Text

Proposed Tech Specs Associated W/Control Room Emergency Ventilation Sys
	ML20082C587
Person / Time
Site:	Arkansas Nuclear
Issue date:	04/04/1995
From:	; ENTERGY OPERATIONS, INC.
To:	;
Shared Package
ML20082C586	List: 0CAN049501, Application for Amends to Licenses DPR-51 & NPF-6,revising TS Associated W/Control Room Ventilation Sys; ML20082C587;
References
	NUDOCS 9504070087
	Download: ML20082C587 (52)
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1 TABLE OF CONTENTS i

LSECTION- TITLE PAGE 'l t

i 1.' DEFINITIONS ~1 l' 1.1, RATED POWER 1

!- 1.2 REACTOR OPERATING CONDITION :1 1.3 OPERABLE ^2

{1.4 PROTECTION INSTRUMENTATION LOGIC '2 ,

-1.5 INSTRUMENTATION-SURVEILLANCE' '3 )

106 POWER DISTRIBUTION- '4

.1.7 REACTOR BUILDING ..

.5 1.8 FIRE SUPPRESSION MATER SYSTEM 5 1.9 STAGGERED' TEST BASIS- 5 1.10 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS Sa 'l I

-(RETS) DEFINITIONS 1.11 CORE OPERATING IlMITS REPORT i6' 'l

2. SAFETY LIMITS AND LIMITINE SAFETY SYSTEM SETTINGS- 7- '

2.1 SAFETY LIMITS REACTOR CORE. 70 i

'2.2 SAFETY LIMITS, P2. ACTOR SYSTEM PRESSURE 10; j 2.3 LIMITING-SAFETY SYSTEM SETTINGS, PROTECTIVE j INSTRUMENTATION 11 .

-16 j

'3. LIMITING CONDITIONS'FOR OPERATION' 3.1 REACTOR COOLANT SYSTEM 16 j 3.1.1 Operational Components- .

16 l 3.1.2 Pressurization, Heatup and Cooldown Limitations 18 j 3.1.3 Minimum conditions for Criticality 21 r 3.1.4 Reactor Coolant System Activity '23- I 3.1.5 Chemistry 25 l

.3.1.6 Leakage- .

27 ;

3 .1. 7 - Moderator Tens >erature Coefficient of Reactivity - 30 j 3.1.8 Low Power Physics Testing Restrictions 31 ;

3.1.9 Control Rod Operation '32 ,

3.2 MAKEUP AND CHEMICAL ADDITION SYSTEMS 34 !

3.3 EMERGENCY CORE COOLING, REACTOR BUILDING COOLING, l AND REACTOR BUILDING SPRAY SYSTEMS 36 <

3.4 STEAM AND TOWER CONVERSION SYSTEM 40 !

3.5 INSTRUMENTATION SYSTEMS 42 l l

3.5.1 ' Operational Safety Instrumentation: .

'42-l 3.5.2 Control Rod Group and Power Distribution Limits 46

! 3.5.3 Safety Features Actuation System Setpoints 49

-3.5.4 'Incore Instrumentation- 51 3.5.5 Fire Detection Instrumentation .

53d 3.5.6 Radioactive Liquid Effluent Instrumentation 53f-

'3.5.7 Radioactive Gaseous Effluent Instrumentation 53I 3.6 RFACTOR BUILDING 54-3.7 AUXILIARY ELECTRICAL SYSTEMS 56 3.8- FUEL LQADING AND REFUELING 58 3.9 CONTROL ROOM EMERGENCY VENTILATION AND AIR.

CONDITIONING SYSTEM .60

' 3.10 SECONDARY SYSTEM ACTIVITY 66 3.11 EMERGENCY COOLING POND 66a 3.12 MISCELLANEOUS RADIOACTIVE MATERIALS SOURCES 66b 3.13 PENETRATION ROOM VENTILATION' SYSTEM 66c I

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' Amendment No. M ,48,M 9 i q

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3- i SECTION TITLE-- PAGE i

e 3.14- HYDROGEN RECOMBINERS1 ..

'66e-

'3.15. FUEL HANDLING AREA VENTIIATION FLITEM 66g 3.16

SHOCK SUPPRESSORS (SNUBBERS) ;661 j-3.17 ~ FIRE SUPPRESSION MATER SYSTEM. :66m-3.18 FIRE SUPPRESSION SPRINNLER SYSTEMS 66n- ;j 13.19 CONTROL ROOM AND AUXILIARY CONTROL ROOM MALON l i .

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SYSTEMS ~66o !

l 3.20 ~ ' FIRE HOSE STATIONS 66p l l 3.21 FIRE BARRIERS: 66q '

3.22 REACTOR BUILDING PURGE FILTRATION SYSTEM 66r

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3.23 REACTOR' BUILDING PURGE VALVES- -66t p -3.24 EXPLOSIVE GAS MIXTURE :66u l_ '3.25 RADIOACTIVE EFFLUENTS 66v

(- 3.25.1.. Radioactive Liquid Effluents > 66v

- ~ 3.25.1.1 Concen: ration 66v?

! 3.25.1.2 . Dose 66w I 3.25.1.3 Waste Treatment; '

66x

!' 3.25.1.4 Liquid Holdup Tanks _

66y

3.25.2- Radioactive Gaseous Effluents -

662c I- 3.25.2.1 Dose-Rate -662 3.25.2.2. Dose - Noble Gases 66aa f) .

3.25.2.3 Dose - Iodine-131, Tritium, and Radionuclides

! -in Particulate Form- 66bb j 3.25.2.4 Gaseous.Radwaste Treatment ' 66P 3.25.2.5 Gas' Storage Tanks 66dd

! 3.25.3 Total Dose. 66ee i 3.25:4- . Solid Radioactive Waste 2 '66ff.

[- 4. SURVET LANCE REQUIREMENTS 67=

i 4.1 OPERATIONAL SAFETY ITEMS '67'

!' 4.2 REACTOR COOLANT SYSTEM SURVEILIANCE 76 I 4.3 TESTING FOLI4 WING OPENING OF SYSTEM 78 2

4.4 REACTOR BUILDING .

79

, 4.4.1: Reactor Buildire Leakage Tests 79 i 4.4.2 Structural Integrity 85 ~'

! .4.5 EMERGENCY CORE COOLING SYSTEM AND REACTOR-

!. BUILDING COOLING SYSTEM PERIODIC TESTING 92:

, 4.5.1 Emergency Core Cooling Systems 92 4.5.2 Reactor Building cooling Systems 95 i 4.6 AUXILIARY ELECTRICAL SYSTEM TESTS 100 l 4.7 REACTOR CONTROL ROD SYSTEM TESTS- 102

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4.7.1 Control Rod Drive System Functional' Tests 102 i 4.7.2 Control Rod Program Verification 104 4

'4.8 EMERGENCY FEEDWATER PUMP TESTING 105

!' 4.9 REACTIVITY ANOMALIES- 106

, 4.10 CONTROL ROOM EMERGENCY VENTIIATION AND AIR CONDITIONING

SYSTEM OURVEILLANCE 107 4 4.11 PENETRAT20N ROOM VENTIIATION SYSTEM SURVEILLANCE 109 i 4.12 HYDROGEN KECOMBINERS SURVEILLANCE 109b

{' 4.13 EMERGENCY COOLING FOND 110a j 4.14 RADIQACTIVE MATERIALS SOURCES SURVEILLANCE 110b

. 4.15 AUGMENTED INJERVICE INSPECTION PROGRAM FOR HIGH

! ENERGY LINES OUTSIDE OF CONTAINMENT .110c 4

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" Amendment No. M,M,44,M,M,64,M, 11

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i 3.5.1.7 The Decay Heat Removal System isolation valve closure setpoints shall be equal to or less than 340 psig for one valve and equal to or less than 400 psig for the second valve in the suction line. The relief valve setting for the DHR system shall be equal to or less than 4:0 psig.

3.5.1.8 The degraded voltage monitoring relay settings shall be as I follows:

a. The 4.16 KV emergency bus undervoltage relay setpoints-shall be >3115 VAC but <3177 VAC.

b. The 460 V emergency bus undervoltage relay setpoints shall be >423 VAC but <431 VAC with a time delay setpoint of 8 seconds il second.

3.5.1.9 The following Reactor Trip circuitry shall be operable as indicated:

1. Reactor trip upon loss of Main Feedwater shall be

operable (as detenmined by Specification 4.1.a and item 35 of Table 4.1-1) at greater than 5% reactor power.

l (May be bypassed up to 10% reactor power.) I t i

2. . Reactor trip upon Turbine Trip shall be operable'(as determined by Specification 4.1.a and item 41 of Table' 4.1-1) at greater than 5% reactor power. (May be I bypassed up to 45% reactor power.) j l'

3. If the requirements of Specifications 3.5.1.9.1 or l 3.5.1.9.2 cannot be met, restore the inoperable trip within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or bring the plant to a hot shutdown condition.

3.5.1.10 Two independent control room ventilation chlorine detection systems shall be operable and capable of actuating control ;

room isolation and the emergency ventilation systems, with alarm / trip setpoints adjusted to actuate at a chlorine concentration of $5 ppm whenever the reactor coolant system is above the cold shutdown condition.

4 3.5.1.11 For on-line testing of the Emergency Feedwater i Initiation and Control (EFIC) system channels during power I j operation only one channel shall be locked into " maintenance bypass" at any one time. If one channel of the NI/RPS is in

. maintenance bypass, only the corresponding channel of EFIC may

be bypassed.

3.5.1.12 The Containment High Range Radiation Monitoring instrumentation 7

shall be operable with a minimum measurement range from 1 to 10 R/hr.

Amendment No. W,G,49,M,M,M4 42a

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l 3.5.1.13EThe seismic Monitoring Instrumentation shall.be operable with a

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sdnf mum measurement range of 0.01 - 1.0 g' for Triaxial Time -

History Accelerographs, 0.05 .1.0 g for Triaxial' Peak'

- Accelerographs, and 2-25.4 Hz for Triaxial Response Spectrum

. Recorders. ,

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j '3.5.1.14l The Main Steam Line~ Radiation Monitoring Instrumentation shall' i

be4operable with a minimum measurement range from 10 2 to

4 10 mR/hr, whenever the reactor-is above the cold shutdown. ;

condition.

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!. .3.5.1.15 Initiate' functions of the EFIC' system which are; bypassed at cold [

shutdown conditions shall have the following minimum' operability-i'

-conditions: ,

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! a. " low steam' generator pressure" initiate shall be operable when 1 the main steam pressure exceeds 750 psig. l 3

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" loss of 4 RC pumps" initiate shall be operable when neutron ,

l flux: exceeds 10% power. !

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j c. " main feedwater pumps tripped"~ initiate shall be operable when ;

neutron flux exceeds 10% power. ;

1 l 3.5.1.16 The automatic steam generator isolation system within EFIC'shall be- .

I operable when main steam pressure is greater than 750 psig. !

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5 3.5.1.17 Two' independent control room ventilation radiation monitoring systems'

.shall be operable whenever the reactor coolant system is.above the . l cold shutdown condition or whenever'the reactor coolant system is in !

j the refueling shutdown condition with handling of irradiated fuel in j i progress in the reactor building.

