ML20236Y595
| ML20236Y595 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 08/06/1998 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20236Y593 | List: |
| References | |
| NUDOCS 9808120333 | |
| Download: ML20236Y595 (56) | |
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i PROPOSED TECHNICAL SPECIFICATION CHANGES i -
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TABLE OF CONTENTS SECTION TITLE PAGE
- 1. DEFINITIONS 1 1.1 RATED POWER 1 1.2 REACTOR OPERATING CONDITION 1 1.3 OPERABLE 2 1.4 PROTECTION INSTRUMENTATION LOGIC 2 1.5 INSTRUMENTATION SURVEILLANCE 3 1.6 POWER DISTRIBUTION 4 1.7 REACTOR BUILDING 5 1.8 FIRE SUPPRESSION WATER SYSTEM S 1.9 STAGGERED TEST BASIS 5 1.10 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS Sa (RETS) DEFINITIONS 1.11 CORE OPERATING LIMITS REPORT 6
- 2. SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 7 2.1 SAFETY LIMITS REACTOR CORE 7 2.2 SAFETY LIMITS, REACTOR SYSTEM PRESSURE 10 2.3 LIMITING SAFETY SYSTEM SETTINGS, PROTECTIVE INSTRUMENTATION 11
- 3. LIMITING CONDITIONS FOR OPERATION 16 3.1 REACTOR COOLANT SYSTEM 16 3.1.1 Operational components 16 3.1.2 Pressurization, Heatup and Cooldown Limitations 18 3.1.3 Minimum conditions for criticality 21 3.1.4 Reactor Coolant System Activity 23
, 3.1.5 Chendstry 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 SYSTDfS 34 3.3 EMERGENCY CORE COOLING, REACTOR BUILDING COOLING, 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 3.7 AUXILIARY ELECTRICAL SYSTEMS 56 3.8 FUEL LOADING AND REFUELING 58 3.9 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING SYSTEM 60 3.10 SECONDARY SYSTEM ACTIVITY 66 3.11 EMERGENCY COOLING POND 66a 3.12 MISCELLANEOUS RADIOACTIVE MATERIALS SOURCES 66b 3.13 PENETRATION ROOM VENTILATION SYSTEM 66c I
(
Amendment No. M,88,M9 i l
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. l SECTION TITLE PAGE 3.14 HYDROGEN RECOMBINERS 66e $
3.15 FUEL HANDLING AREA VENTILATION SYSTEM 66g 3.16 SHOCK SUPPHESSORS (SNUBBERS) 661 ,
3.17 FIRE SUPPRESSION WATER SYSTEM 66m 3.18 FIRE SUPPRESSION SPRINKLER SYSTEMS 66n 3.19 CONTROL ROOM AND AUXILIARY CONTROL ROOM HALON SYSTEMS 66o 3.20 FIRE HOSE STATIONS 66p ;
3,21 -FIRE BARRIERS 66q ;
3.22 REACTOR BUILDING PURGE FILTRATION SYSTEM 66r 3.23 REACTOR BUILDING PURGE VALVES 66t 3.24 EXPLOSIVE GAS MIXTURE 66u 3.25 l RADIOACTIVE EFFLUENTS 66v 4 3.25.1 Radioactive Liquid Effluents 66v 3.25.1.1 Concentration 66v 3.25.1.2 Dose 66w 3.25.1.3 Waste Treatment 66x 3.25.1.4 Liquid Holdup Tanks 66y 3.25.2 Radioactive Gaseous Effluents 66z 3.25.2.1 Dose Rate 66z 3.25.2.2 Dose - Noble Gases 66aa j 3.25.2.3 Dose - Iodine-131, Tritium, and Radionuclides '
in Particulate Form 66bb j 3.25.2.4 Gaseous Radwaste Treatment 66cc i 3.25.2.5 Gas Storage Tanke 66dd 3.25.3 Total Dose 66ee 3.25.4 Solid Radioactive Waste 66ff
- 4. SURVEILLANCE REQUIREMENTS 67 4.1 OPERATIONAL SAFETY ITEMS 67 4.2 REACTOR COOLANT SYSTEM SURVEILLANCE 76 4.3 TESTING FOLLOWING OPENING OF SYSTEM 78 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 BUILDING COOLING SYSTEM PERIODIC TESTING 92 4.5.1 Emergency Core Cooling Systems 92 4.5.2 Reactor Building Cooling Systems 95 4.6 AUXILIARY ELECTRICAL SYSTEM TESTS 100 4.7 REACTOR CONTROL ROD SYSTEM TESTS 102 l 1
4.7.1 Control Rod Drive System Functional Tests 102 1 4.7.2 Control Rod Program Verification 104 4.8 EMERGENCY FEEDWATER PUMP TESTING 105 4.9 REACTIVITY ANOMALIES 106 4.10 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING SYSTEM SURVEILLANCE 107 4.11 PENETRATION ROOM VENTILATION SYSTEM SURVEILLANCE 109 4.12 HYDROGEN RECOMBINERS SURVEILLANCE 109b i 4.13 EMERGENCY COOLING POND 110a 4.14 RADIOACTIVE MATERIALS SOURCES SURVEILLANCE 110b 4.15 AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH l ENERGY LINES OUTSIDE OF CONTAINMENT 110e l I
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Amendment No. M,34,M,44,44,M,M, 11 l M ,44, M ,M , M B,-1 M l
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l 3.5.1.13 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.
3.5.1.14 The Main Steam Line Radiation Monitoring Instrumentation shall l be operable with a minimum measurement range from 10-1 to
! 104 mR/hr, whenever the reactor is above the cold shutdown condition.
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- 3.5.1.15 Initiate functions of the EFIC system which are bypassed at cold shutdown conditions shall have the following minimum operability 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.
3.5.1.16 The automatic' steam generator isolation system within EFIC shall be operable when main steam pressure is greater than 750 psig.
Amendment No. M&,MO,M3,F;L7,ME 42b
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-The principal function of the Control Room Isolation-High Radiation is to provida 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 high radiation signal- from the ANO-1 control room ventilation intake duct monitor j and the redundant channel receives a high radiation signal from the ANO-2 control I-room vetatilation intake duct 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 i may continue indefinitely in this state.
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:
- 1. all four RC pumps are tripped
- 2. both main feedwater pumps are tripped
- 3. the level of either steam generator is low
- 4. either steam generator pressure is low
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:
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-between the two SG's exceeds 100 psig, supply EFW only to the SG
- with the higher pressure.
