ML20132G638
| ML20132G638 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/19/1996 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20132G637 | List: |
| References | |
| NUDOCS 9612260323 | |
| Download: ML20132G638 (62) | |
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TABLE OF CONTENTS SECTION TITLE PAGE 1.
DEFINITIONS 1
1.1 RATED POWER 1
1.2 REACTOR OPERATING CONDITION 1
i 1.3 OPERABLE 2
1.4 PROTECTION INSTRUMENTATION LOGIC 2
i 1.5 INSTRUMENTATION SURVEILLANCE 3
1.6 POWER DISTRIBUTION 4
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 i
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 PRESSURE 10 l
2.3 LIMITING SAFETY SYSTEM SETTINGS, PROTECTIVE F
INSTRUMENTATION 11 3.
LIMITING CONDITIONS FOR OPERATION 16 3.1 REACTOR COOLANT SYSTEM 16 6
3.1.1 Operational Components 16 3.1.2 Pressurization, Heatup and Cooldown Limitations 18 3.1.3 Minimum conditions for Criticality 21 i
3.1.4 Reactor Coolant System Activity 23 1
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
[
3.1.9 Control Rod Operation 32 3.2 MAKEUP AND CHEMICAL ADDITION SYSTEMS 34 3.3 EMERGENCY CORE COOLING, REACTOR BUILDING COOLING, j
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 Radioactive Liquid Effluent Instrumentation 53f 3.5.7 Radioactive Gaseous Effluent Instrumentation 53I 3.6 REACTOR BUILDING 54 3
3.7 AUXILIARY ELECTRICAL SYSTEMS 56 3.8 FURL LOADING AND REFUELING 58 3.9 CONYROL ROOM EMERGENCY VENTILATION AND I
A;R CONDITIONING SYSTEM 60 4
3.10 S ECONDARY SYSTEM ACTIVITY 66 3.11 EMERGENCY COOLING POND 66a 3.12 MISCELLANEOUS RADIOACTIVE MATERIALS SOURCES 66b 1
3.13 PENETRATION ROOM VENTILATION SYSTEM 66c l
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l Amendment No. M,M,M9 i
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SECTION TITLE PAGE l
3.14 HYDROGEN RECOMBINERS 66e l
3.15 FUEL HANDLING AREA VENTILATION SYSTEM 66g i
3.16 SHOCK SUPPRESSORS (SNUBBERS) 661
(
l 3.17 FIRE SUPPRESSION' WATER SYSTEM 66m l
l 3.18 FIRE SUPPRESSION SPRINKLER SYSTEMS 66n 3.19 CONTROL ROOM AND AUXILIARY CONTROL ROOM HALON SYSTEMS 66o i
3.20 FIRE HOSE STATIONS 66p
[
3.21 FIRE BARRIERS 66q 3.22 REACTOR BUILDING PURGE FILTRATION SYSTEM 66r i
3.23 REACTOR BUILDING PURGE VALVES 66t i
3.24 EKPLOSIVE GAS MIXTURE 66u l
3.25 RADIQACTIVE EFFLUENTS 66v i
- 3.25.1 Radioactive Liquid Effluents 66v j
3.25.1.1 Concentration 66v i
3.25.1.2 Dose 66w
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3.25.1.3 Waste Treatment 66x 3.25.1.4 Liquid Holdup Tanks.
66y 3.25.2 Radioactive Gaseous Effluents 66z l
3.25.2.1 Dose Rate 66z l
3.25.2.2 Dose - Noble Gases 66aa f
3.25.2.3 Dose - Iodine-131, Tritium, and Radionuclides l
in Particulate Form 66bb l
3.25.2.4 Gaseous Radwaste Treatment 66cc 3.25.2.5 Gas Storage Tanks 66dd 3.25.3 Total Dose 66ee 3.25.4 Solid Radioactive Waste 66ff'
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4.
SURVEILLANCE REQUIREMENTS 67 j
4.1 OPERATIONAL SAFETY ITEMS 67 4.2 REACTOR COOLANT SYSTEM SURVEILLANCE 76 i
4.3 TESTING FOLLOWING OPENING OF SYSTEM 78 l
4.4 REACTOR BUILDING 79 4.4.1' Reactor Building Leakage Tests 79 4.4.2 Structural Integrity 85-4.5 EMERGENCY CORE COOLING SYSTEM AND REACTOR f
l BUILDING COOLING SYSTEM PERIODIC TESTING 92 4.5.1 Emergency Core Cooling Systems 92 l
l 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 j
4.7.1 Control Rod Drive System Functional Tests 102 j
4.7.2 control Rod Program Verification.
104 4.8 DMERGENCY FEEDWATER PUMP TESTING 105 4.9 REACTIVITY ANOMALIES 106 t
4.10 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING SYSTSM SURVEILLNNCE 107 4.11 PENETRATION ROOM VENTILATION SYSTEM SURVEILLANCE 109 4.12 HYDROGEN RECOMBINERS SURVEILLANCE 109b 4.13 EMERGENCY COOLING POND 110a i
4.14 RADIOACTIVE MATERIALS SOURCES SURVEILLANCE 110b 4.15 AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH ENERGY LINES OUTSIDE OF CONTAINMENT 110c l
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Amendment No. G4,G4,64,44,44,63,66, ii 66,&4,48,G3,4GG,1G7 l
.i
3.5.1.7 The Decay Heat Removal System isolation valve closure cetpoints 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 450 psig.
3.5.1.8 The degraded voltage monitoring relay settings shall be as follows:
a.
The 4.16 KV emergency bus undervoltage relay setpoints shall be >311b VAC but (2177 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 determined by Specification 4.1.a and item 35 of Table 4.1-1) at greater than 5% reactor power.
(May be bypassed up to 10% reactor power.)
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 5v reactor power.
(May be oypassed up to 45% reactor power.)
3.
If the requirements of Specifications 3.5.1.9.1 or 3.5.1.9.2 cannot be met, restore the inoperable trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or bring the plant to a hot shutdown condition.
3.5.1.10 Two control room ventilation chlorine detection systems shall be operable and capable of actuating control room isolation and emergency ventilation systems, with alarm / trip setpoints adjusted to actuate at a chlorine concentration of 55 ppm whenever the reactor coolant system is above the cold shutdown condition.
3.5.1.11 For on-line testing of the Emergency Feedwater Initiation and Control (EFIC) system channels during power 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, shall be operable with a minimum measurement range from 1 to 10 R/hr.
l Amendment No. M, M, M, M,44, M4 42a
i 3.5.1.13 The seismic Monitoring Instrumentation shall be operable with a minimum 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.
3.5.1.14 The Main Steam Line Radiation Monitoring Instrumentation shall be operable with a minimum measurement range from 10-1 to 104 mR/hr, whenever the reactor is above the cold shutdown condition.
3.5.1.15 Initiate functions of the EFIC system which are bypassed at cold shutdown conditions shall have the following minimum operability conditions:
a.
" low steam generator pressure" initiate shall be operable when the main steam pressure exceeds 750 psig,
- b. " loss of 4 RC pumps" initiate shall be operable when neutron flux exceeds 10% power.
c.
" main feedwater pumps tripped" initiate shall be operable when neutron flux exceeds 10% power.
3.5.1.16 The automatic steam generator isolation system within EFIC shall be operable when main steam pressure is greater than 750 psig.
3.5.1.17 Two control room ventilation radiation monitoring channels shall be operable whenever the reactor coolant system is above the cold shutdown condition or during handling of irradiated fuel.
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Amendment No. 4-36,MO,M3,4M 42b
-. ~.-
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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 consistent with the recommendations of Safety Guide 12, " Instrumentation for Earthquake," published March 19, 1971, and NUREG-0800 Section 3.7.4,
" Seismic Instrumentation."
To support loss of main feedwater analyses, steam line/feedwater line break 7
analyses, SBLOCA analyses, and NUREG-0737 requirements, the EFIC system is designed to automatically initiate EFW when:
1.
all four RC pumps are tripped i
2.
both main feedwater pumps are tripped 3.
the level of either steam generator is low 4.
either steam generator pressure is low 5.
ESAS ECCS actuation (high RB pressure or low RCS pressure)
The EFIC system is also designed to isolate the affected steam generator on a steam line/feedwater line break and supply EFW to the intact generator according j
to the following logic:
If both SG's are above 600 psig, supply EFW to both SG's.
If one SG is below 600 psig, supply EFW to the other SG.
If both SG's are below 600 psig, but the pressure difference 1
between the two SG's exceeds 100 psig, supply EFW only to the SG I
with the higher pressure.
l i
If both SG's are below 600 psig and the pressure difference is less than 100 psig, supply EFW to both SG's.
At cold shutdown conditions all EFIC initiate and isolate functions are bypassed except low steam generator level initiate. The bypassed functions I
will be automatically reset at the values or plant conditions identified in Specification 3.5.1.15.
" Loss of 4 RC pumps" initiate and " low steam generator pressure" initiate are the only shutdown bypasses to be manually initiated during cooldown.
If reset is not done manually, they will automatically reset. Main feedwater pump trip bypass is automatically removed above 10% power.
The principal function of the Control Room Isolation-High Radiation is to provide an enclosed environment from which the unit can be operated following an uncontrolled release of radioactivity.
Due to the unique arrangement of the shared control room envelope, one control room isolation channel receives a i
high radiation signal from the ANO-1 control room area radiation monitor and the redundant channel receives a high radiation signal from the ANO-2 control room l
ventilation process monitor. With no channel of the control room radiation monitoring system operable, the CREVS must be placed in a condition that does not require the isolation to occur (i.e.,
one operable train of CREVS is placed in the emergency recirculation mode of operation.
Reactor operation may continue indefinitely in this state, t
REFERENCE FSAR, Section 7.1
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FSAR, Section 2.7.6 i
I Amendment No. 161,144 43c
Table 3.5.1-1 (cont'd)
OTHER SAFETY RELATED 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 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)
E
- 15. Reactor Vessel Level Monitoring System 2
N/A 2
0 Note 28, 29
- 16. Hot Leg Level Measurement System (HLLMS) 2 N/A 2
0 Note 28, 29
- 17. Main Steam Line 1 / steam line N/A 1/ steam line O
Note 30 Radiation Monitors L
- 18. Control Room 2
1 2
1 Note 17, 18 Radiation Monitors i
I Amendment No. W,W 45d2 m..__-,__,-a.._m s-
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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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or verify the block valve closed and power removed within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If the block valve cannot be verified closed within the additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, de-energize the electromatic relief valve power supply within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, otherwise, Note 14 applies.
14.
With the number of chanrels J ess than required, restore the inoperable channels to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
15.
This trip function nay 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.
18.