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j j- Amendment No. 41%,444,444,4M . 42b 1

The OPERABILITY of the Seismic Monitoring Instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.

This capability is required to permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is required pursuant to Appendix "A" of 10CFR Part 100. The instrumentation is l consistent with the recommendations of Safety Guide 12, " Instrumentation for Earthquake," published March 19, 1971, and NUREG-0800 Section 3.7.4, " Seismic .

Instrumentation." )

l The principal function of the Control Room Isolation-High Radiation is to provide l l

an enclosed environment from which the unit can be operated following an j l uncontrolled release of radioactivity. The high radiation isolation function l l provides assurance.that under the required conditions, an isolation signal will l I

be given. Due to the unique situation of the shared control room habitability, one ANO-1 control room isolation channel receives a high radiation signal from !

the ANO-1 control room area radiation monitor (RE-8001) and the redundant channel I receives a high radiation signal from the ANO-2 control room ventilation process monitor (2RITS-6750-1) . With no channel of the control room radiation monitoring I system operable,-the CREVS must be placed in a condition that does not require the isolation to occur. To ensure that the ventilation system has been placed in a state equivalent to that which occurs after the high radiation isolation has occurred, one OPERABLE train of the CREV3 is placed in the emergency recirculation mode of operation. Reactor operation can continue indefinitely in this state. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time is a sufficient amount of time in which to take the Required Action.

REFERENCE FSAR, Section 7.1 FSAR, Section 2.7.6 l

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Amendment No. -lu 43c

Table 3.5.1-1 (cont'd)

OTHER SAFETY REIATED SYSTEMS (Cont'd) 1 2 3 4 5 No. of Operator action channels Min. Min.- if conditions of.

No.,of for sys- operable. degree of coltuun 3 or 4 ,

Functional Unit channels tem trip channels redundancy cannot be met

c. Triaxial Response-Spectrum Recorders

1. 2XR-8350, Unit 2 Containment 1 N/A 1 0 Note 27

' Base slab, Elev. 335' 6" O/S Containment)

15. Reactor Vessel Level Monitoring System 2 N/A. 2 0 Note 28, 29

16. Hot Leg Level Measurement System (HLIMS) 2 N/A .2 _ 0. Note 28, 29

17. Main Steam Lir 1 / steam line N/A 1/ steam line: 0 Note 30 Radiation Mo- *s

18. Control Room 2. I 1 0- Note.17, 18 Radiation Monitor-Amendment No. 4M,M3 45d2

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TABLE 3.5.1-1 (Cont'd)

12. With the number of operable channels less than required, either return the indicator to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or verify the block valve closed and power removed within an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . If the block valve cannot be verified closed within the additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , de-energize the electromatic relief valve power supply within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

13. Channels may be bypassed for not greater than 30 seconds during reactor coolant pump starts. If the automatic bypass circuit or its alarm circuit is inoperable, the undervoltage protection shall be restored within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , otherwise, Note 14 applies.

14. With the number of channels less than required, restore the inoperable channels to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in NOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

15. This trip function may be bypassed at up to 10% reactor power.

16. This trip function may be bypassed at up to 45% reactor power.

17. With no channel operable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the control room' l emergency ventilation system in the recirculation mode of operation.

18. With one channel inoperable, restore the inoperaM e channel to operable status within 7 days or within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.

19. This-function may be bypassed below 750 psig OTSG pressure. Bypass is' automatically removed when pressure exceeds 750 psig.

20. With one channel inoperable, (1) either restore the inoperable channel to operable status within-7 days, o_r (2) prepare and submit a Special Report to the Conunission pursuant to Specification 6.12.5 within 30 days following the event, outlining the action taken, the cause of the inoperability, and the plans and schedule for restoring the system'to operable status. With both channels inoperable, initiate alternate methods of monitoring the containment-radiation level within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in addition to the actions described above.

21. With one channel inoperable, rsstore the inoperable channel to operable status within 30 days or be in hot shutdown within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months unless containment entry is required. If containment entry is required, the inoperable channel must be restored by the next refueling outage. If both channels are inoperable, restore the inoperable channels within 30 days or be in HOT. SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Amendment No. 49,M,49,9b 94,-144,-144 45f

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3 p .3.8.15 storage in the spent fuel pool.'shal1Lbe restricted to fuel assembliesL {

! having initial enrichment less than'.or equal to 4.1.w/o.U-235. The i F provisions lof Specification 3.0.3 are not applicable.. {

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b 3.8.16 storage in ' Region 2 ' (ss shown on: Figure 3.8.1)- of. the spent fuel pool j

[' .shall.be further restricted by burnup and enrichment limits specified in. '

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a Figure 3.8.2. In the event.a checkerboard storage configuration'is deemed necessary for.a portion _of Region'2,. vacant spaces adjacent to-

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! the. faces,of any fuel assembly which does not meet'the Region 24burnup j- criteria (non-restricted) shall'be. physically blocked before any such j F fuel assembly may be placed in Region 2. This will prevent inadvertent )

i fuel assembly insertion into two' adjacent storage locations. The .j provisions of specification 3.0.3'are not applicable.

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{- 3.8.1'1 -The boron concentration in'the spent fuel' pool ~shall be maintained (at' -

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all times) at greater than 1600 parts per million. j I

, 318.18 During the handling of irradiated fuel in the reactor' building, thel I l control.. room emergency air. conditioning system and'the control-room )

{ emergency ventilation system shall be operable as required by' l Specification.3.9.1.

i, i f; Bases Detailed written procedures will be available for.use by refueling personnel.. .

j These procedures, the above specifications,.and the design.of the fuel handling

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3 equipment as described in section 9.6 ofithe FSAR incorporating: built-in interlocks and safety features, provide assurance'that no' incident could occur during the refueling operations that would result in a hazard'to public health?

l j 'and safety. .If no change is being made in core geometry, one flux monitor.is.

4 sufficient. This permits maintenance on'the instrumentation. ' continuous-l monitoring of radiation levels and. neutron flux provides immediate indication of p an unsafe condition.

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{ The requirement that at least one decay heat' removal loop be in operation

j. ensures that (1) sufficient cooling capacity is.available.to remove decay heat ,

and maintain the water in the reactor pressure. vessel'at the refueling'

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j i toeperature .(normally 140*F), and (2) sufficient coolant. circulation is i maintained through the reactor core to minimize the' effects:of a-boron dilution

} incident and prevent boron stratification. (8)

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j The requirement to have two decay. heat removal'1 oops operable when there is less

< than 23 feet of water above the core,' ensures'that a single failure of the

! operating decay heat removal loop will not-result in a complete loss of decay.

l heat removal. capability. With the reactor vessel head removed and 23' feet of-water above the core, a large heat sink is available.for core cooling, thus in l the event of a failure of the. operating decay heat removal loop, adequate time j is provided to initiate emergency procedures to cool the core.

I i The shutdown margin indicated in Specification 3.8.4 will keep,the core 5

suberitical, even with all control rods withdrawn from the core. (8) Although the refueling boron concentration is sufficient to maintain the core keff 5 0.99

. if all the control rods were removed from the core, only a few control rods will

j. be removed at any one time during fuel shuffling and i

l I Amendsent No. W ,M ,M ,M ,M 7,M S, 5Da 1 4G,MS I

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3. 9' CONTROL ROOM EMERGENCY VENTIIATION AND AIR CONDITIONING SYSTEMS 'l l Applicability.

Applies to.the operability of the control room emergency ventilation and. air i conditioning systems. l Objective To ensure that the control room emergency ventilation and air' conditioning systems'will perform within acceptable levels of efficiency and reliability.

Specification .)

1 3.9.1 Control Roan Emergency Air Conditioning System l 3.9.111 Two' independent trains of the control room emergency air )

conditioning system shall be operable whenever the reactor j coolant system is above the cold shutdown condition or' I whenever the reactor coolant system is in the refueling .l shutdown condition with handling of irradiated fuel in- l progress.in-the reactor building.

3.9.1.2 With one control room emergency air conditioning system j inoperable, restore the inoperable system to Operable status- l within 30 days or be in at least Hot Shutdown within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in Cold Shutdown within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

3.9.2 control' Roan Emergency Ventilation System- ,

3.9.2.1- Two independent trains of. the control room emergency. ventilation system shall be operable whenever the reactor coolant' system is ;

above the cold shutdown condition or whenever the reactor- ;

coolant' system is in the refueling shutdown condition with {

handling of. irradiated fuel in progress.in the reactor building. l 5

3.9.2.2 With one control room emergency ventilation system inoperable, I restore the inoperable system to Operable' status within 7 days :

or.be in at least Hot Shutdown within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in Cold shutdown within.the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . ,

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1 Amendment No. M,M 60

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' Bases- .

h IThe control room emergency ventilation and air conditioning' system is designed to -

isolate the-combined control rooms to ensure that the control rooms will remain ~ j habitable for operations; personnel during and following all credible accident' _

I conditions ~and to' ensure that the ambient air temperature does not exceed the j

{' allowable temperatureifor continuous duty rating for the equipment and .

'j instrumentation cooled by'this system. The design configuration of the system is-i based on Itaiting.the radiation' exposure to. personnel occupying the control room .,

i to:5 REN'or:less whole body, or-its equivalent, in accordance.with the j

[ requirements of General Design Criteria 19 of Appendix A,.10CrR 50.

Unit 1'and Unit 2 control rooms are a single environment"for emergency Jventilation and air conditioning concerns. Since.the control' room emergency.

I ventilation and air conditioning equipment is shared between units, the plant j ' status'of both. units must be considered when determining' applicability of the.

I specification.

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l Due to the unique situation of the shared emergency ventilation and air l

conditioning equipment, the components may be cross fed from the opposite unit

per predetermined contingency actions / procedures. During modes'when the emergency contro1~ room ventilation and emergency air conditioning.is not required

( on Unit 2, Unit 1 may take' credit for operability oflthese systems when

[ configured to achieve' separation and independence regardless of. normal power-l and/or: service water configuration. This will be in accordance with pre-t-

determined. contingency actions /orocedures.-

The control room emergency ventilation system consists of two indepen' dent filter r

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j and fan trains, two independent actuation channels per Unit and-the Control Room i isolation dampers.' The control room dampers isolate the control roam within 10

[ seconds of receipt of a high radiation signal. If he actuation signal can not-l close the control room isolation' dampers, isolatitg the control roan by manually closing the affected control room dampers provides the required isolation design ;

j function of the Control Room Emergency Ventilation System.

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j~ If the actuation signal can not start the emergency ventilation recirculation fan, sperating the affected fan in the manual recirculation mode and isolating.

the control room isolation dampers provides the. required design function of the

, control room emergency ventilation system to isolate the combined control rooms i to ensure that the control rooms will remain habitable. for operations personnel l during and following accident conditions. If the control room isolation' dampers l' are inoperable, implementing pre-planned isolation contingencies, such as closing i and sealing the fire damper in the associated isolation damper ventilation duct

or otherwise completely blocking flow through the ductwork, provides the required 1 design function'of the control ~ room isolation damper to isolate the control room.

! 1 l Accomplishing the compensatory measures fully satisfies the functional aspects of

! control room'energency ventilation system, therefore, no time limits for-I operation in this mode are applicable and reactor operation'may continue..