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 ,
will be automatically reset at the values or plant conditions identified in l Specification 3.5.l.15. . " Loss of 4 RC pumps" initiate and " low steam generator l pressure" initiate are the only shutdown bypasses to be manually ;
initiated during cooldown. If. reset is not done manually, they will l t automatically reset. Main feedwater pump trip bypass is automatically l
removed above 10% power.
REFERENCE l
'FSAR, Section 7.1
-Amendment No. M 4,&74,M 3 '43e
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3.8.15 Storage in tha spant fuel pool shall be restricted to fual assemblics 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 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 million.
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 sufficient. This permits maintenance on the instrumentation. Continuous monitoring of radiation levels and neutron flux provides immediate indication of an unsafe condition. l 1
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 l and maintain the water in the reactor pressure vessel at the refueling temperature (no rmally 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. ( * )
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 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 l suberitical, even with all control rods withdrawn from the core. (8) Although the refueling boron concentration is sufficient to maintain the core keff 5 0.99 if all the control rods were removed from the core, only a few control rods will t be removed at any one time during fuel shuffling and r Amendment No. M, M,M,M,4M,MG, 59a l 441,+44 l
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- 3. 9. ' ' CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING SYSTEMS l App 11cability Applies to the. operability of the control room emergency ventilation and air conditioning systems.
Objectly To ensure that the control room emergency ventilation and air conditioning 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 during handling of irradiated fuel.
3.9.1.2 ~ With one train of control room emergency air conditioning inoperable, restore the inoperable train to Operable status 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 Energency 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 train of control room emergency ventilation inoperable, restore the inoperable train 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 />. j l
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- i Amendment No. M ,M 60 l
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Bassa The control room emergency ventilation and air conditioning system is designed to isolate the combined control rooms to ensure that the control rooms 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 allowable temperature for continuous duty rating for the equipment and 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, 10 CFR 50.
Unit 1 and Unit 2 control rooms are a single environment for emergency ventilation and air conditioning concerns. Since the control room emergency ventilation and air conditioning equipment is shared between units, the plant status of both units must be considered when determining applicability of the specification.
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. 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 and fan trains, two independent actuation channels and the Control Room isolation
- dampers. The control room dampers isolate the control room within 10 seconds l 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 isolatin; 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 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.
i With both trains of the control room emergency ventilation and/or emergency air l 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.
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Amendment No. 44,4G 61 (next page is 66)
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4.10 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING SYSTEM l SURVEILLANCE
' 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 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 sB4*F D.B. {
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- b. At least once per 18 months by verifying a system flow rate of 9900 cfm 110%. j l
4.10.2 Each train of control room emergency ventilation shall be demonstrated l Operable: !
.a. - At least once per 31 days on a Staggered Test Basis by initiating, from the control Room,. flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes.
- b. At least once per 18 months or 1)after any structural maintenance on the HEPA filter or charcoal adsorber housings, or 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 110%. l
- 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 of
- 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 N510-1C75.
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j Amendment No. 44,G6,4G 107
- c. After svary 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorbar oparation by varifying j 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:
- 1. s 2.5% for 2 inch charcoal adsorber beds, or I I
- 2. s 0.5% 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 i 10%.
- 2. Verifying that on a control Room ventilation 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.
- e. After each complete or partial replacement of the HEPA filter bank by verifying that the HEPA filter banks remove 2 99.95% 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 i 10%.
- f. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove 2 99.95% 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 i 10%.
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 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.
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Bases (Continusd) l The frequency of tests and sample analysis are necessary to show that the HEPA filters and charcoal adsorbers can perform as evaluated. The charcoal adsorber efficiency test procedures should allow for obtaining at least two samples. Each sample should be at least two inches in diameter and a length equal to the thickness of the bed. Tests of the charcoal adsorbers with DOP aerosol shall be performed in accordance with ANSI N510 (1975)
" 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 isolation 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, chemjcals or foreign material, the same tests and rample analysis shall be performed as required.for operational use. The determir.ation of significant shall be made by the operator on duty at the time of the incident. Knowledgeable staff members should be consulted prior to making this determir.ation.
Amendmer.t No. 10Ba l
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SECTION PAGE 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE j 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 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING SYSTEM................................... 3/4 7-17 3/4.7.8 SHOCK SUPPRESSORS (SNUBBERS)............................ 3/4 7-22 j 3/4.7.9 SEALED SOURCE CONTAMINATION............................. 3/4 7-27 3/4.7.10 FIRE SUPPRESION SYSTEMS Fire Suppression Water System........................... 3/4 7-29 i 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 l
3/4.7.12 SPENT FUEL POOL STRUCTURAL INTEGRITY.................... 3/4 7-38 i
3/4.8 ELECTRICAL POWER SYSTEMS l i
3/4.8.1 A.C. SOURCES !
Operating............................................... 3/4 8-1 j Shutdown............................................... 3/4 8-5 l l
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ARKANSAS - UNIT 2 VIII Amendment No. M,M,G,M
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INDEX
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-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 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 7-1,
'3/4.7.8 SHOCK SUPPRESSORS-(SNUBBERS)............................ B'3/4 7-6 3/4.7.9 SEALED SOURCE CONTAMINATION............................. B 3/4 7-7 3/4'.7.10 FIRE SUPPRESSION SYSTEMS................................ B 3/4 7-7 ,
I 3/4.7.11 PENETRATION FIRE BARRIERS................................ B 3/4 7-7 l l
3/4.7.12 . SPENT FUEL POOL STRUCTURAL INTEGRITY.................... B 3/4 7 3/4.8 ELECTRICAL FOWER' SYSTEMS...........................~....... . B 3/4 8-1
'3/4.9 REFUELING OPERATIONS 3/4.9.1 BORON CONCENTRATION...................................... B 3/4 9-1 3/4.9.2 INSTRUMENTATION......................................... B 3/4 9-1 3/4.9'.3 DECAY TIME.............................................. B 3/4 9-1 3/4.9.4 CONTAINMENT PENETRATIONS................................ B 3/4 9-1 l
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l ARKANSAS - UNIT'2. XIII Amendment No. 49,4G 1
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TABLE 3.3-6 (Continued)
TABLE NOTATION j 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 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 l the Minimum Channels OPERABLE requirement, comply with the !