With one channel inoperable, restore the inoperable channel to operable status within 7 days or within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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, or (2) prepare and submit a Special Report to the CommissAon 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 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 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> un2ess 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Amendment No. 6G, M,69, M,94, M4, M8 45f L
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3.8.15 Storage in the spent fuel pool shall be restricted to fuel assemblies i
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 shall be further restricted by burnup and enrichment limits specified in Figure 3.8.2.
In the event a checkerboard storage configuration is i
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 provisions of Specification 3.0.3 are not applicable.
3.8.17 The boron concentration in the spent fuel pool shall be maintained (at all times) at greater than 1600 parts per udllion.
3.8.18 During the handling of irradiated fuel, the control room emergency air conditioning system and the control room emergency ventilation system shall be operable as required by Specification 3.9.
Bases Detailed written procedures will be available for use by refueling personnel.
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 during the refueling operations that would result in a hazard to public health and safety.
If no change is being made in core geometry, one flux monitor is i
sufficient. This permits maintenance on the instrumentation.
Continuous monitoring of radiation levels and neutron flux provides immediate 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 j
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.(2)
The requirement to have two decay heat removal loops operable when there is less 1
than 23 feet of water at me the core, ensures that a single failure of the operating 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 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 suberitical, even with all control rods withdrawn from the core. (8)
Although the refueling boron concentration is sufficient to maintain the core keff s 0.99 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 j
b Amendment No. M, %, M,46, M7, M3, 59a 444,144
3.9 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING SYSTEMS l
Applicability Applies to the operability of the control room emergency ventilation and air conditioning systems.
Objective 1
To ensure that the control room emergency ventilation and air conditioning l
systems will perform within acceptable levels of efficiency and reliability.
Specification 3.9.1 Control Room Emergency Air Conditioning System 3.9.1.1 Two independent trains of the control room emergency air conditioning system shall be operable whenever the reactor
]
coolant system is above the cold shutdown condition or j
during handling of~ irradiated fuel.
3.9.1.2 With one control room emergency air conditioning system inoperable, restore the inoperable system to operable status.
i within 30 days or be in at least Hot Shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
3.9.2 Control Room 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 during handling of irradiated fuel.
3.9.2.2 With one control room emergency ventilation system inoperable, 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Cold Shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Amendment No. 10,42 60
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f Bases The control room emergency ventilation and air conditioning system is designed to isolate the combined control rooms to ensure that the control roons will remain habitable for operations personnel during and following all credible accident
[
conditions and to ensure that the ambient air temperature does not exceed the f
allowable temperature for continuous duty rating for the equipment and r
instrumentation cooled by this system. The design configuration of the system is based on limiting the radiation exposure to personnel occupying the control room to 5 REM or less whole body, or its equivalent, in accordance with the requirements of General Design Criteria 19 of Appendix A, 10CFR 50.
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Unit 1 and Unit 2 control rooms are a single environment for emergency i
ventilation and air conditioning concerns.
Since the control room emergency l
ventilation and air conditioning equipment is shared between units, the plant j
status of both units must be considered when determining applicability of the l
specification.
l Due to the unique situation of the shared emergency ventilation and air conditioning equipment, the components may be cross fed from the opposite unit per predetermined contingency actions / procedures.
During modes when the emergency control room ventilation and emergency air conditioning is not required on Unit 2, Unit 1 may take credit for operability of these systems when configured to achieve separation and independence regardless of normal power and/or service water configuration. This will be in accordance with pre-determined contingency actions / procedures.
The control room emergency ventilation system consists of two independent filter f
and fan trains, two independent actuation channels per Unit and the Control Room isolation dampers. The control room dampers isolate the control room within 10 j
seconds of receipt of a high radiation signal.
l
)
If the actuation signal can not start the emergency ventilation recirculation fan, operating the affected fan in the manual recirculation mode and isolating l
the control room isolation dampers provides the required design function of the control room emergency ventilation system to isolate the combined control rooms to ensure that the control rooms will remain habitable for operations personnel during and following accident conditions.
This contingency action should be put in place immediately (within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) to fully satisfy the design functions of l
the control room emergency ventilation system.
The control room emergency air conditioning system (CREACS) provides temperature control for the control room following isolation of the control room.
It is manually started from Unit Two Control Room.
The CREACS consists of two independent and redundant trains that provide cooling of recirculated control l
room air.
A cooling coil and a water cooled condensing unit are provided for each system to provide suitable temperature conditions in the control room for operating personnel and safety related control equipment.
I 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.
I Amendment No. 44,42 61 (next page is 66)
1 Table 4.1-1 (Cont.)
Channel Description Check Test Calibrate Remarks
- 47. RCS Subcooling Margin D
NA R
Monitor
- 48. Electromatic Relief Valve D
NA R
Flow Monitor
- 49. Electromatic Relief Block D
NA R
Valve Position Indicator a
i
- 50. Pressurizer Safety Valve D
NA R
Flow Monitor
- 51. Pressurizer Water Level D
NA R
Indicator i
- 52. Control Room Chlorine Detector S
M R
l t
- 53. EN Initiation i
t t
a.
Manual NA M
NA t
b.
SG Low Level, SGA or B S
M R
i I,
c.
Low Pressure SGA or B S
M R
I t
d.
Loss of both M W Pumps S
M R
l and PWR > 10%
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I Amendment No. M, M, M, M, M, 3-5, M 72b1 l
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4.10 CONTROL ROOM EMERGENCY VENTILATION AND AIR COMDITIONING SYSTEM l
SURVEILLAMCE Applicability Applies to the surveillance of the control room emergency ventilation and air conditioning systens.
Objective To verify an acceptable level of efficiency and operability of the control room emergency ventilation and air conditioning systems.
l l
Specification 4.10.1 Each train of control room emergency air conditioning shall be demonstrated Operable:
- a. At least once per 31 days on a STAGGERED TEST BASIS by:
- 1. Starting each unit and
- 2. Verifying that each unit operates for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and maintains the control room air temperature 584'F D.B.
I
- b. At least once per 18 months by verifying a system flow rate of 9900 cfm i10%.
4.10.2 Each Control Room Emergency Ventilation System shall be 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.
i 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:
1.
Verifying that the cleanup system satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.S.a, C.S.c, and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 2000 cfm i10%.
i 2.
Verifying within 31 days after removal that a laboratory analysis i
of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, l
March 1978, meets the laboratory testing criteria of ASTM D3803-1989 when tested at 30*C and 95% relative humidity for a methyl iodide penetration of:
i i
a.
s2.5% for 2 inch charcoal adsorber beds, or b.
50.5% for 4 inch charcoal adsorber beds.
3.
Verifying a system flow rate of 2000 cfm i10% during system operation when tested in accordance with ANSI N510-1975.
I Amendment No. 19,36,42 107
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by verifying c.
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, March 1978, meets the laboratory testing criteria of ASTM D3803-1989 when tested at 30*C and 95% relative humidity for a methyl iodide penetration of:
a.
52.5% for 2 inch charcoal adsorber beds, or b.
50.5% for 4 inch charcoal adsorber beds,
- 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. Verifying 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.
l
- e. After each complete or partial replacement of the HEPA filter bank by verifying that the HEPA filter banks remove 299.95% 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 110%.
- 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 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 and a fan.
Since the emergency ventilation system is not normally operated, a periodic test l is required to insure operability when needed.
During this test the system will be inspected for such things as water, oil, or other foreign material; gasket deterioration, adhesive deterioration in the HEPA units; and unusual or excessive noise or vibration when the fan motor is running.
Pressure drop across the combined HEPA filters and charcoal adsorbers of less than 6 inches of water at l
the system design flow rate will indicate that the filters and adsorbers are not clogged by excessive amounts of foreign matter.
Pressure drop i
should be determined at least once per operating cycle to show system performance capability.
l i
108
Bases (Continued) l The frequency of tests and sample analysis are necessary to shew 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)
" 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 results l
are unacceptable, all charcoal adsorbents in the system shall be replaced with charcoal adsorbent qualified according to Regulatory Guide 1.52.
The operability of the control room emergency air conditioning Systems ensure that the ambient air temperature does not exceed the allowable temperature for the equipment and instrumentation cooled by this system and the control Room will remain habitable for Operations personnel during and following all credible accident conditions.
Operation of the systems for 15 minutes every month will demonstrate operability of the emergency ventilation and emergency air conditioning systems. All dampers and other mechanical and.'. solation systems will be shown to be operable.
If significant painting, fire or chemical release occurs such that the HEPA filter or charcoal adsorber could become contaminated from the fumes, 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 j
this determination.
I l
Amendment No.
10Ba l
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e INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE 1
i REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS i
l 3/4.7.1 TURBINE CYCLE Safety Valves...........................................
3/4 7-1 Emergency Feedwater System..............................
3/4 7-5 Condensate Storage Tank.................................
3/4 7-7 i
Activity.......
3/4 7-8 l
Main Steam Isolation Valves.............................
3/4 7-10 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..........
3/4 7-14 3/4.7.3 SERVICE WATEP SYSTEM.......................
3/4 7-15 3/4.7.4 EMERGENCY COOLING POND..................................
3/4 7-16 3/4.7.5 FLOOD PROTECTION........................................
3/4 7-16a 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION AND 1
AIR CONDITIONING SYSTEM..........................
....... 3/4 7-17 3/4.7.8 SHOCK SUPPRESSORS (SNUBBERS)............................
3/4 7-22 3/4.7.9 SEALED SOURCE CONTAMINATION.............................
3/4 7-27 i
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 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 3/4.8.1 A.C.
SOURCES Operating...............................................
3/4 8-1 Shutdown...............................................
3/4 8-5 ARKANSAS - UNIT 2 VIII Amendment No. 40,60,6G,GG
INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 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 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 SYSTEM..................................
B 3/4 7-4 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 3/4.7.10 FIRE SUPPRESSION SYSTEMS................................
B 3/4 7-6 3/4.7.11 PENETRATION FIRE BARRIERS...............................
B 3/4 7-7 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 i
I 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 i
3/4.9.4 CONTAINMENT PENETRATIONS................................
B 3/4 9-1 l
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i ARKANSAS - UNIT 2 XIII Amendment No. 60,62
~
t TABLE 3.3-6
'i RADIATION MONITORING INSTRUMENTATION l
MINIMUM CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT t
INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTICN j
l 1.
AREA MONITORS j
a.
Spent Fuel Pool Area Monitor 1
Note 1 s 1.5x10-2 R/hr 10 101 R/hr 13 b.
Containment High 7 R/hr 18 I
Range 2
1, 2, 3& 4 Not Applicable 1 - 10 i
2.
PROCESS MONITORS a.
Containment 1.