I .The control room emergency air conditioning system (CREACS) provides temperature ,

control-for the control room following isolation of'the control room. 'It is i l manually started from Unit Two Control Room or locally'if powered from Unit One.

l; The CREACS consists of two independent and redundant trains that provide cooling

of recirculated control room air. A cooling coil and a water cooled condensing unit are provided for each system to provide suitable temperatura"Osnditions in .

.the control room for operating personnel and safety reletea control' equipment. l I

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! Amendment No. M,M 61

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Bases (continued)

Ductwork, valves or dampers, and instrumentation _also foon part of the system.

During emergency operation, the CREACS naintains_the control room temperature.

With both trains of the control room emergency ventilation and/or emergency air conditioning inoperable, the function of the control room emergency air systems have been lost, requiring immediate action'to place.the reactor in a condition where the specification does not apply. With two trains of the control room emergency ventilation system inoperable, the appropriate contingency actions discussed above may be instituted to allow continued operation. These contingency actions should be put in place immediately (within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ) to fully satisfy the design functions of the control room emergency ventilation system.

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1 Amendment No. 62 (next page is. 66) l

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4.10 -CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING SYSTEM l

{ ~ SURVEILLANCE ~

Applicability.

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~ Applies to the' surveillance of the control room emergency ventilation and air i conditioning systems.'

obiective'

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- To verify an acceptable level of efficiency.and' operability of the control roas_ 3

[ emergency ventilation and air conditioning systems. .

_l l- Specification i

! 4.10.1 Each train of control room emergency air conditioning shall be

!- demonstrated operable:-

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a. At least once per 31 days.on a STAGGERED TEST RASIS by

! - 1. Starting each unit and.

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j 2. Verifying that each unit operates for at least;1. hour i and maintains the control room air temperature 584'F D.B.

I j b. At least once per 18 months by verifying a system flow rate

!~ of 9900 ' cfm 110%.

f- 4.10.2 Each Control Room Emergency Ventilation System shall'be demonstrated j operable:

a. At least once per 31 days on a Staggered Test Basis by initiating, from the control Room, flow through the HEPA filters and charcoal i adsorbers and verifying that the system operates for at least 15'

! minutes.

b. At least once per 18 months or 1)after any structural maintenance on the HEPA filter or charcoal adsorber housings,' or 2) following significant painting, fire, or chemical release in any ventilation

zone communicating with the system by

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! 1. Verifying that the cleanup system satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory l Positions C.S.a, C.5.c, and C.5.d of Regulatory Guide 1.52, i Revision 2, March 1978, and the system flow rate is 2000 cfm i10%.

3 2. Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, j March 1978, meets the laboratory testing' criteria of Regulatory

! Position C.6.a of Regulatory Guide 1.52, Revision 2, Nkrch 1978.

I 3. Verifying a system flow rate of 2000 cfm 110% during system j operation when tested in accordance with ANSI N510-1975.

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c. After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying

. within 31 days after removal that a laboratory analysis of a 1 representative carbon sample obtained in"accordance with Regulatory Position C.6.b of Regulatory Guide 1.52,-Revision 2, March 1978, i- meets the laboratory testing criteria of Regulatory Position.C.6.a j of Regulator,- Guide 1.52, Revision 2, March 1978.

) ' Amendment No. M ,M ,M 107 4

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d. At'least once per 18 months by:

1. Verifying'that the pressure drop across the. combined HEPA filters and charcoal adsorber banks is <6 inches of water while operating at a flowrate of 2000 cfm i10%.

2.eVerifying that on a control Room high radiation test signal, the system automatically isolates the. control Room within 10 seconds and switches into a recirculation mode of. operation with flow through the HEPA filters and charcoal adsorber. banks.

a. After each complete or partial replacement of the HEPA filter bank by verifying that the HEPA filter banks remove 199% of the DOP when they are tested-in-place in accordance.with ANSI N510-1975 while operating the system at a flow rate of 2000 cfm ilot.

f. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove 199.95% of'a halogenated hydrocarbon refrigerant test gas when they are tested L

in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 2000 cfm i10%.

Bases The purpose.of the control room emergency ventilation system is to limit the. l particulate and gaseous fission products to which the control area would be subjected during an accidental radioactive. release in or near the' Auxiliary ~ .

Building. The system is designed with 100 percent capacity filter trains which

! consist of a prefilter, high efficiency particulate filters,' charcoal adsorbers j and a' fan.

Since the emergency ventilation system is not normally operated, a periodic test l

1s required to insure operability when needed. During this test the system will be inspected for such things as water, oil, or other foreign materials gasket deterioration, adhesive deterioration in the HEFA' units; and unusual or excessive

~

noise or vibration when the fan motor is running.- Pressure drop across the combined HERA filters and charcoal adsorbers of less than 6 inches of water at the system design flow rate will indicate that the filters and adsorbers are not l clogged by excessive amounts of foreign matter. Pressure drop should be l determined at least once per operating cycle to show system performance l capability.

If significant painting, fire or chemical release occurs-such that the HEPA l filter or charcoal adsorber could become contaminated from the. fumes, L chemicals or foreign material, the same tests and sample analysis shall be performed as required for operational use. The determination of significant shall be made by the operator on duty at the time of the incident. Knowledgeable staff members should be consulted prior to making <

this determination.

The frequency of tests and sample' analysis are necessary to show that the HEPA filters and charcoal adsorbers can perform as evaluated. The charcoal

. adsorber efficiency test procedures should allow for obtaining at least two samples. Each sample should be at least two inches in diameter and a length equal to the thickness of the bed. Tests of the charcoal adsorbers with DOP aerosol shall be performed in accordance with ANSI N510 (1975) l " Standard for Testing of Nuclear Air Cleaning Systems." Any HEPA filters found defective shall be replaced with filters qualified according to Regulatory Position C.3.d of Regulatory Guide 1.52. If laboratory test l Amendment No. 108 ev- e ' - -

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Bases (continued) l 1

results are unacceptable, all charcoal adsorbents in the system shall be-replaced with charcoal adsorbent qualified according to Regulatory Guide 1.52.

] l

. l The operability of.the control room emergency air conditioning Systems ensure j that the ambient air temperature does not exceed the allowable temperature for 'l the equipment'and instrumentation' cooled by this-system and the Control Room will l l remain habitable for operations personnel during and following all credible j

j. accident conditions.

Operation of the systems for 15 minutes every month will demonstrate operability of the emergency ventilation and emergency air conditioning systems. All 2 dampers and other mechanical and isolation systems will be shown to be. operable. !

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) Amendment No. 108a l' 4

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INDEX 1 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE l REQUIREMENTS j 1

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SECTION PAGE l

. 3/4.7 PLANT SYSTEMS

.3/4.7.1 TURBINE CYCLE Safety Va1ves........................................... 3/4 7-1 ;

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Emergency Feedwater System.............................. 3/4 7-5' '

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Condensate Storage Tank................................. 3/4 7-7 l l

Activity................................................ 3/4 7-8 ;

Main Steam Isolation va1ves............................. 3/4 7-10 J a

3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.......... 3/4 7-14 )

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3/4.7.3 SERVICE WATER SYSTEM.................................... 3/4 7-15 i l

3/4.7.4 EMERGENCY COOLING POND.................................. 3/4 7-16 '

3/4.7.5 FLOOD PROTECTION........................................ 3/4 7-16a i

3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING SYSTEM.................................................. .3/4 7-17 3/4.7.8 SHOCK SUPPRESSORS (SNUBBERS)............................ 3/4 7-22 1

3/4.7.9 SEALED SOURCE CONTAMINATION............................. 3/4 7-27 3/4.7.10 FIRE SUPPRESION SYSTEMS ,

l Fire Suppression Water System........................... 3/4'7-29 i

, Spray and/or Sprinkler Systems.......................... 3/4 7-33 Fire Hose Stations...................................... 3/4 7-35 l 1

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3/4.7.11 FIRE BARRIERS........................................... 3/4 7-37 ;

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, 3/4.7.12 SPENT FUEL POOL STRUCTURAL INTEGRITY. . . . . . . . . . . . . . . . . . . . 3/4 7-38 1 3/4.8 ELECTRICAL POWER SYSTEMS I i

j 3/4.8.1 A.C. SOURCES l Operating............................................... 3/4 8-1 I Shutdown............................................... 3/4 8-5 1

ARKANSAS - UNIT 2 VIII Amendment No. 40,60,42,G9

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INDEX- :

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.SECTION PAGE' i

3/4.7 PLANT SYSTEMS

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3/4.7.1 . TURBINE CYCLE........................................... B 3/4 7-1 i i

3/4.7.2 STEAM GENERATOR' PRESSURE / TEMPERATURE LIMITATION......... B 3/4 7-4 -l 1 t

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i j 3/4.7.3 SERVICE MATER SYSTEM.................................... B 3/4 7-4 !

! . i B 3/4 7-4

. 3/4.7.4 DEERGENCY COOLING POND . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . i

i 3/4.7.5 FLOOD PROTECTION........................................ B 3/4 7-4 i i

3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING l :

SYSTEM..................................................- B 3/4-7-4 l

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i. , 3/4.7.8 SHOCK SUPPRESSORS (SNUBBERS)............................, B'3/4 7-5 1 3/4.7.9- . SEALED SOURCE. CONTAMINATION.................'............, B 3/4 7-6 .j i

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3/4.7.10 FIRE SUPPRESSION SYSTEMS................................ B 3/4 7-6 .<

) 3/4.7.11 PENETRATION FIRE BARRIERS...........'.................... B 3/4 7-7 ,

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3/4.7.12 SPENT FUEL POOL STRUCTURAL INTEGRITY........'.....~....... B 3/4 7-7 'i

) 3/4.8 ELECTRICAL POWER SYSTEMS................................... B 3/4 8 l i

d 3/4.9 REFUELING OPERATIONS '!

i 3/4.9.1 B 3/4 9-1 I BORON CONCENTRATION......................................

I l 3/4.9.2 INSTRUMENTATION..'......................................

. B 3/4 9-1 -

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3/4.9.3 DECAY TIME...............................'................ B 3/4 9-1 {

3/4.9.4 CONTAINMENT PENETRATIONS................................ B'3/4 9-1 .

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ARKANSAS - UNIT 2 XIII Amendment No. 40,63 j

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l TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION--

MINIMUM CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION

1. AREA MONITORS

a. Spent Fuel Pool Area Monitor 1 Note 1 s 1.5x10-2 R/hr 10 101 R/hr 13

b. Containment High Range 2 1, 2, 3 & 4 Not Applicable 1 - 107 R/hr 18

2. PROCESS MONITORS

a. Containment

i. Gaseous Activity a) Purge & Exhaust Isolation 1 5& 6 s 2 x background 10 - los epm 16. i b) RCS Leakage Detection 1 1, 2, 3 & 4 Not Applicable.. 10 - 108 y 14

11. Particulate Activity a) RCS Leakage Detection 1 1, 2, 3 & 4 Not Applicable 10 - 106 cpm' 14 i

b. Control Room Ventilation Radiation Monitoring 2 Note 2 s 2 x background 10 - 108 cpm 17,'20 l

c. Main Steam Line 1/ Steam 1, 2, 3, &4- Not Applicable 10 10 mR/hr 4

19 Radiation Monitors Line N:,te 1 - Nith fuel in the spent fuel pool or building Nate 2 - MODES 1, 2, 3, 4,'and 6 (with handling of irradiated fuel in progress in the containment building. l.