ACTION requirements of Specification 3.4.6.1. 4 ACTION 16 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, complete the followiag:
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- 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 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 j operation of the control room emergency ventilation system in j the recirculation mode of operation. l I
ACTION 18 - With the number of channels OPERABLE one less than required l by the Minimum Channels OPERABLE requirement, (1) either j restore the inoperable channel to OPERABLE status within 7 j 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 i of the inoperability, and the plans and schedule for l restoring the system to OPERABLE status. With both channels inoperable, initiate alternate methods of monitoring the containment radiation level within 72 houra in addition to the actions described above. l l
ACTION 19 - With the number of OPERABLE Channels less than required by I the Minimum Channels OPERABLE requirements, initiate the l preplanned alternate method of monitoring the appropriate l 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 Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the l inoperability and the plans and schedule for restoring I the system to OPERABLE status.
ACTION 20 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, 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 the control room emergency ventilation system in the recirculation mode of operation.
ARKANSAS - UNIT 2 3/4 3-26 Amendment No. 63,-MO,+M l
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i PLANT SYSTEMS 1e j 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING SYSTEM l l
LIMITING CONDITION FOR OPERATION I l
3.7.6.1 Two independent control room emergency ventilation and air conditioning systems shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, 4, and during handling of irradiated fuel. l ACTION:
- a. With one control room emergency air conditioning system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <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 />.
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- b. With one control room emergency ventilation 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 />.
- c. With one control room emergency air conditioning system and one control room emergency ventilation system inoperable, restore the inoperable control room emergency ventilation system to OPERABLE status within 7 days and restore the inoperable control room emergency air conditioning 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 />.
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 STAGGERED TEST BASIS 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 demonstrated OPERABLE:
- a. At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes.
- b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communicating with the system by:
l ARKANSAS - UNIT 2 3/4 7-17 Amendment No. ;
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l SURVEILLANCE REQUIREMENTS (Continued) l l 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.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 2000 cfm i 10%.
- 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 of:
- a. s 2.5% for 2 inch charcoal adsorber beds, or
- b. s 0.5% for 4 inch charcoal adsorber beds.
- 3. Verifying a system flow rate of 2000 cfm i 10% 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 ASTM D3803-1989 when tested at 30*C and 95% relative humidity for a methyl iodide penetration of:
- 1. s 2.5% for 2 inch charcoal adsorber beds, or
- 2. s 0.5% for 4 inch charcoal adsorber beds.
- d. At least once per 18 months by:
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- 1. Verifying that the pressure drop across the combined HEPA I filters and charcoal adsorber banks is < 6 inches Water Gauge while operating the system at a flow rate of 2000 cfm ,
i 10%.
- 2. Verifying that on a control room high radiation test signal, the j system automatically isolates the control room within 10 seconds j 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 2 99.95% of the DOP l when they are tested in-place in accordance with ANSI N510-1975 i
, while operating the system at a flow rate of 2000 cfm i 10%.
l ARKANSAS - UNIT 2 3/4 7-18 Amendment No. 494,
3/4.3 INSTRUMENTATION BASES 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensure 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 intake duct monitors 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 high radiation signal from the ANO-1 control room ventilation intake duct monitor and the redundant channel receives a high radiation signal from the ANO-2 control room ventilation intake duct monitor. With neither 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.
3/4.3.3.2 DELETED 3/4.3.3.3 DELETED 3/4.3.3.4 DELETED 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.
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ARKANSAS - UNIT 2 B 3/4 3-2 Amendment No. M,-H4,MO,MG,M4 l
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( PLANT SYSTCMS
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1 BASES '
i 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING SYSTEM l The OPERABILITY of the control room emergency ventilation and air 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 l 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 whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criteria 19 of Appendix "A", 10 CFR 50.
Unit 1 and Unit 2 control rooms are a single environment for emergency i ventilation and air conditioning concerns. Since the control room emergency ventilation and air conditioning equipment is shared between units, the plant status of both units must be considered when determining applicability of the specification.
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. 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 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 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 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 condensir.g 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 has been lost, requiring immediate action to place the reactor in a condition where the specification does not apply.
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I ARKANSAS - UNIT 2 B 3/4 7-5 Amendment No. 43,439 n:vi::d by lett : d:t:d 9/S/05
PLANT SYSTEMS BASES 3/4.7.8 SHOCK SUPPRESSORS ( SNUBBERS )
All snubbers are require.d OPERABLE to ensure that the structural integrity of the reactor' coolant system and all other safety-related systens 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 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 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
.2 5 % ) 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 I
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 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.
I ARKANSAS - UNIT 2 B 3/4 7-6 Amendment No. 143 i
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l PLAMT 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) limits 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 DELETED 3/4.7.11 FIRE BARRIERS DELETED 3/4.7.12 SPE! 't 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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I ARKANSAS - UNIT 2 B 3/4 7-7 Amendment No. 49,M3 l
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1 MARKUP OF CURRENT ANO-1 TECHNICAL SPECIFICATIONS i l
(FORINFO ONLY) .