Gaseous Activity
}
a) Purge & Exhaust Isolation 1
5& 6 s 2 x background 10 - 106 16 i
cpm b) RCS Leakage i
Detection 1
1, 2, 3& 4 Not Applicable 10 - 106 14 cpm
- 11. Particulate Activity a) RCS Leakage l
Detection 1
1, 2, 3& 4 Not Applicable 10 - 106 14 cpm b.
Control Room Ventilation L
Radiation Monitors 2
Note 2 17, 20 1.
Unit 1 Area Monitor Channel s 7 mR/hr 10 104 mR/hr
- 11. Unit 2 Ventilation Intake ' Duct 5 2 x background 10 - 106 cpm j
Monitor Channel e
c.
Main Steam Line 1/ Steam 1, 2, 3,
& 4 Not Applicable 10 104 mR/hr 19
['
Radiation Monitors Line i
I Note 1 - With fuel in the spent fuel pool or building
-l Note 2 - MODES 1, 2, 3, 4, and durir g handling of irradiated fuel l
[
i ARKANSAS - UNIT 2 3/4 3-25 Junendment No. 63,-1-30,-1-46 i
6
t 6
l TABLE 3.3-6 (Continued)
TABLE NOTATION I
ACTION 13 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring f
instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
i ACTION 14 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the l
ACTION requirements of Specification 3.4.6.1.
L ACTION 16 -
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, complete the following:
i a.
If performing CORE ALTERATIONS or moving irradiated fuel within the reactor building, secure the containment purge i
system or suspend CORE ALTERATIONS and movement of irradiated. fuel within the reactor building.
- b. If a containment PURGE is in progress, secure the containment purge system.
f c.
If continuously ventilating, verify the SPING monitor operable or perform the ACTIONS of 3.3.3.9, or secure the l
containment purge system.
ACTION 17 -
With no channels OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain' operation of the control room emergency ventilation system in the recirculation mode of operation.
ACTION 18 -
With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, (1) either restore the inoperable channel to OPERABLE status within 7 days or (2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 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 I
channels inoperable, initiate alternate methods of I
monitoring the containment radiation level within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in addition to the actions described above.
l ACTION 19 -
With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements, initiate the i
preplanned alternate method of monitoring the appropriate
(
parameter (s), within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:
l l
- 1) either restore the inoperable Channel (s) to OPERABLE l
status within 7 days of the event, or
- 2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 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.
l ACTION 20 -
With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable 3
channel to OPERABLE status within 7 days, or within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> initiate and maintain the control room emergency i
tilation system in the recirculation mode of operation.
ve ARKANSAS - UNIT 2 3/4 3-26 Amendment No. 63,430,444 l
l
TABLE 4.3-3 RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST REQUIREE 1.
AREA MONITORS 4
a.
Spent Fuel Pool Area Monitor S
R M
Note 1 b.
Containment High Range S
R Note 4 M
1, 2,
3,
& 4 2.
PROCESS MONITORS r
a.
Containment 1.
Gaseous Activity a) Purge & Exhaust Isolation Note 2 R
Note 3 5& 6 b)RCS Leakage
[
Detection S
R M
1, 2, 3,
& 4 l
ii.
Particulate Activity a)RCS Leakage Detection S
R M
1, 2,
3,
& 4 F
b.
Control Room Ventilation Radiation Monitors S
R M
Note 5 l
c.
Main Steam Line Radiation Monitors S
R M
1, 2, 3,
& 4 e
Note 1 - With fuel in the spent fuel pool or building.
Note 2 - Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to initiating containment purge operations and at least once per 12 bours during containment purge operations.
Note 3 - Within 31 days prior to initiating containment purge operations and at least once per 31 days cning containment purge operations.
Note 4 - Acceptable criteria for calibration are provided in Table II.F.1-3 of NUREG-0737.
Note 5 - MODES 1, 2,
3, 4,
and during handling of irradiated fuel.
l ARKANSAS - UNIT 2 3/4 3-27 Amendment No. 63, MO, 5 l
.m m m
m-
i PLANT SYSTEMS l
6 3/4.7.6 CONTROL ROOM EMERGENCY 7ENTILATION AND AIR CONDITIONING SYSTEM l
j i
LIMITING CONDITION FOR OPERATION 3.7.6.1 Two independent control room emergency ventilation and air I
conditioning systems shall be OPERABLE.
1 APPLICABILITY: MODES 1,2,3, 4, and during handling of irradiated fuel.
l ACTION:
j With one control room emergency air conditioning system inoperable, l
a.
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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within'the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
{
b.
With one control room' emergency ventilation system inoperable, restore l
the' inoperable system to OPERABLE status within 7 days or be in at least f
HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
j SURVEILLANCE REQUIREMENTS i
4.7.6.1.1 Each control room emergency air conditioning system shall be f
demonstrated OPERABLE:
(
l y
a.
At least once per 31 days on a STAGGERED TEST BASIS by:
j i
1.
Starting each unit from the control room, and 2.
Verifying that each unit operates for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and maintains the control room air temperature s 84*F D.B.
l t
b.
At least once per 18 months by verifying a system flow rate of l
9900 cfm i 10%.
4.7.6.1.2 Each control room emergency air filtration. system shall be demonstrated OPERABLE:
a.
At least once per 31 days on a STAGGERED TEST BASIS by
.l initiating, from the control room, flow through the HEPA filters
)
and charcoal adsorbers and verifying that the system operates i
for at least 15 minutes.
(
b.
At least once per 18 months ior (1) after any structural
)
maintenance on the HEPA filter or charcoal adsorber housings, or l
i (2) following painting, fire or chemical release in any j
ventilation zone communicating with the system by:
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J I
I ARKANSAS - UNIT 2 3/4 7-17 Amendment No.
..m
.m
_-_m m_
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued 1.
Verifying that the cleanup system satisfies the in-place testing acceptance criteria'and uses the test procedures of Regulatory Positions C.S.a, C.S.c and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 2000 cfm i10%.
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, March 1978, meets the laboratory testing criteria of ASTM D3803-1989 when tested at 30'C and 95% relative humidity for a methyl iodide penetration l
of:
l l
a.
52.5% for 2 inch charcoal adsorber beds, or
?
b.
50.5% for 4 inch charcoal adsorber beds.
l 3.
Verifying a system flow rate of 2000 cfm i10% during system operation when tested in accordance with ANSI N510-1975.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by c.
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 l
1.52, Revision 2, March 1978, meets the laboratory testing criteria of ASTM D3803-1989 when tested at 30'C and
+
j 95% relative humidity for a methyl iodide penetration of:
a.
s2.5% for 2 inch charcoal adsorber beds, or b.
50.5% for 4 inch charcoal adsorber beds.
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 Water Gauge while operating the system at a flow rate of 2000 cfm t10%.
2.
Verifying that on a control room high radiation or high chlorine 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.
e.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove 299.95% of the DOP l
when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 2000 cfm i10%.
I i
1 f
ARKANSAS - UNIT 2 3/4 7-18 Amendment No.
l l
1 e
s 3/4.3 INSTRUMENTATION BASES 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION i
The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
The PURGE as defined in the definitions section is a release under a purge permit, whereas continuous ventilation is defined as operation of the purge system after the requirements of the purge permit have been satisfied.
When securing the containment purge system to meet the ACTION requirements of this specification, at least one supply valve and one exhaust valve is to be closed, and the supply and exhaust fans secured.
The principal function of the Control Room Ventilation Monitors is to provide an enclosed environment from which the unit can be operated following an i
uncontrolled release of radioactivity.
Due to the unique arrangement of the shared control room envelope, one control room isolation channel receives a high radiation signal from the ANO-1 control room area radiation monitor and the redundant channel receives a high radiation signal from the ANO-2 control
)
room ventilation process monitor. With neither channel of the control room radiation monitoring system operable, the CREVS must be placed in a condition j
that does not require the isolation to occur (i.e.,
one operable train of CREVS is placed in the emergency recirculation mode of operation.
Reactor operation may continue indefinitely in this state.
]
1 3/4.3.3.2 DELETED l
l 3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic 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 f acility to deterndne if plant shutdown is required pursuant to Appendix "A" of 10 CFR Part 100.
The instrumentation is consistent with the recommendations of Safety Guide 12, " Instrumentation for Earthquakes," March, 1971.
3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that i
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 i
health and safety of the public and is consistent with the recommendations of Regulatory Guide 1.23 "Onsite Meteorological Programs," Feburary 1972.
3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
I
(
ARKANSAS - UNIT 2 B 3/4 3-2 Amendment No. 34,444,HO,M3 l
- _ ~
--. - - ~ -
l i
PLANT SYSTEMS BASES 2
3/4.7.6 CONTROL ROOM EMERGENCY AIR CONDITIONING / AIR FILTRATION j
SYSTEM 1
i The OPERABILITY of the control room emergency ventilation and air l
conditioning 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 i
room will remain habitable for operations personnel during and following all credible accident conditions. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less o
1 whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criteria 19 of Appendix "A",
Unit 1 and Unit 2 control rooms are a single environment for emergency j
ventilation and air conditioning concerns.
Since the control room emergency i
ventilation and air conditioning equipment is shared between units, the plant status of both units must be considered when determining applicability of the specification.
3 i
Due to the unique situation of the shared emergency ventilation and air conditioning equipment, the components may be cross fed from the opposite unit per predetermined contingency actions / procedures.
During snodes when the emergency control room ventilation and emergency air conditioning is not required on Unit 2, Unit 1 may take credit for operability of these systems when configured to achieve separation and independence regardless of normal power and/or service water configuration.
This will be in accordance with pre-determined contingency actions / procedures.
t 1
The control room emergency ventilation system consists of two independent filter j
and fan trains, two independent actuation channels per Unit and the Control Room isolation dampers. The control room dampers isolate the control room within 10 seconds of receipt of a high radiation signal.
If the actuation signal can not start the emergency ventilation recirculation fan, operating 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 4
to ensure that the control zooms will remain habitable for operations personnel during and following accident conditions.
This contingency action should be put in place immediately (within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) to fully satisfy the design functions of the control room emergency ventilation system.
The control room emergency air conditioning system (CREACS) provides temperature control for the control room following isolation of the control room.
It is manually started from Unit Two Control Room.
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 temperature conditions in the control room for operating personnel and safety related control equipment.
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.
l l
ARKANSAS - UNIT 2 9 3/4 7-5 Amendment No. 62,139 ncviced by letter dcted 0/8/95 i
. -.-._ - _ _ _ ~
- ~ - -
i PLANT SYSTIMS BASES 3/4.7.8 SHOCK SUPPRESSORS (SNUBBERS)
All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads.
Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety-related system.