ARKANSAS - UNIT 2 3/4 3-25 Amendment No. 43,440,444

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TABLE NOTATION /

P l l ACTION 13 - With the number of channels OPERABLE.less than require'd by j the Minimum Channels OPERABLE. requirement, perform area'

~

l surveys of the monitored area with portable monitoring ;

instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .' l

} ACTION 14 -- With the number of channels OPERABLE less than required by.. l

[

the Minimum channels OPERABLE requirement, comply with the ;

j- ACTION-requirements of Specification 3.4.6.1.. j I ACTION 16 - With the number ofTOPERABLE channeli one less than the !

Miniansa Channels OPERABLE requirement, complete the L followings. l l

j a. If performing CORE ALTERATIONS or moving irradiated fuel j i within the reactor building, secure the containment purge l l"

system or suspend CORE ALTERATIONS and movement of ?

irradiated fuel within the reactor building. ;

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( b. If a containment PURGE is in progress, secure the j

containment purge system. j

{ -

j c. If continuously ventilating, verify the SEING monitor j l'j' operable or perform the ACTIONS of'3'3.3.9, or secure the containment purge system. l l l

ACTION 17 - With no channels OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and .

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i maintain operation of the control room emergency ventilation system in the recirculation mode of operation. I

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ACTION 18 -' With the number of channels OPERABLE one 1ess than required l by the Minimum Channels OPERABLE requirsoent,-(1) either l

{ restore theLinoperable channel'to OPERABLE siatus within 7 l days'or (2) prepare and submit a Special Report to-the l j( Cannission pursuant to spec)*iention 6.9.2 within 30 days ~

a j following the event, outlining the action taken, the cause j

of-the inoperability, and the plans'and schedule.for

restoring the system to OPERABLE status. With both'

channels inoperable, initiate alternate methods of .!

j- monitoring the containment radiation level within-72 hours l i in addition to the actions described above. j i .

i ACTION 19 - With the. number of OPERABLE Channels less than required by

4 the Minimum Channe?; OPERABLE requirements, initiate the 3

preplanned' alternate method'of monitoring the appropriate '

{- parameter (s), within 72. hours, and i

0 .1) either restore the inoperable Channel (s) to OPERABLE I

. status within 7 days of-the event, or [

J j 2) prepare and submit a Special Report to the Commission i

pursuant to specification 6.9.2 within 14 days following b the event outlining.the action taken, the'cause of the..

1 inoperability and the plans.and schedule for restoring '

j the system to OPERABLE status.

i ' ACTION 20'- With'the number of. channels OPERABLE one less than required.

j by the Minimum Channels OPERABLE requirement, restore the' j.' inoperable: channel to' operable status within 7 days,'or within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months initiate and maintain _the control room l

emergency ventilation system in the recirculation mode of-operation..

j ARKANSAS - UNIT 2 3/4 3-26 Amendment No. 63,4r44,44

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i PLANT SYSTEMS 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING SYSTEM LIMITING CONDITION FOR OPERATION l

3.7.6.1 Two independent control room amergency air conditioning and air j filtration systems shall be OPERABLE. l l

APPLICABILITY: MODES 1,2,3,4, and 6 (with handling of irradiated fuel in !

progress in the containment building). )

ACTION:

- a. With one control room emergency air conditioning system' inoperable, l restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

i

, b. With one control room emergency air filtration system inoperable, t restore the inoperable system to OPERABLE status within 7 days or be 5 in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS i 4.7.6.1.1 Each control room emergency air conditioning system shall be demonstrated OPERABLE: ,

i

a. At least once per 31 days on a STAGGERED TEST BASIS by:

1. Starting each unit fram the control room, and j

, 2. Verifying that each unit operates for at least I hour and i j maintains the control room air temperature s 84*F D.B. ;

i b. At least once per 18 months by verifying a system flow rate of i 9900 cfm i 10%. l i

i i 4.7.6.1.2 Each control room emergency air filtration system shall be j demonstrated OPERABLE:

a. At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters ,

! and charcoal adsorbers and verifying that the system operates for at least 15 minutes.

b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or I

. (2) following painting, fire or chemical release in any

, ventilation zone communicating with the system by:

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ARKANSAS - UNIT 2 3/4 7-17 Amendment No.

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,. 3/4.3 INSTRUMENTATION BASES

3/4.3.3 ' MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION

! . .The OPERABILITY of the radiation monitoring channels ensures'that 1)

the radiation levels are continually measured in the areas served by the ;

i individual channels and 2) the alarm or automatic action is initiated when' l l the radiation level; trip setpoint isJexceeded.

1 i The PURGE as defined in the definitions section is a release under a l purge permit, whereas continuous ventilation is defined as operation of the

! purge system after the requirements of the purge permit have been satisfied., j d

when securing the containment purge system to meet the ACTION requirements of t

this Specification, at least one supply valve and one exhaust valve is to be

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closed, and the supply and exhaust fans secured. ,

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{ Due to the unique situation of the shared control room habitability, one ANO-2 j l control room isolation channel receives a high radiation-signal from the ANO-1 . I

! control room area radiation monitor (RE-8001) and the redundant channel receives a high radiation signal from the ANO-2 control roca ventilation process monitor (2RITS-8750-1) .

}

3/4.3.3.2 INCORE DETECTORS l The OPERABILITY of the incore detectors with the specified minimum complement.of equipment ensures that the measurements obtained from use.of j this system accurately represent the spatial neutron-flux distribution of

! the reactor core.

l 1

} 3/4.3.3.3 SEISMIC INSTRUMENTATION i

i The OPERABILITY of the seismic instrumentation ensures that

, sufficient capability is available to promptly determine the magnitude of j a seismic event and evaluate the response of those features important to

, safety. This capability is required to permit comparison of the measured

response to that used in the design basis for the facility to determine if

!. plant shutdown is required pursuant to Appendix "A" of 10 CFR Part 100.

l The instrumentation is consistent with the recammendations of Safety Guide i j 12, " Instrumentation for Earthquakes," March,.1971. i j 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION f The OPERABILITY of the meteorological instrumentation ensures that

! sufficient meteorological data is available for estimating potential 4

radiation doses to the public as a result of' routine or accidental release !

of radioactive materials to the atmosphere. This capability is required

! to evaluate the need for initiating protective measures to protect the ,

l health and safety of the public and is consistent with the recommendations l of Regulatory Guide 1.23 "Onsite Meteorological Programs," Feburary 1977. I I 3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION 1- l The OPERABILITY of the remote shutdown instrumentation ensures that i sufficient capability is available to permit shutdown and maintenance of f HOT STANDBY of the facility from locations outside of the contr I room.

This capability is required in the: event control room habitability is lost j and is consistent with General Design Criteria 19 of 10 CFR 50.

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i ARKANSAS - UNIT 2 B 3/4 3-2 Amendment No. M,MG,MG 4

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PLANT SYSTEMS BASES 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION The limitation on steam generator pressure and. temperature ensures l that the pressure-induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits. The limitations to 90*F and 275 psig are based on a steam generator RTNDT of 30'F and are sufficient to prevent brittle fracture.

3/4.7.3 SERVICE MATER SYSTEM d

The OPERABILITY of the service water system ensures.that sufficient cooling capacity is available for continued operation of equipment during normal and accident conditions. The redundant cooling capacity of this

system, assuming a single failure, is consistent with the assumptions used

in the accident analyses.

1 3/4.7.4 EMERGENCY COOLING POND The limitations on the emergency cooling pond level and temperature are based on worst case initial conditions which could be present considering a simultaneous normal shutdown of Unit 1 and emergency shutdown of Unit 2 following a LOCA in Unit 2, using the ECP as a heat sink. The indicated ECP level is based on sounding to ensure a minimum contained water volume of 70 acre-feet. These' soundings ensure degradation is within acceptable limits such that the indicated level is consistent with the required volume and the

pond meets its design basis. The measured ECP temperature at the discharge from the pond is considered a conservative average of total pond conditions since solar gain, wind speed, and thermal current effects throughout the pond a will essentially be at equilibrium conditions under initial stagnant conditions. j Visual inspections are performed to ensure any physical degradation is within cceeptable limits to enable the ECP to fulfill its safety function. An 4

engineering evaluation shall be performed by a qualified engineer of any i apparent changes in visual appearance or other abnormal degradation to determine operability.

l The limitations on minimum water level and maximum temperature are j

based on providing a 30-day cooling water supply to safety-related equipment without exceeding their design basis temperature and is consistent with the recommendations of Regulatory Guide 1.27, "Ultinate Heat Sink for Nuclear Plants", March 1974.

3/4.7.5 FLOOD PROTECTION The 10mitation on flood protection ensures that facility protective actions will be taken in the event of flood conditions. !

3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING SYSTEM l 4 The OPERABILITY of the control room amergency air conditioning / air filtration system ensures that 1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and 4

5 ARKANSAS - UNIT 2 B 3/4 7-4 Amendment No. M B

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MARKUP OF CURRENT ANO-1 TECHNICAL SPECIFICATIONS j (FORINFO ONLY) l y

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1 TABLE OF CONTENTS

-SECTION TITLE PAGE I

1.

DEFINITIONS 1 1.1 RATED POWER 1 1.2 REACTOR OPERATING CONDITION 1 i 1.3 OPERABLE 2 ]

4 :1.4 PROTECTION INSTRUMENTATION LOGIC 2 1.5 INSTRUMENTATION SURVEILLANCE 3 I 1.6 POWER DISTRIBUTION 4 1 l

1.7 REACTOR BUILDING 5 1.8 FIRE SUPPRESSION WATER SYSTEM 5 1.9 STAGGERED TEST BASIS -5 1.10 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS Sa (RETS) DEFINITIONS-1.11 CORE OPERATING LIMITS REPORT 6

2. SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 7 2.1 SAFETY LIMITS REACTOR CORE 7 2.2 SAFETY LIMITS, REACTOR SYSTEM PPESSURE 10 2.3 LIMITING SAFETY SYSTEM SETTINGS, PnCIECTIVE ,

- INSTRUMENTATION 11 l

3. LIMITING CONDITIONS FOR OPERATION 16 I 3.1 REACTOR COOLANT SYSTEM 16 16-3.1.1 Operational Components .

3.1.2 Pressurization, Heatup and Cooldown Limitations 18 1

, 3.1.3 Minimum Conditions for Criticality 21 {

3.1.4 Reactor Coolant System Activity 23 j

. 3.1.5 Chemistry 25

^

3.1.6 Leakage 27

, 3.1.7 Moderator Temperature Coefficient of Reactivity 30 3.1.8 Low Power Physics Testing Restrictions 31 1 3.1.9 Control Rod Operation 32 '

, 3.2 MAKEUP AND CHEMICAL ADDITION SYSTEMS 34 3.3 EMERGENCY CORE COOLING, REACTOR BUILDING COOLING, i AND REACTOR BUILDING SPRAY SYSTEMS 36 3.4 STEAM AND POWER CONVERSION SYSTEM 40 3.5 INSTRUMENTATION SYSTEMS 42 3.5.1 Operational Safety Instrumentation- 42 3.5.2 Control Rod Group and Power Distribution Limits 46 3.5.3 Safety Features Actuation System Setpoints 49 3.5.4 Incore Instrumentation 51 3.5.5 Fire Detection Instrumentation 53d 3.5.6 hadioactive Liquid Effluent Instrumentation 53f 3.5.7 Radioactive Gaseous Effluent Instrumentation 53I l 3.6 REACTOR BUILDING 54

3.7 AUXILIARY ELECTRICAL SYSTEMS 56

, 3.8 FUEL LOADING AND REFUELING 58 3.9 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING AND-EGGEAMW-SYSTEM 60 3.10 SECONDARY SYSTEM ACTIVITY 66 3.11 EMERCENCY COOLING POND 66a

.i 3.12 MISCELLANEOUS RADIOACTIVE MATERIALS SOURCES 66b i 3.13 PENETRATION ROOM VENTILATION SYSTEM 66c l

Amendment No. M ,SS,M 9 i

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' SECTION . TITLE 3.14 HYDROGEN RECOMBINERS 66e i 2 3.15- FUEL HANDLING AREA VENTILATION SYSTEM 66g i 3.16 SHOCK SUPPRESSORS : (SNUBBERS) 661-

)- - 3.17' FIRE SUPPRESSION WATER SYSTEM _ ~ 66m

? . 3.18- FIRE SUPPRESSION SPRINKLER SYSTEMS 66n 3.19- CONTROL ROOM AND AUXILIARY CONTROL ROOM-HALON 4 SYSTEMS 66o i 3.20 FIRE HOSE STATIONS' 66p .