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TABLE OF CONTENTS TITLE PAGE
..'SECTION
- 1. DEFINITIONS 1
1.1 RATED POWER 1 1.2 REACTOR OPERATING CONDITION 1 1.3 OPERABLE 2 1.4 PROTECTION INSTRUMENTATION LOGIC 2 1.5 INSTRUMENTATION SURVEILLANCE 3 1.6 POWER DISTRIBUTION 4 l
i 1.7 REACTOR BUILDING 5
1.8 FIRE SUPPRESSION WATER SYSTEM 5 1.9 STAGGERED TEST BASIS 5 1.10 RADIOLOGICAL EFFLUENT TECHNICAL SPECIFICATIONS Sa (RETS) DEFINITIONS 1.11 CORE OPERATING LIMITS REPORT 6
-2. SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 7 2.1 SAFETY LIMITS REACTOR CORE 7 l 2.2 SAFETY LIMITS, hEACTOR SYSTEM PRESSURE 10 2.3 LIMITING SAFETY SYSTEM SETTINGS, PROTECTIVE INSTRUMENTATION 11
, 3. LIMITING CONDITIONS FOR OPERATION 16 3.1 REACTOR COOLANT SYSTEM 16 3.1.1 Operational components 16 t 3.1.2 Pressurization, Heatup and Cooldown Limitations
' 18 3.1.3 Minimum conditions for criticality 21 3.1.4 Reactor Coolant System Activity 23 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 l
3.2 MAKEUP AND CHEMICAL ADDITION SYSTEMS 34 3.3 EMERGENCY CORE COOLING, REACTOR BUILDING COOLING, AND REACTOR BUILDING SPRAY SYSTEMS 36 l -3. 4 STEAM AND POWER CONVERSION SYSTEM 40 3.5 INSTRUMENTATION SYSTEMS 42 t- 3.5.1 Operational Safety Instrumentation 42 3.5.2 Control Rod Group and Power Distribution Limits 46
- 3. 5c. 3 Safety Features Actuation System Setpoints 49
- 3. 5'. 4 Incore Instrumentation 51 1
'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
! 3.9 CONTROL ROOM EMERGENCY VENTILATION AND AIR l
CONDITIONING AN9 HMANON-SYSTEM 60 i
3.10 SECONDARY SYSTEM ACTIVITY 66 3.11 EMERGENCY COOLING POND 66a 3.12 MISCELLANEOUS RADIOACTIVE MATERIALS SOURCES 66b
-3.13- PENETRATION ROOM VENTILATION SYSTEM 66c l
- Amendment No. M,M,MG i l-
- -- SECTION TITLE PAGE 3.14 HYDROGEN RECOMBINERS 66a I 3.15 FUEL HANDLING AREA VENTILATION SYSTEM 66g 3.16 SHOCK SUPPRESSORS (SNUBBERS)
' 661
.3.17 G RE SUPPRESSION WATER SYSTEM 66m 3.18 FIRE SUPPRESSION SPRINKLER SYSTEMS 66n 3.19 CONTROL ROOM AND AUXILIARY CONTROL ROOM HALON l SYSTEMS 66o l
3.20 FIRE HOSE STATIONS 66p
.3.21- FIRE BARRIERS 66q 3.22 REACTOR BUILDING PURGE FILTRATION SYSTEM 66r
! 3.23 REACTOR BUILDING PURGE VALVES 66t
( '3.24 EXPLOSIVE GAS MIXTURE 66u 3.25 RADIOACTIVE EFFLUENTS 66v L3.25.1 Radioactive Liquid Effluents 66v 3.25.1.1 Concentration 66v l 3.25.1.2 Dose 66w 3.25.1.3 Waste Treatment 66x
, 3.25.1.4 Liquid Holdup Tanks 66y i 3.25.2 Radioactive Gaseous Effluents 66z 3.25.2.1 Dose Rate 662
! '3.25.2.2- Dose - Noble Gases- 66aa 3.25.2.3 Dose - Iodine-131, Tritium, and Radionuclides in' Particulate Form 66bb t
3.25.2.4 Gaseous Radwaste Treatment 66cc
-3.25.2.5 l Gas Storage Tanks 66dd
'3.25.3' Total Dose 66ee.
! 3.25.4 Solid Radioactive Waste 66ff
- 4. -SURVEILLANCE REQUIREMENTS 67 4.1 -OPERATIONAL SAFETY ITEMS 67 4.2 REACTOR COOLANT SYSTEM SURVEILLANCE .76 4.3 TESTING FOLLOWING OPENING OF SYSTEM 78 4.4 REACTOR BUILDING 79 4.4.1 Reactor Building Leakage Tests 79
, 4.4.2 Structural Integrity 85 l 4.5- EMERGENCY CORE COOLING SYSTEM AND REACTOR BUILDING COOLING SYSTEM PERIODIC TESTING 92~
l 4.5.1 Emergency' Core Cooling Systems 92 4.5.2 Reactor Building Cooling Systems 95 4.6 AUXILIARY ELECTRICAL SYSTEM TESTS 100 4.7' REACTOR CONTROL ROD SYSTEM TESTS 102 l
4 . 7.1'- Control Rod Drive System Functional Tests 102 i :4.7.2 Control Rod Program Verification 104 l ,4.8- EMERGENCY FEEDWATER PUMP TESTING 105 4.9 REACTIVITY ANOMALIES 106 4.10 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING,,-AND M M A9MN-SYSTEM SURVEILLANCE 107 i .4.11 PENETRATION ROOM VENTILATION SYSTEM SURVEILLANCE 109 4.12 HYDROGEN RECOMBINERS SURVEILLANCE 109b
'4.13 EMERGENCY COOLING POND 110a 4.14 RhDICACTIVE MATERIALS SOURCES SURVEILLANCE 110b
! ' 4.15 - AUGMENTED INSERVICE INSPECTION PROGRAM FOR HIGH l
h ENERGY LINES OUTSIDE OF CONTAINMENT 110c I
l Amendment No. M,M,M,M,M, M,M, 11 l M , M , M , M ; M e,4 M -
= - - - _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - - - _ _ _ _ _ _ _
3.5.1.13 Two control room ventilation radiation monitorina channels shall be operable whenever the reactor coolant system is above the cold shutdown condition or durina handlina of irradiated fuel.
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.
l I
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Amendment No. M6,MO,M3,4W,4M 42b I
L_____________
i The pri.ncipal_ function of the Control Room Isolation-Hiah Radiation is to providn an enclosed environm'nt from which th= unit can ba op, rated followina an !
- uncontrolled release of radioactivity. Due to the uniaue arrangement of the !
shared control room envelope, one control room isolation channel receives a j hjgh r_adiation sianal from the ANO-1 control room ventilation intake duct monitor l and_the_ redundant channel receives a hiah radiation sianal from the ANO-2 control j ronm_ypntilation intake duct monitor. With no channel of the control room i radiation monitorina system operable, the CREVS must be placed in a condition l that does not recuire the isolation to occur (i.e., one operable train of CREVS is placed in the emeroency recirculation mode of operation). Reactor operation may continue indefinitely in this state.
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:
- 1. all four RC pumps are tripped
- 2. both main feedwater pumps are tripped
- 3. the level of either steam generator is low
- 4. either steam generator pressure is low
The EFIC system is also designed to isolate the affected steam generator on a j steam line/feedwater line break and supply EFW to the intact generator according l to the following logic: l 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 between the two SG's exceeds 100 psig, supply EEW only to the SG with the higher pressure.
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 will be automatically reset at the values or plant conditions identified in Speci fication 3. 5.1.15. " Loss of 4 RC pumps" initiate and " low steam generator ,
pressure" initiate are the only shutdown bypasses to be manually l
initiated during cooldown. If reset is not done manually, they will ;
automatically reset. Main feedwater pump trip bypass is automatically j removed above 10% power. 1 REFERENCE FSAR, Section 7.1 FSAR, Section 2.7.6 Amendment No. 4M,4-7-7,4M 43c i
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-@eving initici cnrichment less th:n or squal to 4.1 w/o U-235. The provisions of Spacifiestion 3.0.3 are not applicable. , l I
3.8.16 Storaga in Ragion 2 (es shown on Figure 3.8.1) of the spant fusi pool l shall be further restricted by burnup and enrichment limits specified in Figure 3.8.2. In the event a checkerboard storage configuration is deemed necessary for a portion of Region 2, vacant spaces adjacent to ~
y the faces of any fuel assembly which does not meet the Region 2 burnup l criteria (non-restricted) shall be physically blocked before any such l- 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.