The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection i
interval varies based upon the number of INOPERABLE snubbers found during the previous inspection in proportion to the sizes of the various snubber populations or categories and the previous inspection interval as specified in NRC Generic Letter 90-09, " Alternative Requirements For Snubber Visual i
Inspection Intervals and Corrective Actions".
Inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection. However, the result of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval will override the previous schedule.
When the cause of the rejection of a snubber is clearly established and remedied for that snubber and for any other snubbers that may be generically susceptible and verified by inservice functional testing, that snubber may be exempted from being counted as inoperable.
Generically susceptible snubbers are those which are of a specific make or model and have the same design features directly related to rejection of the snubber by visual inspection, or are similarly located or exposed to the same environmental conditions such as temperature, radiation and vibration.
When a snubber is found inoperable, an engineering evaluation is performed, in addition to the determination of the snubber mode of failure, in order to determine if any safety-related component or system has been adversely affected by the inoperability of the snubber. The engineering evaluation is performed to determine whether or not the snubber mode of failure has imparted a significant effect or degradation on the supported component or system.
If a review and evaluation of an INOPERABLE snubber is performed and documented to justify continued operation and provided that all design criteria are met with the INOPERABLE snubber, then the INOPERABLE snubber would not need to be restored or replaced.
To provide further assurance of snubber reliability, a representa-tive sample of the installed snubbers will be functionally tested during plant shutdowns at 18 month intervals.
These tests will include stroking of the snubbers to verify proper piston movement, lock-up and bleed. Observed failures of these sample snubbers will require functional testing of additional units.
To minimize personnel exposures, snubbers installed in areas which have high radiation fields during shutdown or in especially difficult to remove locations may be exempted from these i
l functional testing requirements provided the OPERABILITY of these snubbers was demonstrated during functional testing at either the completion of their fabrication or at a subsequent date.
ARKANSAS - UNIT 2 B 3/4 7-6 Amendment No. 142 i
l I
. ~-..
f PLANT SYSTEMS BASES 3/4.7.9 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources requiring
[
~,
leak testing, including alpha emitters, is based on 10 CFR 70.39(c) lindts for plutonium. This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values.
3/4.7.10 FIRE SUPPRESSION SYSTEMS i
1 DELETED 1
i 3/4.7.11 FIRE BARRIERS DELETED I
l 3/4.7.12 SPENT FUEL POOL STRUCTURAL INTEGRITY The reinforcing steel in the walls of the spent fuel pool was erroneously terminated into the front face instead of the rear face of the adjoining walls during construction of the spent fuel pool. Therefore, the specified structural integrity inspections of the spent fuel pool are required to be performed to ensure that the pool remains safe for use and
]
that it will adequately resist the imposed loadings.
If no abnormal degradation is observed during the first five inspections, the inspection
]
interval for subsequent routine inspections may be extended to at least once per 18 months or longer if justified by observed performance of the pool.
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5 4
ARKA!4SAS - UNIT 2 B 3/4 7-7 Amendment No. 49,-1-32
hiWKUP OF CURRENT ANO-1 TECHNICAL SPECIFICATIONS i
(FOR INFO ONLY) j l
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-. ~ _ _ _.
.m TABLE OF CONTENTS SECTION TITLE PAGE f
1.
DEFINITIONS 1
l 1.1 RATED POWER 1
l 1.2 REACTOR OPERATING CONDITION 1
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1.3 OPERABLE 2
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1.4 PROTECTION INSTRUMENTATION LOGIC 2
1.5 INSTRUMENTATION SURVEILLANCE 3
4 1.6 POWER DISTRIBUTION 4
1.7 REACTOR BUILDING 5
l 1.8 FIRE SUPPRESSION WATER SYSTEM S
l 1.9 STAGGERED TEST BASIS 5
l 1.10 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS Sa (RETS) DEFINITIONS l
1.11 CORE OPERATING LIMITS REPORT 6
2.
SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 7
l 2.1 SAFETY LIMITS REACTOR CORE 7
l 2.2 SAFETY LIMITS, REACTOR SYSTEM PRESSURE 10 2.3 LIMITING SAFETY SYSTEM SETTINGS, PROTECTIVE l
INSTRUMENTATION 11 3.
LIMITING CONDITIONS FOR OPERATION 16 3.1 REACTOR COOLANT SYSTEM 16 l
3.1.1 Operational Components 16 3.1.2 Pressurization, Heat.up and Cooldown Limitations 18 3.1.3 Minimum Conditions for Criticality 21 3.1.4 Reactor Coolant System Activity 23 l
3.1.5 Chemistry 25 1
3.1.6 Leakage 27 l
3.1.7 Moderator Temperature Coefficient of Reactivity 30 3.1.8 Low Power Physics Testing Festrictions 31 3.1.9 Control Rod Operation 32 3.2 MAKEUP AND CHEMICAL ADDITION SYSTEMS 34 3.3 EMERGENCY CORE COOLING, REACTOR BUILDING COOLING, AND REACTOR BUILDING SPRAY SYSTEMS 36 j
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 Radioactive Liquid Effluent Instrumentation 53f 3.5.7 Radioactive Gaseous Effluent Instrumentation 53I 3.6 REACTOR BUILDING 54 3.7 AUXILIARY ELECTRICAL SYSTEMS 56 3.8 FUEL LOADING AND REFUELING 58 j
3.9 CONTROL ROOM EMERGENCY VENIlLATION AND AIR CONDITIONING AND ISOLT.TIO" SYSTEM 60 j
3.10 SECONDARY SYSTEM ACTIVITY 66 3.11 EMERGENCY COOLING POND 66a l
3.12 MISCELLANEOUS RADIOACTIVE MATERIALS SOURCES 66b 3.13 PENETRATION ROOM VENTILATION SYSTEM 66c I
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Amendment No. M,M,M9 i
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SECTION TITLE PAGE l
3.14 HYDROGEN RECOMBINERS 66e 3.15 FUEL HANDLING AREA VENTILATNN SYSTEM 66g 3.16 SHOCK SUPPRESSORS (SNUBBERS) 661 3.17 FIRE SUPPRESSION WATER SYSTEM 66m 3.18 FIRE SUPPRESSION SPRINKLER SYSTEMS 66n c
3.19 CONTROL ROOM AND AUXILIARY CONTROL ROOM HALON SYSTEMS 66o 3.20 FIRE HOSE STATIONS 66p 3.21 FIRE BARRIERT 66q 3.22 REACTOR BUII.01NG PURGE FILTRATION SYSTEM 66r 3.23 REACTOR BUILDIhC PURGE VALVES 66t 3.24 EXPLOSIVE GAS MIXTUAF 66u I
3.25 RADIOACTIVE EFFLUENTS 66v i
3.25.1 Radioactive Liquid Effluants 3.25.1.1 Concentration 66' 66v i
3.25.1.2 Dose 66w l
3.25.1.3 Waste Treatment 66x l
3.25.1.4 Liquid Holdup Tanks 66y 3.25.2 Radioactive Gaseous Effluents 66z 3.25.2.1 Dose Rate 66z l
3.25.2.2 Dose - Noble Gaa,es 66aa 3.25.2.3 Dose - Iodine-131, Tritium, and Radionuclides in Particulate Form 66bb
)
3.25.2.4 Gaseous Radwaste Treatment 66cc 2
j 3.25.2.5 Gas Storage Tanks 66dd I
3.25.3 Total Dose 66ee 3.25.4 Solid Radioactive Waste 66ff I
4.
SURVEILLANCE REQUIREMENTS 67 4.1 OPERATIONAL SAFETY ITEMS 67 4.2 REACTOR COOLANT SYSTEM SURVEILLANCE 7f 4.3 TESTING FOLLOWING OPENING OF SYSTEM 58 4.4 REACTOR BUILDING 79 j
4.4.1 Reactor Building Leakage Tests 79 4.4.2 Structural Integrity 65 4.5 EMERGENCY CORE COOLING SYSTEM AND REACTOR BUILDING COOLIN'J SYSTEM PERIODIC TESTING 92 i
4.5.1 Emergency Core Cooling Systems 92 4.5.2 Reactor Building Cooling Systems 95 i
4.6 AUXILIARY ELECTRICAL SYSTEM TESTS 100 4.7 REACTOR CONTROL ROD SYSTEM TESTS 102 4.7.1 Control Rod Drive System Functional Tests 102 4.7.2 control Rod Program Verification 104 I
4.8 DCRGENCY FEEDWATER PUMP TESTING 105 I
4.9 REACTIVITY ANOMALIES 106 4.10 CONTROL ROOM EMERGENCY VENTILATlON_AND_ AIR CONDITIONING,-AND ISOL".TIO" SYSTEM SURVEILLANCE 107 4.11 PENETRATION ROOM VENTILATION SYSTEM SURVEILLANCE 109 4.12 HYDROGEN RECOMBINERS SURVEILLANCE 109b 4.13 EMERGENCY COOLING POND 110a 4.14 PADIOACTIVE MATERIALS SOURCES SURVEILLANCE 110b 4.15 AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH 4
. ENERGY LINES OUTSIDE OF CONTAINMENT 110c I
1 Amendment No. M,24, M,-34,44, M, M, ii
%,64,Mo%,W2,M4
'l 3.5.1.7 The Decay Heat Removal System isolation valve clogure setpointa j
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 l
equal to or less than 450 psig.
3.5.1.8 The degraded voltage monitoring relay settings shall be as 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:
I 1.
Peactor trip upon loss of Main Feedwater shall be operable (as determined by Specification 4.1.a and item 35 of Table 4.1-1) at greater than 5% reactor power.
(May be bypassed up to 10% reactor power. )
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 bypassed up to 45% reactor power.)
3.
If the requirements of Specifications 3.5.1.9.1 or 3.5.1.9.2 cannot be met, restore the inoperable trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or bring the plant to a hot shutdown condition.
3.5.1.10 theme control room ventilation chlorine detection systemg instrumentction shall be operable and capable of actuating control room isolation and filtrcticn gmeggency ventilation systens, with alarm / trip setpoints adjusted to actuate at a chlorine i
concentration of 55 ppm _wheneyer the reactor coolant sv_ stem is aboye tjle_ cold shutdown _condi_ tion.
3.5.1.11 For on-line testing of the Emergency Feedwater j
Initiation and Control (EFIC) system channels during power i
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, shall be operable with a minimum measurement range from 1 to 10 R/hr.
Amendment No. 60,M,69, M,M,M4 42a
m _._. - _ _..
3.5.1.13 The seismic Monitoring Instrumentation shall be operable with a minimum 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.
3.5.1.14 The Main Steam Line Radiation Monitoring Instrumentation shall be operable with a ndnimum measurement range from 10-1 to 104 mR/hr, whenever the reactor is above the cold shutdown condition.