L 3.21 FIRE BARRIERS .

66q:

3.22 REACTOR BUILDING. PURGE FILTRATION SYSTEM 66r i j 3.23 REACTOR BUILDING PURGE VALVES '. 6 6 t l 4

3.24 EXPLOSIVE GAS MIXTURE 66u:

. 3.25 RADIQACTIVE EFFLUENTS 166v

[ 3.25.1- Radioactive Liquid Effluents 66v-

3.25.1.1 Concentration 66v.

3.25.1.2 Dose 66w

}

1 3.25.1.3 Waste Treatament 66x 1 3.25.1.4 Liquid Holdup Tanks 66y 1 l 3.25.2 Radioactive Gaseous Effluents 662 3 3.25.2.1 Dose Rate 66z i i 3.25.2.2 Dose - Noble Gases 66aa l

! 3.25.2.3 ' Dose - Iodine-131, Tritium, and Radionuclides 1~

in Particulate Form 66bb '

] 3.25.2.4 Gaseous Radwaste Treatment 66cc j 3.25.2.5 Gas Storage Tanks =66dd- f

3.25.3 Total Dose .

66ee '

j -3.25.4 Solid Radioactive Waste .66ff i 4. SURVEILLANCE REQUIREMENTS. 67' ]

e 4.1 OPERATIONAL SAFETY ITEMS 67' <

{ 4.2 REACTOR COOLANT SYSTEM SURVEILLANCE '76~ -)

4.3 TESTING FOLLOWING OPENING OF. SYSTEM- 78 l 4.4 REACTOR BUILDING .

79' l 4.4.1 Reactor Building Leakage Tests 79 i 4.4.2 Structural Integrity 85 !

F 4.5. EMERGENCY CORE COOLING SYSTEM AND REACTOR l BUILDING COOLING SYSTEM PERIODIC TESTING 92 I

! 4.5.1 Emergency Core Cooling Systems 92 I ll 4.5.2 Reactor Building Cooling Systens 95 l

4.6 AUXILIARY ELECTRICAL SYSTEM TESTS 100

4.7 REACTOR CONTROL' ROD SYSTEM TESTS- 102- -l l 4.7.1 Control Rod Drive System Functional Tests .102 j- 4.7.2 Control Rod Program Verification -104

! 4.8 EMERGENCY FEEDWATER PUMP TESTING 105' 4.9 REACTIVITY ANOMALIES 166

l. 4.10 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING AND l M OEANON-SYSTCM SURVEILLANCE 107

4.11 PENETRATION ROOM VENTILATION SYSTEM SURVEILLANCE 109

4.12 HYDROGEN RECOMBINERS SURVEILLANCE 109b

' 4.13 EMERGENCY COOLING POND 110a 4.14. RADIOACTIVE MATERIALS SOURCES SURVEILLANCE 110b l j' 4.15 AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH j

ENERGY LINES OUTSIDE OF CONTAINMENT 110c !

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G h l Amendment No. 44,44,4G,44,44,M ,M , 11 !

44,44,SS,94,Ma,M 4 i V

. . . _ . . . . . - - . - - ~ -. ,,. -- - -

T 1,

4 F ^3.5.1.7 The Decay' Heat Removal System isolation valve closure setpoints-I shallibe equal to or less'than:340 psig.for one valve and equal ~ J to or;1ess than 400 psig1 for the second valve in the suction -

line. The relief valve setting for the DHR system shall be

[

equal to or less than-450 psig. l 3.5.1.8 The degraded voltage monitoring relay settings shall be as-followst'

]

l-a.- The:4.16 KV emergency bus undervoltage relay setpoints.

)- shall be >311b VAC but <3177.VAC.

1 j b. .The 460.V emergency bus undervoltage relay'setpoints'shall i

~be >423 VAC but <431 VAC with a. time delay setpoint;of 8 i i seconds il second.

i 3.5.1.9 The following Reactor Trip circuitry shal1~be operable as indicated: ,

1. Reactor trip 'upon loss . of Main . Feedwater shall' be ,

operable' (as' determined by Specification'4.1.a and; item i 35 of Table 4.1-1) at greater than'5%' reactor power.-

~

- (May'be bypassed upito 10% reactor. power.)

2.- Reactor trip upon Turbine Trip'shall be' operable:(as i i

l' -determined by Specification 4.1.a and' item 41 of Table i 4.1-1) at greater than 5% reactor power. '(May be ' t

bypassed up to 45% reactor power.)

l 3. If the requirements'of specifications 3..5 1.9.1 or.

t 3.5.1.9.2 cannot be meti? restore _the inoperable. trip

{ within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or bring the plant to a hot' shutdown j condition. .

! 3.5.1.10 Whe- h control room ventilation chlorine detection syateeg emeteumonte46em-shall be' operable.and: capable of aetuating j control room isolation and filt:: tic: ;y;t---the ameroency -

i' ventilation systems, with. alarm / trip 1 'setpoints adjusted to actuate at a' chlorine concentration of r 3

55 ppm whenever the reactor coolant system is above the cold' shutdown

! s.9Adi.t.i.en . l l

} 3.5.1.11 For on-line testing of the Emergency Feedwater t

Initiation and Control (EFIC) system channels-during power i operation only one channel shall be locked into " maintenance ,

l bypass" at any one time. 'If one channel of the NI/RPS is :in.

maintenance bypass, only the corresponding channel'of EFIC may be bypassed. . ,

l 3.5.1.12. The Containment High Range Radiation Monitoring instrumentation 7

shall be operable with a minimum measurement range from 1 to 10 1 R/hr. l 4' 'l i l e

. Amendment No. 40,M,M,M,94,M4 42a i

3-

. ~ _ ..-. _ . _ . _ . _ _ _ . ._ .. .. ._. . _ . . _

I y

1

~

-3.5.1.13=-The seismic Monitoring Instrumentation-shall be~ operable with'a l minimum measurement" range of 0.01 - 1.0 g for Triaxial-. Time:-

History Accelerographs, 0.05 - 1.0 g for Triaxial PeakL

Accelerographs, and 2-25.4 Hz for Triaxial Response Spectrum

~ Recorders.

-. The Nhin steam Line Radiation Monitoring Instrumentation shall

^ 3.5.1.14 j be4operable with'a' minimum measurement range from 10 7 to 1

'10 mR/hr, whenever the-reactor is above'the. cold shutdown.-

l ' condition.

} 3.5.1.15 Initiate functions of the EFIC system which are. bypassed at cold I

j shutdown conditions ; shall have the following minimum operability -

conditions:

I a. " low steam generator pressure" initiate shall be~ operable when -

~

j_ the main steam pressure exceeds 750 psig. ;

I .b. " loss of 4.RC~ pumps" initiate shall be operable when neutron.

l flux exceeds lot power.' -i j' . ~ l F c. " main-feedwater pumps tripped". initiate shall be operable when i i neutron. flux exceeds 10% power.- l 1

i 3.5.1.16 The . automatic steam generator isolation system within EFIC 'shall be I j operable when main steam pressure is greater than 750'psig. l 4 l l 3.5.1.17 Two indenandept control roan ventilation radiation monitorina systems shall be operable whenever the reactor coolant system is above the j cold shutdown condition or whenever the reactor coolant system is in -l 3 the refuelina shutdown condition with handlina of irradiated fuel in

! croareas in the reactor buildina.

)

a f;

i 1

i i

4 i

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+

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Amendment No. 4M,MG,444,W .

42b

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

?

t i

.]

The'OFERABILITY of the. Seismic Monitoring Instrumentation ensures.that -)

sufficient' capability is available to promptly' determine the magnitude of a l seismic event and evaluate the response of those features important to safety. !

This capability is required to permit. comparison of the measured response to, l that used in the design basis for'the facility,to determine if plant shutdown is j required pursuant to Appendix "A" of 10CFR Part 100. The instrumentation is consistent with the recommendations of Safety Guide 12,. " Instrumentation for ' ,

- Earthquake," published March 19, 1971, and NUREG-0800 Section 3.7.4, " Seismic 1 Int.trumentation." l l

The eranainal function of thn control Room' Isolation-Hiah P.adiation is to Drovide I I

an enc:Losed envir----- t from which thm unit can be eneratad followins an ggLg activity. The hiah radiation isolation dunction> ,

nrovid== masurance that undar the reauired aanditions. an isolation saan=1 will be triven. Due to the uniaue situation of the shared con' crol room hah:.tability. ;

one A20-1 control room isolation eh=nn=1 receives a h:.oh radiation sian=1 from ;

' the ANO-1 control rea= area rad' ation monitor (RE-800:. and the radandant channel; .l receives a hiah radiation sianal from the ANO-2 contro:L room ver tilation crocess -]

i =aitor (2RJTS-0750-l'. With no ch=nn=1 of the contro?. room raciation monitorina- .j system operable. +he CREVS =nat be niaced in a condition that does not reauire J

+h= isol& tion to occur. To anaura that the ventilation-system has been olaced in I a state eauivalent to that which occurs after the hiah radiation isolation has occurred, one OPERABLE train of the CREVS is olaced in the emeraency recirculation =ada of onerat: on. Reactor operation can continue indefinitelv in this state. The 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months P Wation T4== is a sufficient == aunt of time in which to take the Reauired Action.

REFERENCE FSAR, Section 7.1.