]
i'
-3.8.17 The boron concentration in the spent fuel pool shall be maintained (at l all times) at greater than 1600 parts per million.
3.8.18 Durina the handline of irradiated fuel, the control room ameroenev air condntionina syster,. and the control room emeroency ventilation system shalt be operable as reauired by Specification 3.9.
Bases Detailed written procedures will be available-for use by refueling personnel.
[
I 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 l and safety. If no change is being made in core geometry, one flux monitor is j sufficient. This permits maintenance on the instrumentation. Continuous monitoring of radiation levels and neutron flux provides immediate indication of an unsafe condition.
The requirement that at.least one decay heat removal loop be in operation l ensures that (1) sufficient cooling capacity is available to remove decay heat 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 L incident and prevent boron stratification. (*)
- 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 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 Eis 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 Amendment No. M,H,M,44,4M,MS, 59a 444,444 .
o
l 3.9 CONTRO2. ROOM EMERGENCY VENTI 2.ATION AND AIR CONDITIONING ?.t !!tU.TIO" SYSTEM 8 j
!. Applicability Applies to the operability of the control room emergency ventilation and air conditioning nd i::1 ti:n systemg.-
O_biective To ensure that the control room emergency ventilation and air conditioning and toe &eM+n systemg will perform within acceptable levels of efficiency and reliability.
Specification 3.9.1 Control Room Emercenev Air Conditioning System 3.' 9.1.1 Two independent trai ns of the control room amaraency air conditioning system shall be operable whenever the reactor coolant system is above the cold shutdown condition or durina handlina of irradiated fuel.
L 3. 9.1.2 With one train of control room amaraency air cond1<:ionina inonerable, restore the :.nonerable train to Goerabhe status within 30 dava or be ir at least Hot Shutdown withLn the next 6 l
hours and in Cold Shutc own 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 ggntrol Room F==raency Ventilation System
- 3. 9.2.1 Two independent trains of the control room emeroency ventilation system shall be operable whenever the reactor coolant system is above the cold shutdown condition or durina handlana of irradiated fuel.
Amendment No. M,M 60
. . _ _ _ _ _ - - _ - _ _ _ - - _ _ - _ - _ - ._. =_- _ _ _ - - . _ _ . . _ - _ _ _ _ _ _ _ _ _ - _ - _ _ _ - _ _ _ _ _ .
3.9.2.2 With one train of control room emeroency ventilation inocerable, restore the inocerable train to Ooerable 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 followino 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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The control room emercenev' ventilation and air conditioning system is desianed te a isolate the combined control rooms to ensure that the control rooms will r===1n 4 habitable for Operations eersonnel durina and followina ale credible accident conditions and to ensure that t3e ==hient air ta- erature does not exceed the allowable ta-erature for continuous dutv ratina for the eauiement and instrumentation cooled by this system. The desian configuration of the system'is based on 4m tina the radiation exoosure to nersonnel occunvina the control room t to S REM or Less whole bodva or its eauivalent. in accordance with the requirements of General Desian Criteria 19 of Anoendix Am 10 CFR 50.
[
Unit 3 and Unit 2 contrel rooms are a sinale environment for ===raency ventilation and air conc.itionina concerns. Since tre control room emeroency ventilation and air conc.itionina eauinment is sharec. between unitsa the clant-status of both units must be considered when determining anolicability of the specification.
Due to the un4aue situation of the shared amaraency ver tilation and air conditioning eauinmenta the commonents may be cross fet from the onnosite unit ner credetemined contingency actions /orocedures. Unit may take credit for operability of these systems when confiaured to achieve sene. ration and independence reaardless of normal nower and/or service water configuration. This will be in accordance with cre-determined continuenev actions /orocedures, j Amendment No. M,M 61 (next page is 66) j I
[ .
l The control room emercency ventilation system consists of two independent tilter and fan trains, two independent actuation channels and the Control Room isolation damoers. The control room dampers isolate the control room within 10 seconds of l receipt of a hiah radiation sianal. If the actuation sianal can not close the )
control room isolation dampers, 1(olatino the control room by manually closina j the affected control room dampere nrovides the reauired isolation desian function of the Control Room Emercency Ventilation System.
jf the actuation sional can not start the emeraency ventilation recirculation fan, operatina the affected fan in the manual recirculation mode and isolatina the control room isolation dampers provides the reouired desian function of the l i
' control room emeraency ventilation system to isolate the combined control rooms to ensure that the control rooms will remain habitable for operations personnel durina and followine accident conditions. This contingency action should be out ;
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 desian functions of the control room emeraency ventilation system.
The control room emeraency air conditioning system (CREACS) crovides temoa:rature contro:. for the control room followina isolation of the control room. It :.s j manual:,v started from Unit Two Control Room. The CREACS consists of two independent and redundant trains that provide cooline of recirculated control i room air. A coolina coil and a water cooled condensina unit are orovided for l
each system to orovide suitable temperature conditions in the control room for i operatino personnel and safety related control eauipment.
With both trains of the control room emercency ventilation and/or emercency air conditioning inoperabel, the function of the control room emeraency air systems j have been lost, reauirina immediate action to olace the reactor in a condition where the specification does not apply.
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Amendment No. 40,43 61 (next page is 66)
L -_ _ . _. _ _ _ _ _ _ . _ _ _ . _
=-- -
4.10 CONTRCL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING .'2't IOL*. TION SYSTEM SURVEILLANCE Applicability 1 I
I Applies to the surveillance of the control room emergency ventilation and air conditioning : d i::1; tic; systemg.
)
Obiective To verify an acceptable level of efficiency and operability of the control room emergency ventilation and air conditioning ::d i::12 i:: systemg. l
- Specification 4.10.1 Each train of control room ameroenev air conditioning shall be demonstrated Operable:
gaggg least once ner 31 davs on a stacaered test basis bv:
- . g.,Startina each un'it and
- 2. Verifvina 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 t==aerature 184'r D.B.
- b. At least once ner 18 months by verifyina a system flow rate of 9900 eBe i10%.