3.5.1.15 Initiate functions of the EFIC system which are bypassed at cold shutdown conditions shall have the following minimum operability conditions:
e a.
" low steam generator pressure" initiate shall be operable when the main steam pressure exceeds 750 psig.
- b. " loss of 4 RC pumps" initiate shall be operable when neutron flux exceeds 10% power.
c.
" main feedwater pumps tripped" initiate shall be operable when neutron flux exceeds 10% power.
3.5.1.16 The automatic steam generator isolation system within EFIC shall be operable when main steam pressure is greater than 750 psig.
_3.5.1.17 Two control room ventilation radiation monitor _ing_c_hannels shall be gperable whenever the reactor coolant system is above the cold shutdown condition or dur.ina handline of irradLated fuel.
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f Amendment No. 4M,MO,M3,4-M 42b
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3 j
The OPERABILITY 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 perndt 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 consistent with the recommendations of Safety Guide 12, " Instrumentation for Earthquake," published March 19, 1971, and NUREG-0800 Section 3.7.4, " Seismic Instrumentation."
To support loss of main feedwater analyses, steam line/feedwater line break analyses, SBLOCA analyses, and NUREG-0737 requirements, the EFIC system is designed to automatically initiate EFW when:
l l
1.
all four RC pumps are tripped 2.
both main feedwater pumps are tripped i
3.
the level of either steam generator is low 4.
either steam generator pressure is low I
5.
ESAS ECCS actuation (high RB pressure or low RCS pressure) j l
The EFIC system is also designed to isolate the affected steam generator on a steam line/feedwater line break and supply EFW to the intact generator according to the following logic:
l If both SG's are above 600 psig, supply EFW to both SG's.
I If one SG is below 600 psig, supply EFW to the other SG.
If both SG's are below 600 psig, but the pressure difference between the two SG's exceeds 100 psig, supply EFW only to the SG j
with the higher pressure.
I 1
If both SG's are below 600 psig and the pressure difference is less j
than 100 psig, supply EFW to both SG's.
)
l At cold shutdown conditions all EFIC initiate and isolate functions are bypassed except low steam generator level initiate. The bypassed functions will be automatically reset at the values or plant conditions identified in Specification 3.5.1.15.
" Loss of 4 RC pumps" initiate and " low steam generator pressure" initiate are the only shutdown bypasses to be manually initiated during cooldown.
If reset is not done manually, they will automatically reset. Main feedwater pump trip bypass is automatically removed above 10% power.
Lhe principal function of the Control Room Isolation-Hich Radiation is to provide an enclosed environment from which the unit can be operated followino an uncont_ rolled release of radioactivity.
Due to the uni.que__anancement of the shared control room envelope, one control room isolation channel receives a_high radiation signal from the ANO-1 control room area radiation monitor and the redundant channel receives a high radiation si.gnal from the ANO-2 control room ventilation process monitor. With neither channel of the control room radiation i
moni_t_oLing_syslem operable,__the CREy,S must be placed_in a condition that does not l
require the isolation to occur _li.e.,
one operable train of CREVS is placed in i
the emeroency recirculation mode of op_eration.
Reactor operation may continue
)
indefinitely _in,this_stggpa l
REFERENCE l
FSAR, Section 7.1 i
FSAR, Section 2.7.6 Amendment No. M1,4'R 43c
Table 3.5.1-1 (cont'd)
OTHER SAFETY RELATED 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 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 Measuretaent System (HLLMS) 2 N/A 2
0 Note 28, 29
- 17. Main Steam Line 1 / steam line N/A 1/ steam line O
Note 30 Radiation Monitors
- 18. Control Room g
1 2
1 Note 17, 18 Radiation Monitors Amendment No. W,M3 45d2
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- 20 4--
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6 a
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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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or verify the block valve closed and power removed within an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
If the block valve cannot be verified closed within the additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, de-energize the electromatic relief valve power supply within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, otherwise, Note 14 applies.
14.
With the number of channels less than required, restcre the inoperable channels to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in HOT SHUTDOWN within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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.
i l
17.
With no channel operable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> rectcre the incperchic channcic to cperabic status, cr initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.
18.
With one channel inoperable, restore the inoperable channel to operable status within 7 days or within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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, or (2) prepare and submit a Special Report to the Commission 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in 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 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
Amendment No. 60, G,69, M,94,4-04, -144 45f 1
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3.8.15 Storage in the spent fuel pool'shall be restricted to fuel assemblies l
having initial enrichment less than or equal to 4.1 w/o U-235. 'The r
provisions of _ Specification 3.~ 0.3 are not applicable.
l 3.8.16 Storage in Region 2 (as shown on Figure 3.8.1) of the spent fuel pool shall be further restricted by burnup and enrichment limits specified in Figure 3.8.2.
In the event a checkerboard storage configuration is i
deemed necessary for a portion of Region 2, vacan; spaces adjacent.to j
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 l
fuel assembly insertion into two adjacent storage locations. The l
provisions of Specification 3.0.3 are not applicable.
3.8417 The boron concentration in the spent' fuel pool shall be naintained (at l
all times) ~ at greater than 1600 parts per million.
f 3.8.18 Durina the handlina of irradiated fuel, the control room emeraency air l
conditionina system and the co.ntrol room emergency ventilation system shall be operab_le as recuired by Specification 3.9.
{
Bases l
Detailed written procedures will be available for use by refueling personnel.
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 during the refueling eperations that would result in a hazard to public health and safety.
If no change is being made in core geometry, one flux monitor is sufficient. This permits maintenance on the instrumentation. Continuous monitoring of radiation levels and neutron flux provides immediate indication of i
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 (no rmally 14 0
- F), and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution i
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 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 j
the event of a failure of the operating decay heat removal loop, adequate time is provided to initiate emergency procedures to cool the core.
l The shutdown nargin indicated in Specification 3.8.4 will keep the core suberitical, even with all control rods withdrawn from the core. (8)
Although the refueling boron concentration is suf ficient. to naintain the core keff s 0.99 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 i
i Amendment No. M, M, M, M,4M, M3, 59a 144,474
~
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3.9 CONTROL ROOM EMERGENCY V_ENllLATION AMD AIR CONDITIONING.'."O ISOL.'.T4GN I
SYSTEMS L
t Applicability l
Applies to the operability of the control room emergency ventilation and air l
conditionin9 :nd i:01stian systems.
Objective i
l To ensure that the control room emergency ventilation and air conditioning and j
tee +etten systemp will perform within acceptable levels of efficiency and reliability.
]
i i
specification I
i 3.9.1 Control Room Emeraency_ Air Conditionina System i
i J
3.9.1.1 Two independen.t trains of the control room emeraency air conditioniqq_gystem shall be operable whenever the reactor coolant system is above the cold shutdown condition or durina j
handlina of irradtated fuel.
3.9.1.2 With one control room emeroency air conditionina system inoperable, restore the inoperable system to Operable status within 30 days or be in at least Hot Shutdown within the next 6 houts_and in Cold shutdown within the followina 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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3.9.2 Control Room Emercency Ven_tilation System
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3.9.2.1 Two indeoeqdent trains of th.e centrol room emeraencv ventilation system shall be opergb_le_whenever the reactor coolant system is above the cold shutdown condition or durina handlina of
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1rradiated fuel.
Amendment No. +0,43 60
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l 2 9.2.2 with one control room em,rcency ventilation systern inoperable, restore the inoperable evstem to Operable status within 7 days or pf_in at least Hot Shuti. own within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in Col _d d
. Shutdown within the followina 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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l Amendment No. M,M 60 l
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Bases
(
i The cent:ci :cc cmc g:ncy est-- cnditioning and i:cletien syster le l
designed tc i clate th: ecnt::1 rec and filter the ccat:cl ::::
etmeeph::: during cent: 1 cc: isc1: tion condition:.
One circuit to-designed tc autcmatically : tart upon cent:cl rec i cletica :nd the cthe: circuit tc bc me.nually cts:ted on failurc cf the first t
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Migh c f ficicncy pert 4 culate ci: (MEP74 filter ::: instalicd befc :
the chatecal cd:::bc:: tc p cvent cicgging cf the iodinc ad:::becer The ch ::ccl ad ::bcr: :: installed t: :cduce the. pctential intake l
i cf : dicicdine-t-e-t4.c cont:cl Iccr The in-placc test result; ehe ad indiccte c cystcr leak tight-nc : cf 1c:: than 1 p : cent bypes: Icake9c fc: the ch:::cc1 cd:::ber: cnd MEP".-effieleney-ef J
at Ic=:t "O pc: cent ::moval cf DOP p; ticulatce.
The Icberatory eetbcn : mpic test :: ult cheuld indicate
- dicartive methyl 4edid: Ic=>va4-effi-e-lency cf at les:t 90 p : cent fc cup;cted l
eccident ccadi-ticas.
If the efficiencic cf the MEP". filter: and i
ehe::c=1 ad:c:ber ::= :: :pccificd, the :: ulting de:::.:ill b; l
1ess-than th: 2110wab1: level stated in Criterien 10 cf the 1
ceneral Design c iteria for nuclear Power Planto, 7.ppendin ? to 10 r
CF" Pc:t 50.
Opc stien of the fan: significantly diffe:cnt f:c the dccign f4ew uill change th: ::::" 1 cfficicncy of the MEPA filt=:: and ch :ccal =d:c:b ::.
If anc circuit of the ecat:ci :ccr cmc:gency ci: ccndi-t4cning and l
inc1stien eyeter i; fcund tc be incpc::bic, there is act en ir=.cdiate th:::t to the cent:c1 :ccr :nd ::::to: cp:::tica m:y eentinue fc:
limited p : icd Of ti== ;;hil; cpcir; c:: being made.
)
i i
If th: ecnt:ci-::cn i:clation dampc:: ::: madc c: fcund to bc inoperabic, continued :cactc; cperation is allcued p cvided the petential fc cut:ide cir f4ew i
- cm;ved :: p:cvided by Specification 3.0.3.
The 10 ccecnd cicru:: tim Icquircment in far belca that cquired tc cuppc:t accident dcs: 21culations and is thercfc:: ccncetwt-iver Ihe contI.ol_ room _. emergency,yentiJation_and air conditioning _systep_is_ designed to 1.splate_the_co.mbined,gonttpl._roomsJ o ensure that_1he contIol rooms will remain DLa bit ab l e_lo r__ Ope rn t A on s_ peI s o nn e l__du ri n g _a n d_f o ll owi ng_a l l_c r e d i b l e_ a c_gi d en_t.
e gonditions and to ensure _that_the ambient air temperature does not exceed the allowable temperature,for_pont_ijugus_ duty _ rating for the equipment _and instrumentation cooled _by_t_his_ system.
