3) the pressurizer .,j. ..ij. m is capable of being in an OPERABLE status with a steam bubble, and 4) the (T.- reactor pressure vessel is above its minimum RTNDT temperature. g. ik \Ya 3/4.1.2 B0 RATION SYSTEMS yy l Unim The boron injection system ensures that negative reactivity control M is available during each mode of factitty operation. The components n "'" required to perform this function include 1) borated water sources, 2)
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] charging pumps, 3) separate flow paths, 4) boric acid makeup pumps, 5) associated heat tracing systems, and 6) an emergency power supply from OPERABLE diesel generators. .A With the F.CS average tenperature above 200'F, a minimum of two separate and redundant boron injection systems are provided to ensure single functional capability in the event an assumed failure renders one m of the systems inoperable. Allowable out-of-service periods ensure that - minor component repair or corrective action may be completed without g undue risk to overall facility s.fety from infection system failures Sj during the repair period. , a The boration capability of either system is sufficient to provide a iiii SHUTDOWM MARGIN fron expected operating conditions of 2.00ak/k after l 9 xenon decay and cooldown to 200'F. The maximum expected boration cap- i. >gg. ability requirement occurs at EOL from full power equilibrium xenon !v conditions and requires boric acid solution from the boric acid makeup tanks in the allowable concentrations and . volumes of Specification 3.1.2.8 E or 40,200 gallons of 1731 ppm borated water from the refueling water tank. With the RCS temperature below 200'T one injection system is acceptable withcut single failure consideration on the basis of the ri;;. stable reactivity condition of the reactor and the additional restric-tions prohibiting CORE ALTERATIONS and positive reactivity change in the ;;; :.: iis event the single injection system becomes inoperable. Te:.(!! . iv
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..=0m The boron capability required below 200*F is based upon providing a :
2% Ak/k SHUTDOWN MARGIN after xenon decay and cooldown from 200*F to 140*F. l This condition requires either 4700 gallons of 1731 ppm borated water : from the refueling water tank or boric acid solution from the boric acid _ makeup tanks in accordance with the requirements of Specification 3.1.2.7. The contained water volume limits includes allowance for water not available because of discharge line location and other physical characteristics. The 37,100 gallon limit for the refueling water tank _ is based upon having an indicated level in the tank of at least 2*' . The OPERABILITY of one boron injection system during REFUELING ensures that this system is available for reactivity control while in " MODE 6. The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 8.9 and 11.0 for the solution recirculated within containment after a LOCA. This pH band minimizes the 3.,; evolution of iodine and minimizes the effect of chloride and caustic ' " ~ stress corrosion on mechanical systems and components. 3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is maintained, and (3) the potential effects of CEA misalignments are limited to acceptable levels. The ACTION statements which permit limited variations from the N basic rnquirements are accompanied by additional restrictions which b ensure that the original design criteria are met. The ACTION statements applicable to a stuck or untrippable CEA, to two or more inoperable CEAs, and to a large misalignment (> 19 inches) of two or more CEAs, require a prompt shutdown of the reactor since any i. :. of these conditions may be indicative of a possible loss of mechanical functional capability of the CEAs and in the event of a stuck or untrip- - able CEA, the loss of SHUTDOWN MARGIN. iE For small misalignments (< 19 inches) of the CEAs, there is 1) a rig small effect on the time dependent long tenn power distributions rela-tive to those used in generating LCOs and LSSS setpoints, 2) a small -:grii;- effect on the available SHUTDOWN MARGIN, and 3) a small effect on the ejected CEA worth used in the safety analysis. Therefore, the ACTION - ARKANSAS UNIT 2 B 3/4 1-3 t e% wwu wu
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1 f"a 0 REACTIVITIY CONTROL SYSTEMS E" g w . BASES - statement associated with small misalignments of CEAs permits a one hour time interval during which attempts may be made to restore the CEA to : within its alignment requirements. The one hour time limit is sufficient to (1) identify causes of a misaligned CEA, (2) take appropriate correc-tive action to realign the CEAs and (3) minimize the effects of xenon redistribution. ~ m The CPCs provide protection to the core in the event of a large ~ misalignment (> 19 inches) of a CEA by applying appropriate penalty b factors to the calculation to account for the misaligned CEA. However, 6 this misalignment would cause distortion of the core power distribution. This distribution ray, in turn, have a significant effect on 1) the w3.: available SHUTDOWN f: GIN, 2) the time dependent long term power distri-butions relative to those used in generating LCOs and LSSS setpoints, and 3) the ejected CEA worth used in the safety analysis. Therefore, the ACTION statement associated with the large misalignment of a CEA requires a prompt realignment of the misaligned CEA. The ACTION statements applicable to misaligned or inoperable CEAs include requirements to slign the OPERABLE CEAs in a given group with the . inoperable CEA. Conformance with these alignment requirements brings the core, within a short period of time, to a configuration consistent with that assumed in generating LC0 and LSSS setpoints. However, extended - operation with CEAs significantly inserted in the core may lead to perturbations in 1) local burnup, 2) peaking factors and 3) available SHUTDOWN MARGIN which are more adverse than the conditions assumed to . exist in the safety analyses and LC0 and LSSS setpoints determination. Therefore, time limits have been imposed on operation with inoperable CEAs to preclude such adverse conditions from developing. Operability of at least two CEA position indicator channels is required to determine CEA positions and thereby ensure compliance with tne CEA alignment and insertion limits. The CEA " Full In" and " Full Out" limits provide an additional indepen' dent means for determining the CEA positions when the CEAs are at either their fully inserted or fully withdrawn positions. Therefore, the ACTION statements applicable to inoperable CEA position indicators penn'it continueo operations , hen the positions of CEAs with inoperable position indicators can be verified by the " Full In" or " Full Out" limits. is l ARKANSAS - UNIT 2 B 3/4 1-4
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