..t int: c:1 : : :::::i 10 x:;th , th: p;;; ::: d;;p :::::: th;
- 'in:d "C".'. filt :; :sf -t:::;21 xd:::i;; i;;h: cicli i:
"- :::::t:d 0: i 1::: "-- ! inch:: :f ::t:: :: :y:::: d::ig; fi:n (1100) 4.10.2 Each train of control roam ameroency ventilation shall be d--anstrated SESIMASi
- a. At least once ner 31 days on a Stanaered Test Basis by initiatina, from the Control Room, flow throuah the MRPA filters and charcoal adsorbers and verifyina that the system onerates for at least 15 h
- b. At least once ner 18 months or 11after any structural mainminance on the MRPA filter or charconi adsorbem housinas, or 2) foLLowina significant nanntina, fire, or ch==4cah release in any ventilation zone c- micatina with the system bv
- 1. Verifvina that the cleanuo s er2em satisfies the in-clace testina l accentance criteria and uses the test crocedures of Reaulatory l Positions C.S.a. C.S.e. and C.S.d of Reaulatorv Guide 1.52. I Revision 2. Murch 1978, and the system flow rate is 2000 cfm t10%. ,
1
- 2. Verifvina within 31 days after camoval that a laboratory analysis {
of a reeresentatLve carbon s==aie obtained in accordance with i Reculatory PositLon C.6.b of Reaulatorv Guide 1.52. Revision 2.
March 1978, meets the laboratory testina c riteria of ASTM !
D3803-1989 then tested at 30*C and 95% relative hu=4 ditv for a methyl iodice penetration oft
- a. s2.5% for 2 inch charcoal a/sorber beds, or b,
so.5% for 4 inch charcoal adsorber beds.
- 3. Verifvino a system flow rate of 2000 c6m *10% durina system operation when tested in accordance with ANSI N510-1975.
Amendment No. 49,G6,43 107 '
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1 Amendment No. M,M,M 107
Af ter everv 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber ooeration by verifvina
~
c.
1 within 31 davs after removal t sat a laboratory analvsns of a reeresentatiwe carbon sample obtained in accordance wnth RQGulatorv Position C.6.b of Reaulatorv Guide 3.52, Revision 2, March 1978, meets the laboratory testina criterna of ASTM D3803-1989 when tested at 30'C and 95% relative humidity for a methyl iodide penetration of:
l
- 1. s 2.5% for 2 inch charcoal adsorber beds, or
~
l 2. s 0.5% for 4 inch charcoal adsorber beds,
- d. At least once oer 18 months by:
l
- 1. Verifvina that the cressure dron across the combined HEPA l
fi.ters and charcoal adsorber banks is < 6 inches of water while coeratina at a flowrate of 2000 cfm
- 10%.
i
- 2. Verifvina that on a control Room ventilation hiah radiation test sienmL, the system automatically isolates t ie Control Room within 10 seconds and switches -.nto a reciret.lation mode of operati'an with flow throuah the MR 'A filters anc. charcoal adsorber ban cs.
e.' After each ca==lete or oartial reolac== ant of the HEPA filter bank by verifvina that ti e MEPA filter banka remove 2 99.95% of the )OP when thev are testec. in-clace in accordance with ANSI N510-1975 while oneratina the -system at a flow rate of 2000 e6m f 10%.
- f. After each ca-alete or cartial reolac-- nt of a charcoal adsorber
- 3ank by verifvina that the charcoal adsorbers remove 199.95% of a salocenated hydrocarbon refrigerant test aas when they are tested in-olace in accordance with ANSI N510-1975 while operatina the system at a flow rate of 2000 cem
- 10%.,
Bases The purpose of the control room 4444ecieng emeraency ventilation system is to l Itmit the 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 profilter, high efficiency particulate filters, charcoal adsorbers and a fan.
Since the eye 4em is not normally operated, a l periodic test is required to insure operability when needed. During this test the system will be inspected for such things as water e oil, or other foreign materials gasket deterioration, adhesive deterioration in the HEPA units; and j unusual or excessive noise or vibration when the fan motor is running. Pressure i drop across the combined HEPA filters and charcoal adsorbers of less than 6 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 I
' should be determined at least once per operating cycle to show system performance ,
capability. '
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Btena (Continusd)-
The'frecuenev of tests and s==nle analysis are necessary to show that the HEPA filters and charcoal adsorbers can nerform as evaluated. The charcoal adsorber efficienev test orocedures shouli allow for obtainina at least two s==nles. Each s==nle should be at least two inches in diameter and a lenath eaual to the thickness of the bed. Tests of the charcoal adsorbers with DOP aerosol shall be nerformed in accordance with ANSI N510 (1975)
" Standard for Testina of Nuclear Air Cleanine Systems." Anv HEPA filters found defective shall be reolaced with filters cualified accordina to Raoulatorv Position C.3.d of Reaulatorv Guide 1.52. If laboratory test results are unacceptable, all charcoal adsorbents in the system shall be reolaced with charcoal adsorbent aualified accordina to Reaulatory Guide 1.52.
The operability of the Control Room Emeraency Air Conditioning Systems ensure that the ==hiant air t==nerature does not exceed the allowable t==nerature for the eauinment and instrn==ntation cooled by this system and the Control Room will r===in habitable for Onerations norsonnel durina and followine all credible accident conditions.
Oneration of the syst=== for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> every month will d===nstrate venerability of the eneraency ventilation and -- raency air conditioning syst===. All d==ners and other mechani cal and isolation avsta== will be shown to be onerable.
If significant naintina, fire or ch==4 cal release occurs such that the MEPA filter or charcoal adsorber could become con ==inated e from the fumes, ch==icals or foreian material, the s=== tests and s== ale analysis shall be nerformed as reauired for operational use. The determination of significant shall be made by the enerator on duty at the time of the incident. Knowledgeable staff ===hers should be consulted nrior to makina l' this determination.
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Amendment No. 108a
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MARKUP OF CURRENT ANO-2 TECHNICAL SPECIFICATIONS l
(FORINFO ONLY)
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INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE
.s 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 'l-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
~ 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING N
" L"T.'."' ! '"' S Y S T EM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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 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 l
(
3/4.8.1 A.C. SOURCES l
{
Operating............................................... 3/4 8-1 Shutdown............................................... 3/4 8-5 l
l ARKANSAS - UNIT 2 VIII Amendment No. 40,M ,G ,99
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INDEX BASES I
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 1
l 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.h FLOOD PROTECTION........................................