The design conf _iguration_pf the system _is bas _e_d on limiting _the_ radiation _ exposure _1pJ ersonnel occupying _the_pontrol_Ioom to 5 REM or_less_whole_ body,_or its e_quivalent, in accordance with the requirements of General Design Criteria 19 of_Appe_ndix A, _10CFR 50.
Unit 1 and_ Unit _2_gontrol rooms are a single en',ironment_for_emerjengy yentilation,and_ air _cnnditioning concerns.
Since the contro LLopm_ emergency yentilation and air conditioning _equ_ipment is shared between units, the_plang g}_atus gf_bg y nits must be considered _wh_en_ determining _appli_gability_oi the j
j Ep_ejifAcaliom l
i Due to the unique situation of the shared emergengyg eJLilation_and_ air cpndi_tigning g guipmentt.the_gomponents_may_be_ cross fed _from_the_ opposite _ unit per g edetermined contingenpy, actions /Jroce_dures.
During modes when the eM L9eD97J oltt31 room ventilatign,aJd,eyeyggngy_ air,qonditioning_isJ ot_requirej n
eMDAtl Vni3Jyyjake credit _.for operab_ilily_of these syst p s,yhen ponfAgured to apjieve_ separation _and_iqgigpendenge_regardless of normal,ppyel Amendment No, M,M 61 (next page is 66)
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I a.nd/pr_s eryl ee_wa t e r_ con fi gu r a t i on.
This will be in accordance with_ pre _-
j dgtgratappJ gntjJ13ggp1 ag(ipjls/pIgpedpigs2 i
he_ control room emergengy_ ventilation _ system consisJs of two_ipjdepgn, dent _filteI l
n agLfy.,3 rains 4 two independent. actuation channels _per_ Unit and the Control Room A solationja{npers.s_The control room dampers isolate the control room wi_tbin_1.0 Ee,conds_gf_.re ce ipt_pf_a _hi g). r a di a t ign_ s i.gna l. If the actuation signal can not close the con 3rol._ room _ isolation damper g isolating _the coDtrol_ room _by_ manually j
o plos_ing the affected control poem _dampgtsg r_gyldes the required isolation desian function of_the Control Room Emergengy_ Ventilation System.
}
t If_the_actuatioR_sJgnal_can_not start the emergency _veggation recirculation Lan,_opega.t_ing the affected fan in the manual recirgulation mode and isol tipJ i
a i
the control _toom.JAo}ation_dampgers_plovides the_ required design _fungtf on of the l
conttpl_foom__emergengy_ventil_ation sy_ stem to isolate the combined control _ rooms
~
to ensure that_the_ control topms_will_ remain habitable f o r_op. elations,pe rs onnel during,.agdj oJ 1 owi ng_ a ccA denLepndili ons.
This contingency actipn should be pul in. place immediately_1within 1 hou11_to fully _ satisfy _the__ design _ functions of f
h 1p_e control room..emeIge,n g ventilation systema lhlp_controlgoom emergengy_ air conditioninggystem (CREA_CSJJrovides temperature gpnyol_for the conttpl ropMgilowing_isojation of the contIol room. _Ji_Ag
{nanually_ started _f rom._U_ nit _Two Control Room.
The CREACS consists of two independent and redundant trains that_provAde cooling _of recirculated control l
room air.
A cooling _goil_and_a_ water cooled condensipj_ unit are provided_for each_ system to proyide_ suitable _ temperature conditions in the control room for ppera t i n g._peJ_s onnel_.aacLs a f e ty_ r el a t ed con t rol_ eguipmenta t
i HQh,_both_ trains of the control room emeroency ventilatign__andLor emeraency_aig ponditi_oning i_ggpegabel., the function of_the control room eme_rgen.gy_ air systems s
baye_been_ lost,_riquir.ing_immediate_agtion to place the reactor _in a condition whete_the_ specification does not pyp h I
I i
l I
i Amendment No. M,M 61 (next page is 66)
Table 4.1-1 (Cont.)
Channel Description Check Test Calibrate Remarks
- 47. RCS Subcooling Margin D
NA R
Monitor
- 48. Electromatic Relief Valve D
NA R
Flow Monitor
- 49. Electromatic Relief Block D
NA R
Valve Position Indicator i
- 50. Pressurizer Safety Valve D
NA R
Flow Monitor
- 51. Pressurizer Water Level D
NA R
Indicator
R l
- 53. EEW Initiation a.
Manual NA M
NA L
b.
SG Low Level, SGA or B S
M R
c.
Low Pressure SGA or B S
M R
d.
Loss of both MEW Pumps S
M R
and PWR > 10%
r 9
Amendment No. M, M, M, M, M,4-M,-1-4 72b1
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4.10 CONTROL ROOM EMERGENCY MILATION AN_D_ AIR CONDITZONING-AND-I-SGIAMON l
SYSTEM SURVEILLANCE Applicability Applies.to the surveillance of the control room emergency ventilation and air conditioning :nd i 01 blen systems.
Objective To verify an acceptable level of efficiency and operability of the control room emergency ventilation and air conditioning :nd is:1stien systemg.
l Specification 4.10.1 Each train of control room emeraency air conditionine shall be demonstrated Operable:
- a. At least once per 31 days on a STAGGERED TEST BASIS ig
- 1. Startina each unit and
- 2. Verifyino that each unit operates for at least I houI and maintains the control room air temperature 584'F D.B.
- g. At least once per 18 months by verifyinc a system flow rate of 9900 cfm i10%.
ht int::: 1: :t : cu:::d 1" r. nth:, the p::::u:: d::p :::::: the
- bin
- d " EPA filter nd ch:::: 1 cd:::b : henk: : hall b der. nct:sted t b; le:: th:n 5 inche: Of unter :t y:ter d::ign flou (i10M.
4.10.2 Each Control _ Boom Emeraency Ventilation System shall be demonstrated Operable:
At least once per 31 days on a Staccered Test Basis by initiatingt a.
from the Control Room, flow throuch the HEPA filters and charcoal adsorbers and verifV1Da that the system operates for at lea.st 15 minutes.
l b.
At least once per 18 months or 1)after any structural maintenance on the HEFA fiiter or charcoal adsorber housinas, or 2) followine significant pa:.ntina, fire, or chemical release in any ventilatio3 tone communicating _with t.be system by:
1.
Verifyina_tbat the cleanup system satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.5.a, C.5.c, and C.S.d of Reculatory Guid.e 1.52, Revision 2, March 1978, and the system flow rate is 2000 cfm i10%.
l 2.
Verifvine within 31 days after removal that a laboratory analysis l
of a representative carbon sample obtained in accordance with Reculatory Position C.6.b of Reaulatory Guide 1.52, Revision 2, j
March 1978, meets the laboratory testina criteria of ASTM l
D3803-1989 when tested at 30*C and 95% relative humidity for a methyl _ iodide. penetration of:
I a.
s2.5% for 2 inch charcoal adsorber bedst_or l
b.
50.5% for 4 inch charcoal adsorber beds.
3.
Ver.ifyJna a system flow rate of 2000 cfm i10% during.syst_em operation when tested in accordanc_e_with ANSI N5_10-1975.
Amendment No. M,M,M 107 l
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Amendment No. 9,M,M 107 1
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j After everv 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation _by_ verifying c.
within 31 days after removal that a laboratory anal,ysis of a representative carbon sampJp_obtained in accordance with Reculatory l
{ps1$1on_C f2p_of_Be,gulatory Guide ld2, Revision 2 March 1978 g
g 4
meets the laboratory _testina criteria of ASTM D3803-1989 when tested at 30*C and 95% relative humidity for a me.thyl iodide. penetration of:
a2__52.5% for 2 in_ch charcoal adsorber beds, or b,__n0.5% for_A_ inch charcoal adsorber beds.
1
- d. At least onc_e_per l__8 months by l
l k V rJfying_that the_ pressure drop,across the combined HEPS L
o m
filters and charcoal adsorber banks is <6 inches of water while operating _at a flowrate of 2000 cfm fl0%.
_2. Verifyin_g_tjlat on_a control _ Boom _hish radiation test s_1.gn_al i
u heg t
gystem automatically __ isolates the Control Room within 10 seconds and_swi.tches_into_a_Lecircula_ tion mode of_ operation with flow th ough the HEPA filters and charcoal adsorber_ banks 1 I
e1_Aiter each comnl,e,te or_pattial_I_eplacement of the HEPA_ filter _b_ank by verifying that the HEPA filter banks remove 299.95% of the DOE whe_n they are tested in-place in accordance with ANSI N510-1975 while one_ rating _the_ system _at_a_ flow rate of 2000 cf _110%.
- f. After each complete or_ partial replacement _of a charcoal adsorber pan 1_bg v_er.1fying_that the charcoal adsorbers remove 299.95% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1975 while operating the gystem at a flow rate of 2000 cfm 110%.
Bases The purpose of the control room filtering emergency.ventilajien system is to l
limit the particulate and gaseous fission products to which the control area would be subjected during an accidental radioactive release in or near the i
Auxiliary Building. The system is designed with 100 percent capacity filter trains which consist of a prefilter, high efficiency particulate filters, charcoal adsorbers and a fan.
l Since the emergency ventilation system system is not normally operated, a periodic test is required to insure operability when needed.
During this test the system will be inspected for such things as water, oil, or other foreign materiali 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 HEPA 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 clogged by excessive amounts of foreign matter.
Pressure drop should be determined at least once per operating cycle to show system performance capability.
Thc frequcacy of tect: and : =p?.c analysi
- neccccary tc chcu that thc HEP?. filter and charecci adscrber: can perform : cvaluated.
The chacee*1 adeetbcr cfficiency tcat procedures chculd allca for cbtaining at Icsst tuc j
- =plcc.
Each ::=plc cheuld bc at least tuc inchn in diameter and a length equal to the thicknc;; cf the bed.
Test; cf the charccal adscrber; i
aith DOP acrc:cl shall be performed-in acccrdance arth ?J!SI '510 (1975)
" Standard for Testing cf *?acicar 7.ir C1 caning System:." 7.ny MEP" f41+ete tcund defective shall be replaced with filt-er qualified according te 108 l
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1 i
Baces (Continued) l The frequency of tests and sample analysis ate _nec_espary_to show that the i
RE_P_A_ filters and chatcoal adsorbers can perfornLas_eyaluated.
The chargoal l
I a d s_ orb gr._ef fi cj en gy_t_e s t_p r o c edu r e s should allow for obtainino at least_twg
_sjmpl e s.
Each samp.le should be at least two inches in diameter and a
};ngth_e_ qual to the thickness of the bed.