FRAR,.Section 2.7.6 1

l i

Amendment No. 464 43c l

.__ . . . . - . . _ . . . . _ . __.,_ __.mm - . _ . . . . _ . . . . . _ _ . . - . . . . . _.. __ _. _.m .- .m, ._. _ . . , . . _ _

P Table 3.5.1-1 (cont'd)

OTHER SAFETY REIATED SYSTEMS (C:nt'd) 1 2- 3 4 5 No. of- Operator action channels Min. Min. if conditions of i No. of for sys- operable degree of column 3 or 4 Functional Unit channels tem trip channels redundancy cannot be met

c. Triaxial Response-Spectrum Recorders

1. 2XR-8350, Unit 2 Containment 1 N/A 1 0 Note 27 Base Slab, Elev. 335' 6

O/S Containment)

15. Reactor Vessel Level Monitoring System 2 N/A 2 0 Note 28, 29

16. Hot Leg Level Measurement System (HLINS) 2 N/A -2 0 Note 28, 29

17. Main Steam Line 1 / steam line N/A 1/ steam line: 0- Note 30 Radiation Monitors

& Control Room 1 1 1 g Note 17, 18 Radiation Monitor Amendment No. -141,-144 45d2

-n---....-. . . - - - . - . . . - . . . . ~ . - - - . - . ~ - - - . ~ - - - . _ _ _ . . - _ . - . - . . . - . .- -.

q- :

. i a- ..

4 4

TABLE 3.5.1-1 (Cont'd) 1-4

12. With the nusber of operable channels less than required, either return the indicator to operable

, status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or verify the block valve closed and power removed within an additional 24- ,

hours. If the block valve cannot be verified closed within the additional ~24 hours, de-energize the l electromatic relief valve power supply within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l

13. Channels may be bypassed for not greater than 30 seconds during: reactor. coolant pump starts. If>the automatic bypass circuit or its alarm circuit is inoperable, the undervoltage protection shall be restored within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , otherwise, Note 14 applies.

, 14. With the number of channels less than required,-restore the inoperable channels to operable sts.tus-within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in NOT SNUTDOWN within the next 6' hours and in COLD SNUTDOWN within the-following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

.L

15. This trip function may b~ bypassed at up to 10% reactor power.

j 16. This trip function may be bypassed at up to.45% reactor power.

17. With no channel operable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months :::t::: th: ind: di '- 21: t: :;;;di: 2t:t2 , ::

l initiate and maintain operation of the control room emergency ventilation system in the recirculation i mode of operation.

1 .

1 18. With one channel inoperable, restore the inoperable.. channel.to operable status.withinL7 days or-within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ' initiate and maintain operation of the control room emergency ventilation I

system in the recirculation mode of operation. =

t

.t This function may be bypassed below'750 psig OTSG pressure. ; Bypass-is' automatically removed when

~

19.

pressure exceeds 750 psig.

. 2 0. With one channel inoperable, -(l) either restore:the inoperable channel!to operable status within 7 days, g (2) prepare and suhM t a'Special Report to the Consnission pursuant to Specification 6.12.5- I within.30 days following the event,., outlining the action taken, the cause of the.inoperability,.and the plans and schedule for restoring the system to operable-status.- With both channels . inoperable,-

3 initiate alternate methods.of monitoring'the containment radiation level within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in 4

addition to the actions described above. ,

21. With one ' channel inoperable, . restore the inoperable channel to operable status within '30 days or be in -

~

hot shutdown within-72 hours unless. containment entry is required. "If. containment entry is t

., required,=the inoperable channel must_be restored by the next= refueling outage. If.both channels are inoperable, restore the inoperable channels within 30 days or be in HOT SNUTDOWN'within 12 hotars.

l i

j Amendmcut No. 44,44,49,M,94,-144,444 45f

_ . . , , . . . _ . . . . . . .. . . _ _ _ um.

.- - - . . . . . . -- -- . . - - . - - ~ . . - - - . . - --

[ .- .-

t 3.8.15 storage in the spent fuel pool shall be restricted to fuel 'asssablies'- l

. having initial enrichment less than or equal to 4.1 w/o U-235. The provisions of specification 3.0.3 are not applicable.

3.8.16 storage in Region 2 (as shown.on Figure 3.8.1) .of,the spent fuel pool _ 'l shall be further restricted by burnup and enrichment limits specified in Figure 3.8.2. In the event a checkerboard' storage. configuration is deemed necessary for a portion of Region 2, vacant spaces adjacent to the faces.of.any fuel assembly which does not meet the' Region.2 burnup-criteria (non-restricted) shall be physically blocked before any'such fuel assembly may,be placed in. Region 2. This'will prevent inadvertent. ,

fuel assembly insertion into two adjacent storage locations.' The j provisions of specification 3.0.3 are not applicable.

l 1

3.8.17 The boron concentration ~in the spent, fuel pool shall be maintained 1(at j all times) at greater than 1600 parts per million. l

~

)

3.8.18 Durina'the handlina of irradiated fuel'in the reactor buildina, the- l control room -- raenev air canditionina system and the control room- 'j

-- raenev ventilation system shall be onerable as'reauired by l Specification 3.9.1 'i Bases j

Detailed written procedures will be available for use b; refueling per'sonnel.

These procedures, the above' specifications, and the design of_the fuel handling )

equipment as described'in section 9.6 of the FSAR' incorporating built-in

interlocks and safety features, provide' assurance,that.no-incident could occur i during the refueling operations that would result in a hazard to public health j and safety. If no change is being made in core geometry, one flux monitor is. j sufficient. This permits maintenance on the instrumentation. ~ Continuous monitoring of radiation levels and neutron flux provides issnediate indication of an unsafe condition. ;

The requirement that at least one decay heat removal loop be in operation ensures that (1) sufficient cooling capacity is available'to remove decay heat i and maintain the water in the reactor pressure vessel at the refueling temperature (normally ' 140

F) , and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron ~ dilution incident and prevent boron stratification. (1)

The requirement to have two decay heat-removal loops operable when there is less than 23 feet of water above the core, ensures that a single failure of the cperating decay heat removal' loop will not result in a complete loss of decay heat removal capability.- With the reactor vessel head removed and 23 feet of water above the core,.a'large heat sink is available for core cooling, thus in l the event of a failure of the operating decay heat removal loop, adequate time is provided to' initiate emergency. procedures to cool the core.

The shutdown margin indicated-in specification 3.8.4 will keep the core suberiticali. even with all control rods withdrawn from the core. (8) Although the refueling boron concentration is~ sufficient.to maintain the core keff 5 0.99 l if all the control rods were removed from the core, only a ' few control: rods will-be removed at any one time during fuel shuffling and 1

Amendment No. M,M,M,M,Mh M4, 59a ;

44,M4 i

.- . ._ _ _ - _ ._ __ _ _ _ _ _ _ , n_ _ _

. 3.9 CONTROL ROOM EMERGENCY VENTIIATION AND AIR CONDITIONING ANG-HMMATMN l .SYSTEMg

. Applicability i

. Applies to the operability of the control room emergency ventilation and air l conditioning : d i::12 tic; systemg.

1 objective 7

t l To ensure that the control room emergency ventilation and air conditioning and

! 4**&* M**

systesg will perform within acceptable levels'of efficiency and reliability, i-1- Specification r.

3.9.1 Control Room Emeraency Air Conditionina System

! 3.9.1.1 Two indeoendent trains of the control room emeraenev air i conditionina system shall be operable whenever the reactor a

j coolant system is above the cold shutdown condition or whenever j the reactor coolant system is in the refuelina shutdown condition f with handlina of irradiated fuel in oroaress in the reactor i buildina.

! 3. 9.1.2 With ' one control- room ' -- raency air conditionina system -

i- inocerable, restore the inocerable system to Operable status within 30 days or be in at least Hot Shutdown within the next 6

! hours and in Cold shutdown within the followina 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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3.9.2 Control Room Emeraency Ventilation System l

3.9.2.1 Two indeoendent trains of the control room amaraency ventilation ~ i 1

system shall be operable whenever the reactor coolant system is I i above the cold shutdown condition or whenever the reactor coolant I u

L Amendment No. 44,4G 60 l 1

l i

\

1 3,vstem is in the refuelina shutdown condition with handlina of

j rradiated fuel in oroaress in the reactor buildina.

3.9.2.2 with one control room emeraency ventilation system inoperable, i restore the inocerable system to Operable status within 7 dc,p g be in at least Hot Shutdown within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in Cold Shutdown within the followina 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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~. - - .. . . . . - . - - - - - -..

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The control room amaraency ventilation and air conditionina system-is desianed to <

! isolate the combined control rooms to ensure that the control rooms will remain . ;

I a

habitable-for Operations personnel durina and followina all credible accident j conditions and to ensure that the ==hient air t--aerature does not exceed the j allowable t - erature for continuous duty l instrumentation cooled by this system. The desian confiauration of the system"is l- based on 14=itina the radiation exposure to norsonnel occunvina the control room

- to 5 REN or less whole body, or its eauivalent, in accordance with the ,

I reauir-- ats of General Desian Criteria 19 of Annandix A, 10CFR 50.

e i Unit 1 and Unit 2 control rooms are's sinale enviroa==nt for emeraency l ventilation and air conditionina concerns. - Since the control room emeraency 4

ventilation and air conditionina eauin= ant is shared between units, the olant

status of both units must be cansidered when determinina anolicability of the.

i specification.

O Due to the uniaue situation of the shared ==araency ventilation and air 4

, conditionina mania ==nt, the ca=nonents may be cross fed fram the onnosite unit ner credetermined continaency actions /orocedures. Durina =^das when the !

j. -- raency control room ventilation and emeraency air conditionina is not reauired j on Unit 2. Unit 1 may take credit for operability of these syst=== when ,

l' Amendment No. 44,44 61 ' ::t ;;;; i: 55; l

confiaured to achieve seoaration and indeoendence reaardless of normal cower i l and/or service water confiouration. This will be in accordance with pre-determined continaency actions / procedures.

The control room ameroency ventilation system consists of two independent filter and fan trains, two independent actuation channels per Unit and the Control Room isolation d==aers. The control room d==ners isolate the control room within 10 seconds of receipt of a hiah radiation sianal. If the actuation sianal can not close the control room isolation d==ners, isolatina the control room by manually closina the affected control room d==ners provides the reauired isolation desian function of the Control Room Emeraency Ventilation System.

j If the actuation sianal can not start the amaraency ventilation recirculation fan. oneratina the affected fan in the manual recirculation mode and isolatino the control roam isolation d==aers orovides the reauired desian function of the control room ameraency ventilation system to isolate the combined control rooms t to ensure that the control rooms will ra==in habitable for operations eersonnel durina and followina accident conditions. If the control room isolation d==aers are inocerable. 4=al===ntino ore-olanned isolation continaencies, such as closino t and sealina the fire d==ner in the associated isolation d==ner ventilation duct or otherwise completelv blockina flow throuah the ductwork, orovides the reauired desian function of the control' room isolation d==ner to isolate the control room.

l Accomplishina the compensatory measures fully satisfies the functional aspects of l Control Room Emeroency Ventilation System, therefore, no time limits for i ooeration in this mode are anolicable and reactor operation may continue.

The control room emeraency air conditionina system (CREACS) provides temperature l control for the control room followina isolation of the control room. It is manually started from Unit Two Control Room or locally if oowered from Unit One.