B 3/4 7-4 3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING /.".!P T!LTP.'.
TI^.S SYSTEM.........................................'..
B 3/4 7-4) 3/4.7.8 SHOCK SUPPRESSORS (SNUBBERS)............................ B 3/4 7-6-j l 1
J 3/4.7.9 SEALED SOURCE CONTAMINATION............................. B 3/4 7-42 l
]
3/4.7.10 ifIRE SUPPRESSION SYSTEMS................................
B 3/4 7-42 l 3/4.7.11 PENETRATION FIRE BARP.IERS............................... B 3/4 7-7 i
3/4.7.12 SPENT FUEL POOL STRUCTURAL INTEGRITY.................... B 3/4 7-7 {
3/4.8 ELECTRICAL POWER SYSTEMS................................... B 3/4 6-1 j 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 l l
3/4.9.4 CONTAINMENT PENETRATIONS................................ B 3/4 9 ~. I l
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TABLE 3.3-6 (Continued)
TABLE NOTATION ACTION With the number of channels OPERABLE less than required by L
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 />, l
ACTION 14 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the
{
t ACTION requirements of Specification 3.4.6.1.
l '
ACTION 16 - With the number of OPERABLE channels one less than the i
Minimum Channels OPERABLE requirement, complete the l following:
l
- a. If performing CORE ALTERATIONS or moving irradiated fuel l
within the reactor building, secure the containment purge system or suspend CORE ALTERATIONS and movement of i
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 'h: .- - ' : : ;fE2 channels OPERABLE 1::: t' : ::;uir:d b-i th: Mi ' - "h:;;;1: 0"5"?2L :: qui:---.t, within I hour 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 L days or (2) prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days l 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 1 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 /> I
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:
l-
- 1) either restore the inoperable Channel (s) to OPERABLE status within 7 days of the event, or
- 2) prepare and submit m'Special Report to the Commission t
l- pursuant to specification 6.9.2 within 14 days following the event outlining the action taken, the cause of the i inoperability and the plans and schedule for restoring the system to OPERABLE status.
ACTION 20 - With the nn=her of c4mmnels OPERABLE one less than recuired by the Mini =n= Channeis OPE UOLE requirement, restore the inocerable channel to OPERARTE status within ? days, or within the next 6 f
'. ARKANSAS - UNIT 2 3/4 3-26 Amendment No. 4,MG,M6 *
-hours initiate and maintain the control room == reenev ventilation system in the recircu:.ation mode of operation.
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PLANT SYSTEM
3/4.7.6 CONTROL ROOM EMERGENCY VENTILATION *.I"
- COM0!TIONIMC AND AIR CONDITIONING ,
M44WF4GN SY:3 TEM i
! LIMITING CONDITION FOR OPERATION 3.7.6.1 Two. independent control room emergency ventilation:i: ::nditi:ning and
. air conditioninofilt :ti:n systems shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 36 and-4, and durina handline of irradiated f3 el.
l ACTION:
- a. With one control room emeraenev air conditioning system inocerable, restore the inocerable svstam to OPERABLE status within 30 davs or be in at least l HO" 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 foLlowina 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
- l. l j
ks ,,With one control room emergency ventilation:i: :::diti ;in; :: ci:
- 4M+eenen system I !
i 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 />.
j c. With one control room ===raency air condition 4 na system and one corttrol l
room ameroency ventilation avstem inocerable, restore the inocerabhe ;
control room amaraency ventilation svatam to OPERAR" F status within 7 days
! and restore the inocerable control room amaraency aLr conditioning system to OPERABLE status within 30 davs or be in at least :{OT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> anc in COLD SHUTDOWN within the fol..owino 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS l
4.7.6.1.1 Each control room emergency air conditioning system shall be demonstrated OPERABLE:
l l a. At least once per 31 days on a STAGGERED TEST BASIS by.
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 t
maintains the control room air temperature s 84 *r 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 BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates
- for at least 15 minutes.
- b. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any <
ventilation zone communicating with the system by:
l ARKANSAS - UNIT 2 3/4 7-17 Amendment No.
l
- ~ -
PLANT SYSTEMS i l
SURVEILLANCE REQUIREMENTS (Continutd
- 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 l- rate is 2000 cfm i 10%.
, 2. Verifying within 31 days after removal that a laboratory
- l. analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory l
' Guide 1.52, Revision 2, March 1978, meets the laboratory tasting criteria of n:g 1:t::y P;;itic: C.S. ;f n g 1::::y Cuid: 1.52, n:ci;i:n 2, M :;h 1070 ASTM D3803-1989 when tested at 30*C and 95% relative hn=4 dity for a methyl iodide penetration
!- Sia 34_,g 2.5% for 2 inch charcoal adsorber beds, or
, h4_,g 0.5% for 4 inch charcoal adsorber beds.
l- l
- 3. Verifying a system flow rate of 2000 cfm i 10% during system !
operation when tested in accordance with ANSI N510-1975.
l 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 l
' 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 n;g 1:02:7 0::iti:: C.S.: cf n ;;1;t :y C id: 1.52, n:.ici:n 2, M ::t 19?S. ASTM D3803-1989 when tested at 30'C and 95%
relative-hn=4dity for a methyl iodide penetration of:
- 1. s 2.5% for 2 inch charcoal adsorber beds, or i
- 2. t 0.5% for 4 inch charcoal adsorber beds.
- d. At least once per 18 months by:
L 1. Verifying that the pressure drop across the combined HERA filters and charcoal adsorber banks is < 6 inches Water Gauge while operating the system at a flow rate of 2000 chu i 10%.
- 2. Verifying that on a control room high radiation test signa.1, the system automatically isolates the control room within 10 seconds l and switches into a recirculation mode of operation with flow l through the HEPA filters and charcoal adsorber banks.
- e. After each complete or partial replacement of a HEPA filter bank l by verifying that the HEPA filter banks remove 2 99 2}% 4 of the DOE 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 i 10%.
[- ARKANSAS - UNIT 2 3/4 7-18 Amendment No. 4 M ,
I-
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ______1------------_________ _ - - - - _ _ _ _ _ _ _ - - - - - - _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - - - - _ _ _
3/4.3 INSTRUMENTATION BASES e
3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
purge The PURGE permit, as defined in the definitions section is a release under a 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.
i The erancioal function of the' control room intake duct monitors is to nrovide an enclosed env:ron==nt uncontrolled from which the unit can be enerated followina sn meLease of radioactivity.