Tests of the charcoal adsorbers with DOP aerosol shall be_ performed in accordance with ANSI N510 (1975),
i
Standard fyI_Tesling_o_f Nuclear Air Cleaning _ Systems. " Any J EPA filters found defective shall be gplaced with filtels_gualified according_t,g Begulatory_Positipn C.3.d of_ Regulatory Guide 1.5E. If laboratory _t_est results
)
are unacceptable,_all charcoal adsorbents in the system _shall_be_ replaced wi_t_h j
charcoal adsorbent _ qualified aggording_to, Regulatory _ Guide _L_523 The,,,operabiMyty_of the Control Room Emegency Air Conditioning _Syg ems ensure that_the_ ambient _aig_tempe_tature does not exceed the allowable temperature for
$DLe_eggiyplent_and_ instr.umentation cooled by_this_ system and the Control Room will j
remain habitable for Operat;i_ons_pe_rsonnel_duringgnd following all credible accident condi t; ions.
O eration of thegystems for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> every_ponth will demonstra.te operab.i_lity J
of the emergency ventilation and emercen_cy air conditionino systems. All dampers and other mechanical and isolation systems will be shown to be operable 4 Jf sign 111_ cant _ pain 11pm fire or chemical release occurs such that the HEPA M M er or. charcoal ads _orber cou_ld become contaminated from the fumes, cheminals or foreiggjnaterilab the same tests and sample analysis shall be pel ormed as required for operational use.
The determination of f
significant shall be made by_the operator.on duty at the time of the Ann,cidenL _.Knowle_dgeable stafi members should be consulted pr_ior to making this determinat; ion.
i Amendment No.
10Ba l
y w
4 4
0 I
MARKUP OF CURRENT ANO-2 TECHNICAL SPECIFICATIONS (FOR INFO ONLY) i i
INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE Safety va1ves.......................
3/4 7-1 Emergency Feedwater System..............................
3/4 7-5 Condensate Storage Tank.................................
3/4 7-7 Activity................................................
3/4 7-8 Main Steam Isolation Va1ves.............................
3/4 7-10 3/4.7.2 STEAM GENERATOR PRESSURE / TEMPERATURE LIMITATION..........
3/4 7-14 3/4.7.3 SERVICE WATER SYSTEM....................................
3/4 7-15 3/4.7.4 EMERGENCY COOLING POND..................................
3/4 7-16 3/4.7.5 FLOOD PROTECTION........................................
3/4 7-16a l
3/4.7.6 CONTROL ROOM EMERGENCY ifENI SAT _I_ON_AND_ AIR CONDITIONING AND-AIR
(
FI LT R?iT I ON SYST EM.....................................
3/4 7-17 l
3/4.7.8 SHOCK SUPPRESSORS'(SNUBBERS)............................
3/4 7-22 I
3/4.7.9 SEALED SOURCE CONTAMINATION.................
3/4 7-27 3/4.7.10 FIRE SUPPRESION SYSTEMS i
Fire Suppression Water System...........................
3/4 7-29 Spray and/or Sprinkler Systems..........................
3/4 7-33 Fire Hose Stations......................................
3/4 7-35 3/4.7.11 FIRE BARRIERS...........................................
3/4 7-37 3/4.7.12 S P ENT FU EL POOL ST RU CTU RAL I NT EGRI TY....................
3/4 7-38 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C.
SOURCES operating...............................................
3/4 8-1 Shutdown...............................................
3/4 8-5 ARKANSAS - UNIT 2 VIII Amendment No. M,60,62,&9
INDEX BASES SECTION PAGE 3/4.7 PLANT SYSTEMS 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
3/4.7.3 SERVICE WATER SYSTEM....................................
B 3/4 7-4 l
3/4.7.4 EMERGENCY COOLING POND..................................
B 3/4 7-4 3/4.7.5 FLOOD PROTECTION........................................
B 3/4 7-4 3/4.7.6 CONTROL ROOM EMERGENCY VEN.TIIATION_AND_ AIR CONDITIONINC/7.!P FILTP1.
TION SYSTEM............................................
B 3/4 7-4 3/4.7.8 SHOCK SUPPRESSORS (SNUBBERS)............................
B 3/4 7-5 3/4.7.9 S EALED 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 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 3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONC ENT RATI ON......................................
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 i
i r
l 1
ARKANSAS - UNIT 2 XIII Amendment No. 60,62
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 5 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 1.
Gaseous Activity a) Purge & Exhaust Isolation 1
5& 6 5 2 x background 10 - 106 16 cpm b) RCS Leakage Detection 1
1, 2,
3& 4 Not Applicable 10 - 106 14 cpm li. Particulate Activity a) RCS Leakage Detection 1
1, 2, 3& 4 Not Applicable 10 - 106 cpm 14 b.
Cc. trol Room Ventilation Radiation 4
Intch Duct Monitorg
-11 Note 2ALI. " ODES s2 - backg cund 10 10 -epm 17, 20 1.
Unit 1 Area Monitor Channel s 7 mR/hr 10 104 mR/hr ii. Unit 2 Ventilation Intake Duct s 2 x backaround 10 - 106 com Monitor Channel c.
Main Steam Line 1/ Steam 1, 2, 3,
& 4 Not Applicable 10 104 mR/hr 19 Radiation Monitors Line Note 1 - With fuel in the spent fuel pool or building Note 2 - MODES 1, 2,
3, 4, and durina handlina of irradiated fuel l
ARKANSAS - UNIT 2 3/4 3-25 Amendment No. 63,-1-30,-1-44 m
-.,,m...
-.-o-y
TABLE 3.3-6 (Continued)
TABLE NOTATION l
ACTION 13 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
ACTION 14 -
With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.6.1.
ACTION 16 -
With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, cuaplete the following:
- a. If performing CORE ALTERATIONS or moving irradiated fuel within the reactor building, secure the containment purge system or suspend CORE ALTERATIONS and movement of irradiated fuel within the reactor building.
- b. If a containment PURGE is in progress, secure the containment purge system.
c.
If continuously ventilating, verify the SPING monitor operable or perform the ACTIONS of 3.3.3.9, or secure the containment purge system.
ACTION 17 -
With the number efag channels OPERABLE less than required by the-Minimur Channel: OPEPJ.SLE ::quirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.
ACTION 18 -
With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, (1) either restore the inoperable channel to OPERABLE status within 7 days or (2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in addition to the actions described above.
ACTION 19 -
With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirements, initiate the preplanned alternate method of monitoring the appropriate parameter (s), within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, and:
- 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 Conadssion pursuant to Specification 6.9.2 within 14 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, t
ACTION 20 -
Wit;h the number of channels ofQBB1Q,rp less than reouired by the l
ginimum Channels OPERABLE reouiremeM u g gre the inoperable ghannel to OPERABLE status within 7 days,_pr,within the next 6 ARKANSAS - UNIT 2 3/4 3-26 AmendL mt. No. 63,4-30,446
hours __ initiate and maintain ~ the_qontrol room ernerawncy ventilatio3 pystem in the recirculation mode of ppe_ rat;. ion.
I i
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4 4
4
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4 ARKANSAS - UNIT 2 3/4 3-26 Amendment No. 63,-140,-146
l TABLE 4.3-3 BADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE INSTRUMENT CHECK CALIBRATION TEST REQUIRED 1.
AREA MONITORS a.
Spent Fuel Pool Area Monitor S
R M
Note 1 b.
Containment High Range S
R Note 4 M
1, 2, 3,
& 4 2.
PROCESS MONITORS a.
Containment i.
Gaseous Activity a) Purge & Exhaust l
Isolation Note 2 R
Note 3 5& 6 b)RCS Leakage Detection S
R M
1, 2,
3,
& 4 li.
Particulate Activity a)RCS Leakage Detection S
R M
1, 2, 3,
& 4 b.
Control Room Ventilation RadiationIntch: Duct Monitors S
R M
Note SALL MGBEG c.
Main Steam Line Radiation Monitors S
R M
1, 2, 3,
& 4 f
Note 1 - With fuel in the spent fuel pool or building.
Note 2 - Within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> prior to initiating containment purge operations and at least once per i
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during containment purge operations.
Note 3 - Within 31 days prior to initiating containment purge operations and at least once per 31 days during containment purge operations.
l Note 4 - Acceptable criteria for calibration are provided in Table II.F.1-3 of NUREG-0737.
Note 5 - MODES 1, 2,
3, 4,
and durina handlina of irradiated fuel.
ARKANSAS - UNIT 2 3/4 3-27 Amendment No. 63,-140,446 w
u.-
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a PLANT SYSTEMS 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATIONAI" CONDITION!NC AND AIR CONDJIIONINCrF 4LT"ATION SYSTEM LIMITING CONDITION FOR OPERATION 3.7.6.1 Two independent control room emergency ventilationair : nditioning and air conditioningfiltration systems shall be OPERABLE.
APPLICABILITY:
MODES 1,2,3 end-4, and durina handlina of irr_adiated fuel.
l ACTION:
a.
With one control room emercency air conditionina system inoperable, restore the inoperable system to OPERABLE status w:Jhin 30 days or be in at least MOT _S7_AliD_BJ within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the follow 1_no 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With one control room emergency ventilatiggeir conditioning-:: cir filtration system inoperable, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.7.6.1.1 Each control room emergency air conditioning system shall be demonstrated OPERABLE:
a.
At least once per 31 days on a STA';GERFD TEST RASIS by:
1.
Starting each unit from the control room, and 2.
Verifying that each unit operates for at least 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and maintains the control room air temperature s 84 *F D.B.
b.
At least once per 18 months by verifying a system flow 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 RASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying 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 housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:
I l
l ARKANSAS - UNIT 2 3/4 7-17 Amendment No.
I
m e
a PLANT SY3TEMS SURVEILLANCE REQUIREMENTS (Continued 1.
Verifying that the cleanup system satisfies the in-place testing acceptance criteria and uses the test procedures of Regulatory Positions C.S a, C.S.c and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 2000 cfm i10%.
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, March 1978, meets the laboratory l
testing criteria of neguictcry Pccition C.S.
cf Regulatory i
Cuide 1.52, nevisien 2, March 1979_ ASTM D3803-1989 when tested _at l
3_0*C an_d 95% relati.ve_humidityfor a methyl iodidelenetJation 911 a.
52.5% for 2 inch charcoal adsorber beds 2_cg b.
60.5% for 4 inch cha.rcoal adsorber beds 1 3.
Verifying a system flow rate of 2000 cfm i10% during system operation when tested in accordance with ANSI N510-1975.
c.
After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation by 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, March 1978, meets the laboratory testing criteria of Ecguictory Pccitica C.S.c cf negulatcry Cuide 1.52, ncvicicn 2, March 1979._ASTK_pl803-1989 w3en tes_t;ed at 30'C and 95%
- g. elative humidity _for a methy.1 iodide _ penetration of:
a.
s2.5% for 2 inch charcoal adsorber beds,,,gg b.