The CREACS consists of two independent and redundant trains that orovide coolina of recirculated control room air. A coolina coil and a water cooled condensina unit are orovided for each system to orovide suitable temperature conditions in the control room for coeratina personnel and safety Amendment No. 44,4G 61 ';;;t p;;: i: 55) l

Bases (continued) related control eauinment. Ductwork, valves or d==ners,'and instrumentation also 4 form cart of the system. Durina emeraency operation, the CREACS maintains the ;

control room temperature.

With both trains of the control room ameraenev ventilation and/or ameraency air l conditionina inocerable, the function of the control room emeraency air systems have been lost, reauirina immediate action to olace the reactor in a condition where the specification does not acolv. With two trains of the control room amaraency ventilation system inoperable, the amorocriate continaenev actions '

- discussed above may be instituted to allow continued operation. These continaency actions should be out in olace immediatelv (within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ) to fully satisfy the desian functions of the control room emeroency ventilation system.

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Amendment No. 62 (next oaae is 66) l

4.10 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONINC ?J'O ISOIWr!O" l SYSTEM SURVEILLANCE Applicability Applies to the surveillance of the control room emergency ventilation and air conditioning :nd i: 1stien systema.

Objective To verify an acceptable level of efficiency and operability of the control room emergency ventilation and air conditioning :nd 1:01stion-systema. l Specification 4.10.1 Each train of control room emeroency air conditionino shall be demonstrated Operable:

a. At least once per 31 days on a STAGGERED TEST BASIS by:

1. Startina each unit and

2. Verifyino that each unit operates for at least I hour and maintains the control room air temperature s04'r D.B.

i b. At least once per 18 months by verifyino a system flow rate of 9900 cfm i10%.

7.t interv:1: :t t: :::::d le : nth:, the pressure d::p :::::: th

iin d "EP? filter: :nd ch:::::1 d:::h:2 b:nk: ch:11 h:

d-- :t :t:d to b; 1::: than 5-inch:: Of x:ter et y ter d::ign fl:= 'i10SFr 4.10.2 Each Control Room Emercency Ventilation System shall be demonstrated Operable:

a. At least once per 31 days on a Staacered Test Basis by initiatina, from the Control Room, flow throuch the HEPA filters and charcoal adsorbers and verifvina that the system operates for at least 15 ndnutes.

b. At least once per 18 months or 1)after any structural maintenance on the HEPA filter or charcoal adsorber housinos, or 21 followino sionificant paintino, fire, or chemical release in any ventilation zone communicatina with the system by:

1. Verifyina that the cleanuo system satisfies the in-place testinu acceptance criteria and uses the test procedures of Reculatory Positions C.S.a. C.5.c, and C.S.d of Reculatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 2000 cfm i 10%.

1

2. Verifyina within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Reculatory Position C.6.b of Reculatory Guide 1.52, Revision 2, March 1978, meets the laboratory testino criteria of Reculatory Position C.6.a of Reculatory Guide 1.52, Revision 2, March 1978.

3. Verifyina a system flow rate of 2000 cfm i10% durino system operation when tested in accordance with ANSI N510-1975.

c. After everv 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifvina within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Reculatory Amendment No. 44,M,M 107

q l

t Position C.6.b of Reaulatory Guide 1.52. Revision 2, March 1978, meets the laboratory testina criteria of Reaulatorv Position C.6.a of Reaulatorv Guide 1.52. Revision 2, March 1978.

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j d'.~At least once ner 18 months gv js i ll. Verifvina that the cressure dron across the ca=hined MRsA

{ filters and charcoal adsorber banks is <6 inches of water

- while operatina at a flowrate of 2000'cfm *10%.

! 2. ' Verifvina that on a Control Reem hiah radiation test snanal, the' system auta==tically isolates the Cor.troh Ree= within LO secanr =

l

!- and switeh== into a recirculation mocaof oneration with flow ,

l throuah the EEPA filters and charcoal adsorber banks. ]

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e. After each c---lete or nartial recla_ -t'of the ursa filter bank l

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) by verifyina that'the ursa filter banka'r== ave 199% of the DOP when j j'

they are tested in-nlace in accordance with ANSI'N510-1975 while j oneratina the system at a flow rate of 2000 c6m *10%. !

f f. After each c- ==lete or' n'a rtial renla- -t of a charcoal adsorber ;

4 bank by verifvina that the charcoal adsorbers r== ave 199.95% of a i halec===ted hydrocarbon refriaerant test aas when thev are tested' I 1

j in-nlace in accordmace with ANSI M510-1975 while oneratina the- -l

! system at a flow rate of 2000 cfm f104. l

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Bases j 4

The purpose of the control room 46 hee 6ag emeraency ventilation _ system is to l l limit the particulate and gaseous' fission products.to which the control area l

. would be subjected during an accidental radioactive . release in'or near the :

f. Auxiliary Building. The system is designed with 100 percent capacityJfilter l

!' trains which consist' of a profilter, high efficiency particulate filters, - j i charcoal adsorbers and a fan.-

l

! Since the emeraency ventilation system ey den is not normally operated, a l j periodic test is required to insure operability when needed. - During this test l

the system will be inspected for such things as water, oil, or other foreign ,

i materials gasket deterioration, adhesive deterioration in the HERA units; and ;

$' unusual or excessive noise or vibration-when the fan motor is running. . Pressure i drop across the combined HEPA filters and charcoal adsorbers of less than 6 a inches of water at the system design' flow rate will indicate that the filters and j l

i adsorbers are not clogged by excessive amounts of foreign matter. Pressure drop i j should be determined at least once per operating cycle to show system performance j capability.

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I If significant painting, fire or chemical' release occurs'such that the HEPA !

filter or charcoal adsorber could become contaminated from the fumes, l l

i- chemicals or foreign material, the same tests and sample analysis shall be !

] performed as required for operational use. The determination of' {

i significant shall be made by the operator on duty at the time of the i

! incident. Knowledgeable staff members should be consulted priorLto making l I

! this determination.

.i . .

F - The frequency of tests and sample analysis are necessary to show that the . ,

j HEPA filters and charcoal adsorbers can perform as evaluated. The charcoal- -l adsorber efficiency test procedures-should allow for obtaining at least two !

samples.- Each sample should be at least two inches in diameter'and a l E length equal to the thickness of the bed. Tests'of.the charcoal adsorbers.

i with DOP aerosol shall be' performed-in accordance with ANSI N510 (1975)

} " Standard for Testing of Nuclear Air. Cleaning Systems." Any HEPA filtersy ll found defective shall befraplaced with. filters' qualified according to Regulatory. Position C.3.d of Regulatory Guide 1.52.

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If laboratory test results are unacceptable, all charcoal l adsorbents in the system shall be replaced with charcoal adsorbent qualified according to Regulatory Guide 1.52.

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6 l ' Bases'(Continued) 1

i. The operability of the Control Room Emeraency Air Conditionina Systems ensure i that the ambient air temperature does not exceed the allowable temperature for

the eauinment and instr ==ntation cooled by this system and the Control Room will i remain habitable for Operations personnel durina and followina all credible accident conditions.

Operation of the syst=== for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months every month will~ e'-anstrate operability l

I of the -- raency ventilation and'-- raency air conditionina syst-- . All d===rs and other anchanical and isolation systems will be shown to be operable, f

i-1 If sinnificant naintina, fire or eh -ical release occurs such that'-the HEPA y

filter or charcoal adsorber could become contaminated from the fumes, ch-i cals or fornian material, +ha --

testa ==d s=- le an=1vais shall be.

l.

? performed as reauired for operational use. The determination of y...the__oner.m* or on duty at the t4 == of-the.

[ incident. Knowledaeable staff members should be consulted crior to makina j' this determination.

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]c MARKUP OF CURRENT ANO-2 TECHNICAL SPECIFICATIONS I

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i (FORINFO ONLY)

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i INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE i 1

1 i

REQUIREMENTS i SECTION PAGE I 1

3/4.7 PIANT SYSTEMS )

i ~

1 3/4.7.1 TURBINE CYCLE Safety Va1ves........................................... 3/4 7-1 Emergency Feedwater System.............................. 3/4 7-5 J

Condensate Storage Tank................................. 3/4 7-7 l

Activity................................................ 3/4 7-8 l 1

Main Steam Isolation Va1ves............................. 3/4 7-10 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.......... 3/4 7-14 i

3/4.7.3 SERVICE WATER SYSTEM.................................... 3/4 7-15 l 3/4.7.4 EMERGENCY COOLING POND.................................. 3/4 7-16 i

3/4.7.5 FLOOD PROTECTION........................................ 3/4 7-16a j 3/4.7.6 CONTROL ROOM EMERGENCY VENTIIATION AND AIR CONDITIONING AND-AM

, -M44aA94GN-S YSTEM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . - 3/4 7-17 4

1 3/4.7.8 SHOCK SUPPRESSORS-(SNUBBERS)............................ 3/4 7-22 4

3/4.7.9 SEALED SOURCE CONTAMINATION............................. 3/4 7-27 3/4.7.10 FIRE SUPPRESION SYSTEMS Fire Suppression Water System........................... 3/4 7-29 Spray and/or Sprinkler Systems.......................... 3/4 7-33

) Fire Hose Stations...................................... 3/4 7-35 t-3/4.7.11 FIRE BARRIERS........................................... 3/4 7-37

. 3/4.7.12 SPENT FUEL POOL STRUCTURAL INTEGRITY.................... 3/4 7-38 3/4.8 ELECTRICAL POWER SYSTEMS i

3/4.8.1 A.C. SOURCES operating............................................... 3/4 8-1 Shutdown............................................... 3/4 8-5 A

ARXANSAS - UNIT 2 VIII Amendment No. M,M,W,M

I i

. I INDEX BASES ,

i SECTION PAGE 3/4.7 PLANT SYSTEMS '

l 3/4.7.1 TURBINE CYCLE........................................... B 3/4 7-1 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION......... B 3/4 7-4 l i

3/4.7.3 SERVICE WATER SYSTEM.................................... B 3/4 7-4 '

3/4.7.4 EMERGENCY COOLING POND.................................. B 3/4 7-4 ,

1 3/4.7.5 FLOOD PROTECTION........................................ B 3/4 7-4 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING /AER-FH 9Ah-T ! '"! S Y ST EM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 7-4 i 3/4.7.8 SHOCK SUPPRESSORS (SNUBBERS)............................ B 3/4 7-5 3/4.7.9 SEALED SOURCE CONTAMINATION............................. B 3/4 7-6' ;

3/4.7.10 FIRE SUPPRESSION SYSTEMS................................ .B 3/4 7-6 3/4.7.11 PENETRATION FIRE BARRIERS............................... B 3/4 7-7 i 3/4.7.12 SPENT FUEL POOL STRUCTURAL INTEGRITY.................... B 3/4 7-7 3/4.8 ELECTRICAL POWER SYSTEMS................................... B 3/4 8-1 1

3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION...................................... B 3/4 9-1 3/4.9.2 INSTRUMENTATION........................................._ B 3/4 9-1 3/4.9.3 DECAY TIME.............................................. B 3/4 9-1 3/4.9.4 CONTAINMENT PENETRATIONS................................ B 3/4 9-1 4

4 4

4 ARKANSAS - UNIT 2 XIII Amendment No. 60,63

TABLE 3.3-6 RADIATION MONITORING INSTRUMENTATION MINIMUM CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION

1. AREA MONITORS

a. Spent Fuel Pool Area Monitor 1 Note 1 s 1.5x10-2 R/hr 10-4~- 101 R/hr 13

b. Containment High Range 2 1, 2, 3 & 4 Not Applicable 1 - 107 R/hr 18

2. PROCESS MONITORS

a. Containment

1. Gaseous Activity a) Purge & Exhaust Isolation 1 5& 6 s 2 x background 10 - 10' cpm 16 b) RCS Leakage Detection 1 1, 2, 3 & 4 Not Applicable' 10 - 10 6 ep , 14

11. Particulate Activity al RCS Leakage Detection 1 1,-2, 3 & 4 Not Applicable 10 - 10' cpm . 14

b. Control Room Ventilation Radiation Int:t: '% :t Monitor g & Note 2AMr-M0058 s 2 ~x' background 10 - 108 cpm 17J l

c. Main Steam Line 1/ Steam 1, 2, 3, & 4 Not Applicable' 10 10' mR/hr 19 Radiation Monitors Line Nate 1 - With fuel in the spent fuel pool or building Note 2 - MODES 1, 2, 3, 4, and 6 (with handlina of irradiated fuel in oroaress in the containment buildina. l ARKANSAS - UNIT 2 3/4 3-25 Amendment No. 64,-140,445

. __ - _ . .. ._. . _ . ~ . _ . _ - . _ , - _ _ _ _ _ _ _ _ _

4 ,'

j 6 TABLE 3.3-6 (Cantinund)

TABLE NOTATION.