50.5% for 4 inch charcoal adsorber beds.
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 Water Gauge while operating the system at a flow rate of 2000 cfm i10%.
2.
Verifying that on a centrol room high radiation or high chlorine 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.
1 c.
After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove 199.95% of the DOP l
L when they are tested in-place in accordance with ANSI N510-1975 while operating the system at a flow rate of 2000 cfm 110%.
I l
l ARKANSAS - UNIT 2 3/4 7-18 Amendment No.
l l
3/4.3 INSTRUMENTATION BASES 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION k
The OPERABILITY of the radiation monitoring channels ensures that 1)
{
the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
The PURGE as defined in the definitions section is a release under a purge permit, whereas continuous ventilation is defined as operation of the purge system after the requirements of the purge permit have been satisfied.
When" securing the containment purge system to meet the ACTION requirements of this Specification, at least one supply valve and one exhaust valve is to be closed, and the supply and exhaust fans secured.
The,principa1 function of the Contr_ol Room Ventilation Monitors is to provide an enclosed environment from which the unit can be operated followina an i
uncontrolled release of radioactivity.
Due to the unicue arrangement of the shared control room envelope, one control room isolation channel receives a hiah radiation si_gnal from the ANO-1 control room area radiation monitor and the l
redundant channel receives a hich_ radiation sianal from the ANO-2 control room ventilation process monitor. With nei.ther channel of the control room radiation i
modi _t.oring _ system _ operable, the CREVS must be _placed in a condition that does pot recuire the isolation to occur (i.e.,
one o_perable train of CREVS is placed in the emergency recirculation mode of operation.
Reactor operation may continue inde.finijLely_in this state.
3/4.3.3.2 DELETED I
3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic 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 10 CFR Part 100.
The instrumentation is consistent with the recommendations of Safety Guide 12, " Instrumentation for Earthquakes," March, 1971.
3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive raterials 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 recommendations of Regulatory Guide 1.23 "Onsite Meteorological Programs," Feburary 1972, i
3/4.3.3.5 REMOTE SHUTDOWN INSTRUMENTATION l
The OPERABILITY of the remote shutdown instrumentation ensures that sufficient capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room.
This capability is required in the event control room habitability is lost and is consistent with General Design Criteria 19 of 10 CFR 50.
I ARKANSAS - UNIT 2 B 3/4 3-2 Amendment No. M,MO,HO,MB
_,__.__m
)
PLANT SYSTEMS I
i BASES
)
3/4.7.6 CONTROL ROOM EMERGENCY AIR' CONDITIONING / AIR FILTRATION i
SYSTEM -
'l 1
The OPERABILITY of the control room emergency ventilation and air conditioning /e h filtrctic.. 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 i
room will remain habitable for operations personnel during and following all credible accident conditions. The OPERABILITY of this system j
-in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criteria 19 of Appendix "A",
p311 1 and Unit _2 control rooms aJe a single environment for emeraency l
ventilatign_and_ air condili_opina concerns.
Since the control room emeraency i
yentilat_ ion and air conditionina equipment is shared between units, the plant
-l status of both units must be considered when determinina applicability of the 222,citLcation, pue to the unique situation of_the shared emeraency ventilation and air l
l conditionina equjpgeni,_the components may_be cross fed from the opposite unit I
l per_pIedetermiped continaenc_y_actipns/ procedures.
Durina modes when th_e, emerge.ncy control rogm ventilation and emeroency air conditio31na is not recuired
]
pn_ U__pi t 2. Unit 1 may take credit for operability of these systems whem l
pQnfigured to achieve separation and independence recardless of normal _ppwer p
and/or_ service water configuration.
This will be in accordance with_ pre-getermined_ contingency actions / procedures 1 The control room emeIgency_ ventilation system consists of two independent filter pnd fan _tratjls, two independent actuation channels per Unit and the ContIol RopJn isolation dampgrs. The control room dampers ijolate the control room witJJn 10 l
seconds of recei.pt_of a hiah radiation sianal.
{
i e
If the actuation signal can not start the emergency ventilation recirculation I
Lan,__pperating_1he affected_ fan _in the manual reci.rculation mo.de_and isolatimg the contIgl room isolation dampers provides the re_guired design _fungtion of the l
control room emergen_qv veptilation sys_ tert to_ isolate the combJned control rooms to ensure that the control rooms will remain habitable for operations _ personnel during and f ollowing accident conditions.
This contingency action should be put in_ place immediately (within 1 hourJ_to fully _ satisfy _the design _ functions __of i
l the control room emerseDev ventilalipp. system.
The control room emergeng.y_ air conditioning _ system (CREACS_J_proyJdes temperatute s
p,gntrol for the contIpl room fo.llowina isolation of the control room.
It is mgually_ started _frpm Unit Two Control Room.
The CREACS consists of two independent and redundant trains that provid_e cooling of recirculated _c_ontrol room air.
A cooling y il and a water cooled condensino unit are provided for each sys_ tem to provide suitable temperature conditions in the control room for pperating_pers_ panel _and safety _related control equip. men 12 1
pjfh both trains of the control room emergengy ventilatiertandLoggrnerge_ngyMI i
pons;litioning_inoyeIable,_the funglion of the control room emeraency air systems have been lost,_requirina immedia_t_e_ac_ tion to place the reactor in a conditipn wb_ere the specification does not_ app _lyg 1
3/0.' ?
r"OC" SUPPDSSEORS (ENUSSEns;
)
1 l
l ARKANSAS - UNIT 2 B 3/4 7-5 Amendment No. 4G,449 l
Revised by letter dated 9/9/95 l
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b 3/4.7.8 SHOCK SUPPRESSOBSJ SNUERERS1 e
All snubbers are recuired_ OPERABLE to ensure that the structural intearity of the reactor coolant _sysle_m and all other_ safely-related sysiems.
{
s 1s maintained during_ add _foJJowing_a_ seismic or other event initiating j
gypamic loads.
Snubbers excluded _ffsm this inspeJtion orggram are those installed on nonsafely-Iglaled systems and then only if_their_faRure or i
f311ure of_the system on whjch_they_are_ installed would have no adverse
. gfect on any safety-related syste_mt
-t The visual inspection fre_guency_is_ bas.ed_upon maintainina a constant level of_ snubber proteglion_to__ systems. getre_foles the_requjged inspection l
i.
Anteryal varies based upon the number of INOPERABLE snubbers found durina the i
p.Levious inspeptioD_in_ proportion to the sites of the various_ snubber i
ppop gations or categories and the preyious inspection interval _as spegified l
An_NRC Generic Letter 90-09, " Alternative Requirements For Snubber Visual j
IDspection_Intelvjgs and Corrective Actions".
Inspeccions_perfor,med before that_1pterva_1 has elapsed may_be used as a new reference _ point to determine
]
I the_pext inspectioq. However; 2he result of such early_ inspections _ performed i
before the__griginal_r,e,guired time interval has elapsed (nominal timg,JeAs_
251L_may_not be used to lenathen the reggired inspection interval. Any inspection whose results_re_ quire a shorter inspection interval will override i
thm_pIevioas schedulet When tep_cause of the reiection of a snubber is clearly established and remedied for_that snubber and for any other snubbers that may be cenericall,y j
susceptible _.,and_velified by inservice functignaL_tes$1ng, that snubbermay_b,e, exempfed from being counted asj npperable.
Generically _ susceptible snubbers are those which are oJ_a spepliic make or model and have the same design features directly related to reiection of_the snubber by visual inspection e.
or_Are similarly_lggat_ed_or__ exposed to the same environmental conditions such I
,a s_t_emnega t ule, radiation and vibratigni When_a_ snubber is found inoperable, an enaineering evalua3JpyL_is performed, in additipp_tp_the determination of Abe snubber mode of f ailuret in_oJ. der to det. ermine if any_ safety gelated component or system has been AdveJsely_aff ecte_d_bv the_inoperability of the snubber. The engineering i
evaluation is nerfgimed to determine whether or_not the snubber mod _e of j
failure-has_ imparted a signi.11 cant effect or degradation on_the supppg ej
. component or syplem e If a review and evaluation of an INOPERABLE snubber is performed ancj e
documented to_ jus 11_fy_gontinueA operation and provided that all_desigg critella_are met with the IMOPERABLE_ snubber;__then the IMORMBLE snubber would not need to be restored or replaced c
4 To provide further assurance of snubber reliability, a representa-tive sample of the installed snubbers will be functionally tested during plant shutdowns at 18 month intervals.
These tests will include stroking of the snubbers to verify proper piston movement, lock-up and bleed. Observed failures of these sample snubbers will require functional testing of additional units.
To minimize personnel exposures, snubbers installed in areas which have high radiation fields during shutdown or in especially difficult to remove locations may be exempted from these j
functional testing requirements provided the OPERABILITY of these snubbers was demonstrated during functional testing at either the completion cf
}
their fabrication or at a subsequent date.
3 / ' '. 9 S E" LEO SOURCE CO"T?."MATMN 4
ARKANSAS - UNIT 2 B 3/4 7-6 Amendment No. M 3
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The Mm6 tot-senc cn :cm,vcbic eerramin'ath:: fc: cureco cquiring W. ting, including ci>hc-cmitt-6 r-based - l e C F" "' ^. 394et t
pgg _ _ _,... _ _ 4.. _
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ARKANSAS - UNIT 2 B 3/4 '7-6 Amendment No. -142 l
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PLANT SYSTEMS BASES
,3L42 9 SEALED SOURCE CONTAMINATION
__The_ljJni.tations on removabl_e,qontamination for sources requiring leak testina, including _aJyha emlt_ters, is based on 10 CFR 70.39Lcl_
limits for plu_tonium.
Th_is_1_imi_t;ation will ensure tilat_ leakage f rom gyproducL_ source,_and_special nuclear material sources will not exceed allowable intake values.
3/4.7.10 FIRE _.St!PPRESSION SYSTEMS, DELETED 3/4.7.11 FIRE BARRIERS DELETED 3/4.7.12 SPENT FUEL POOL STRUCTURAL INTEGRITY The reinforcing steel in the walls of the spent fuel pool was i
erroneously terminated into the front face instead of the rear face of the adjoining walls during construction of the spent fuel pool.
Therefore, l
the specified structural integrity inspections of the spent fuel pool are l
required to be performed to ensure that the pool remains safe for use and that it will adequately resist the imposed loadings.
If no abnormal degradation is observed during the first five inspections, the inspection interval fer subsequent routine inspections may be extended to at least once per 18 months or longer if justified by observed performance of the pool.
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ARKANSAS - UNIT 2 B 3/4 7-7 Amendment No. 99,4-34