ACTION 13'- With the number of' channels OPERABLE less than required by 4 .the Minimum Channels OPERABLE requi rement, perf orm area _

surveys of the monitored area with portable monitoring i- instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 14 - With the number of channels OPERABLE less than required by l

the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.'

):

j~ ..

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ACTION 16 - With-the number of OPERABLE channels one less then-the i Minimum. Channels' OPERABLE requirement, complete the-following: )

l

' I

a. If performing CORE ALTERATIONS o'r moving irradiated fuel'- 7,

- within thel reactor building, secure thefcontainment purge '

- system.or suspend CORE ALTERATION 5 and movement of-

!. irradiated fuel within the reactor' building.. i

i. ,

. b. If a containment PURGE is in progress,fsecure the l s containment purge system.

I c. If continuously. ventilating, verify the SPING monitor }

t operable or perform.the ACTIONS of 3.3.3.9, or secure the i li containment purge system. l.

f ACTION 17 - With gg" - - - - ' ' channels OPERABL" ' - - "-- -- - '

j t'- P' '---- "'-- :1: 0" n?_"i" ;;;xi;----2, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months q

i. initiate and maintain operation _of the control room i

!. emergency ventilation system in the recirculation mode of ,

operation.' '

ACTION 18 - With the number of channels. OPERABLE one less-than required ,

j.

~

by the Minimum Channels OPERABLE requirement,- (1) either i restore the inoperable channel to OPERABLE status within 7 !

i days or (2) prepare and submit a special Report to the I i

l Commission pursuant to specification'6.9.2 within 30 days

! ~ following the event, outlining the action taken, the.cause ,

l of the inoperability, and the plans and schedule for. J l restoring the system to OPERABLE status. With both ~

-l l channels inoperable, initiate alternate methods of monitoring the containment radiation level within 72. hours in addition to the actions described above. i

. ACTION 19 - With the number of OPERABLE Channels less.than required by j the Minimum Channels OPERABLE requirements, initiate the

' preplanned alternate method of monitoring the appropriate parameter (s), within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , ands I 1) either restore the inoperable Channel (s) to OPERABLE status within 7 days of the event, or

{ 2) prepare and submit a Special Report to the Commission )

ja ~ pursuant to specification 6.9.2 within 14 days.following '

the event outlining the action taken, the cause of the j inoperability and the plans and schedule for' restoring

+- the system to OPERABLE status.

ACTION 20 - with the nn=her of channels OPERABLE one less than'reauired' i by the Minimum channels OPERABLE reauirement, restore the inanerable channel to operable status within 7 days. or within I the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months initiate and maintain the control room ARKANSAS - UNIT 2 3/4 3-26 Amendment No. 44,+44,145 1

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i ARKANSAS.- UNIT 2 3/4 3-26 Amendment No. . 43,440,145' I

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1 PLANT SYSTEMS ,

I 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING !

t AN9-MA-FHrT4WHeN-SYSTEM LIMITING CONDITION FOR OPERATION j

, 4

3.7.6.1 Two independent control room emergency air conditioning and air filtration systems shall be OPERABLE.

2 APPLICABILITY: MODES 1,2,3 and-4. and 6 (with handlina of irradiated fuel a in oroaress in the containment buildina.. ]

ACTION:

a. With one control room emeraency air conditionina system inoperable, restore the inoperable system to OPERABLE status within 30 days or be

in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SygIgggg

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within the followina 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , b with one control room emergency ventilation:1 ::nditi:ning :: cir a a filt::ti:n system inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANCBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN 1 within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . l f SURVEILLANCE REQUIREMENTS i

4.7.6.1.1 Each control room emergency air conditioning system shall be demonstrated OPERABLE:

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a. At least once per 31 days on a STAGGERED TEST BASIS by:

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1. Starting each unit from the control room, and 1 2. Verifying that each unit operates for at least I hour and

) maintains the control room air temperature s 84*F D.B.

b. At least once per 18 months by verifying a' system ficw rate of

9900 cfm i 10%.

4.7.6.1.2 Each control room emergency air filtration system shall be i

demonstrated OPERABLE:

a. At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes.

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b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any j ventilation zone communicating with the system by

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ARKANSAS - UNIT 2 3/4 7-17 Amendment No.

, 3/4.3 INSTRUMENTATION' l BASES 3/4.3.3 MONITORING INSTRUMENTATION i- 3/4.3.3.1- RADIATION MONITORING INSTRUMENTATION l .

j .The OPERABILITY of the radiation anonitoring channels ensures that 1)

. the radiation levels are continually measured in the areas _ served by the i individual channels and 2) the alarm or. automatic action is initiated when-

the radiation level' trip setpoint is' exceeded.

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i The PURGE as defined in the definitions section'is a release under a purge permit,twhereas continuous ventilation is defined as operation of the 3 ., purge system after the requiressents of the purge permit.have been satisfied.

! When securing the containment purge system to meet the ACTION requirements of.

i this specification,'at least one. supply. valve and one exhaust valve is to be closed, and the supply and exhaust; fans. secured.

l I Due to the un4sua situation of the shared control room habLtabnlity, one'ANO-2 -

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controh room isolation channel receives a hiah radiation stenaL froaa the ANO-1 l controi room area radiation -nitor (RE-0001) ==d the r.Aundant eh=nn=1 receives j a hiah radiation sienal from the ANO-2 control room ventilation crocess monitor l (2RITS-8750-1).

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! '3/4.3.3.2 INCORE DETECTORS The OPERABILITY of=the incore detectors with the specified minimum

, complement.of equipment ensures that the measurements obtained front use-of

! this system accurately represent the spatial neutron flux distribution'of:

} the reactor core.:

l 3/4.3.3.3 SEISMIC INSTRUMENTATION

} The OPERABILITY of the seismic instrumentation ensures that j sufficient capability is available to promptly determine'the magnitude of

a seismic event and evaluate the response.of those features'important to

!- safety. This capability is required to permit comparison of the. measured

response to that: used.in the design basis.for the facility to determine if j plant shutdown is required pursuant to Appendix "A" of.10 CFR Part,100.

l The instrumentation is consistent with the recommendations of Safety Guide-l 12, " Instrumentation for Earthquakes," March, 1971.

4 i 3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION-

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! The OPERABILITY of the metsorological instrumentation ensures that-j sufficient meteorological data is available for estimating potential

radiation doses to the public as a result of routine or accidental release )

j. of radioactive materials to the atmosphere.- This capability is required !

to evaluate the need for initiating protective measures to protect the

[ health and safety of the' public and is consistent with the recosamendations

of Regulatory Guide 1.23 "Onsite Meteorological: Programs," Feburary 1972.

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l '3/4.3.3.5 REMOTE SHUTDONN INSTRUMENTATION i . .

j :. The OPERABILITY of the remote shutdown instrumentation ensures that

. sufficient capability is available to permit shutdown and maintenance of 3 HOT STANDBY of the facility from locations outside of the control room. ..

!' -This capability is required in the event control room habitability is lost-

j. and is consistent with General Design Criteria 19 of 10 CFR 50.

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f( ARKANSAS - UNIT 2 8 3/4 3-2 . Amendment No. M,MG,He i.

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j. ' PLANT SYSTEMS t EASES :

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i l- 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION.

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Thel limitation on steam generator pressure and temperature ensures i that.the pressure-induced stresses in the' steam generators do not exceed ~ l

! the maxi == allowable fracture' toughness stress ' limits. The limitations

to 90*F and.275 psig are based on a steam generator RTNDT of 30*F and are sufficient to prevent brittle fracture. l l

. 3/4.7.3 SERVICE WATER SYSTEM l

j' The OPERABILITY of the service water system ensures that sufficient' 1- .

cooling capacity is available for continued operation ofLequipment during

normal and accident conditions. The redundant cooling capacity of this j system, assuming a single-failure, is consistent with: the assumptions used t in the accident analyses.

t 3/4.7.4 MERGENCY COOLING POND 1 .

The limitations on the emergency cooling pond. level' and temperature are -

I based on worst' case initial conditions.which could be present considering j a simultaneous normal shutdown of Unit 1 and. emergency shutdown of Unit 2--

following a LOCA in Unit 2,.using the ECP as a heat sink. The. indicated ECP' l

4 level is based on sounding to ensure a minimum contained water. volume of 70-

! acre-feet. These soundings ensure degradation is within acceptable-limits =

l such that the indicated level is consistent with the required volume and the l~ pond meets its design basis. The measured ECP temperature at the discharge x j from the pond is considered a conservative average of total pond; conditions j since solar gain, wind speed, and thermal current effects throughout the pond

will essentially be at equilibrium conditions under initial stagnant conditions.

Visual inspections are performed to ensure any physical. degradation is within 1- acceptable limits to enable the ECF to fulfill its safety function. An

engineering evaluation shall be performed by a qualified engineer of any ;

j apparent changes in visual appearance or other abnormal degradation to

determine operability, j I

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The limitations on minimum water level and maximum temperature are ]

l based on providing a 30-day cooling water supply to safety-related !

j equipment without exceeding their design basis temperature and is 3

consistent with the recomunendations of Regulatory Guide 1.27, " Ultimate j Heat Sink for Nuclear Plants", March 1974.

3/4.7.5 FLOOD PROTECTION l The limitation on flood protection ensures that facility protective actions will be taken in the event of flood conditions.'

l 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING _/'JP ?!LT"".T!^" l j SYSTDt i

! The OPERABILITY of the control room emergency air conditioning / air

, filtration system ensures that 1) the ambient air temperature does not exceed the allowable temperature for-continuous duty rating for.the

equipment and instrumentation cooled by this system and 2) the control.

j room will remain habitable for operations personnel during and

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I ARKANSAS - UNIT 2 B 3/4 7-4 Amendment No. M4

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ML20082C587

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