Due to the untaue arrana===nt of the shared controi room anveione, one control room isolation channel receives a hiah radiation sianal from the ANO-1 control room vent:.lation intake duct monitor and the redundant channel receives a hiah radnation sianal from the ANO-2 control room ventilation intake duct monitor. Nath neither channel of the control room radiation monitorina system onerable. the CRtVS must be olaced in a conditNon train of CR IVS that does not reauire the isolation to occur (: .e.. one operable is olaced in the ===raency recirculation mode of oneration).
Reactor oneration may continue indefinitely in this state.
3/4.3.3.2 DELETED 3/4.3.3.3 DELETED 3/4.3.3.4 DELETED 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 l
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.
l I
ARKANSAS - UNIT 2 B 3/4 3-2 Amendment No. M,4M,4M,M4,M+
- PLANT SYSTEMS I RAGES 3/4.7.6 SYSTEM CONTROL ROOM EMERGENCY VENTILATION AND AIR CONDITIONING _/*.!? l TIL The OPERABILITY of the control room emergency ventilation and air 1 conditioning 4ete. l I
filt::ti:n system ensures that 1) the ambient air temperature does not f;
- exceed the allowable temperature for continuous duty rating for the equipment'and instrumentation cooled by this system and 2) the control room will remain habitable for operations personnel during and 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 whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criteria 19 of Appendix "A", 10 CFR 50.
Unit 1 and Unit 2 contre'l rooms are a sinale environment for emeraency ventilation and anr concitLonina concerns. Since tr.e control room emeroency l
ventilation and anr conc.i tLonina eauia==nt is sharec betu::n units, the olant status of both un' ts must be considered when deter =4 nina annlicability anecification. of the Due to the'uniaue situation of the shared emercenev ver.tilation and air conditioning eauia==nt. the cn=nonents may be cross fec.:! rom the onnosite unit eer predetermined contingency actions /orocac,ures . Unit may take credit for j
operability of these syst=== when confiaurec to achieve senaration and {
j nndeoendence recardless of normal cower and/or service water configuration. '
Uhis will be in accordance with cre- determined contingency actions /orocedures.
The control room emercancy ventilation' system consists of two independent filter j and fan trains. two independent actuation channels ner Unit and the Control Room j
! isolation da=ners. The control roem d==ners isolate the control room within 10 ;
l l
seconds of receint of a hiah radiation sianal.
If the actuation sianal car not start the ===roenev ventilation recirculation fan, oneratina the a:!fectec fan in the emnual recirculation moc e and isolatina the control room isolation d==ners nrovides the reauired desian ftnetion of the control roon emeroency ventilation system to isolate the coeLinee. control rooms to ensure t
! sat the control rooms vill r===in habitable for onerations norsonnel durina and foklowine accident conc.itions. Uhis contingency action should be out in niace 4---diatelv twithin 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) to fuliv satisfy the desian functions of the control room ==araency ventilation system.
The controi control room emerae'nev air conditioning system (CREACS) crovides t==nerature for the control room followine isolation of the control room. It is manualLv started from Unit Two Control Room. The CREACS consists of two independent and redundant trains that crovicle coolina of recirculated control room air. A coolina coil and a water cooiec. cor
! densina unit are crovided for each system to crovide suitable t==aerature conc.itions in the controi room for oneratina nersonnel and safety related control eauinment.
With I both trains of the control room ===raenev ventilation and/or emeroenev air cone.itionina inonerable, the ftnetion of the controi room ameroency air syst===
! have been lost, reouirina 4--
- .iate action where the specification does not anniv.
to clace the reactor in a condition 2/t '." CM00M CUrrr.tr:Ori : MU!!!?. '
ARKANSAS - UNIT 2 B 3/4 7-5 Amendment No. G ,MG
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(' PLANT SYSTEM 3 BASES 3/4.7.8 SHOCK SUPPRESSORS'(SNUBBERS)
All snubbers are reauired OPERABLE to enaure that the structural intecrity of tre reactor coolant system and all other safetv-related systems is manntained c,urina and folhowina a seismic or other event initiatina dynamnc loads. Snubbers excluded from this insoection procram are those instailed on nonsafetv-related systems and than c.nly .f their failure or failure of the system on whica thev are instailec would have no adverse
! effect on any safetv-related system. I The visual insoection'freauency is based uoon maintaining a constant level of snubber orotection to svsta==. Therefore, the reauired insoection interval varies based uoon the nn=her of INOPERABLE snubbers found durina the crevnous noct insnection in crocortion to the sizes of the various snubber
! iations or cateaories and the crevious insoection interval as soecifned nn b (C Generic ".etter 90-09, " Alternative Requirements For Snubber Visual Mnanection Intervals and Corrective Actions". Mnacections cerformed before that interval has elansed may be used as a new reference coint to determine l_ the next inmoection. However, the result of such early inanections nerformed f
before the criminal reauired time interva2 has elanned (nominal time less 25%) may not be used to lenathen the reaunrad inmoection intervah. Any inmoection whose results reauire a shorter inmoection intervaLwnll override the crevious schedule.
I When the cause of the reiection of a snubber is clearly established and r---died dor tr at snubber and for any other snubbers that may be generically susceptible anc. verified by inservice functional testnna, that snubber may be f
ex==ated from beina counted as inocerable. Genericaliv susceptible snubbers are those which are of a soecific make or model and have the s=== desian features directiv related to reiection of the snubber by visual ir,scection, or are similarly located or exoosed to the s=== environmental conc,itions such as t== =rature, radiation and vibration.
Wher a snuhher is found ir coerable, an enaineerina evaluation is cerformet ir ,
addition to the cleterminatior of the snubber mede af failure, in order to c.etermine if any safetv-relatec O - --onent or system aan been adverselv affected by the ir ocerabilnty of the snubber. The enaineerina i evaluation is nerformed to cetermine whether or not the snukker =ede of I failure has 4 =aerted a significant effect or degradation on tha_REDDorted component or system {
If a review and evaluation of an INOPERABLE anubber is nerforr.ed and .
doc"==nted to iustifv continued ooeration anc.crovided that all desian criteria are met with the INCiPERARLF snubber, then the INOPERABLE snubber l wauld not need to be restorec. or reolaced.
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 personne1' exposures, snubbers installed in areas which have high radiation fields during shutdown or in especially difficult to remove locations may be exempted from these 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.
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PLANT SYSTEM 3 BASES o
3/4.7.9 SEALED SOURCE CONTAMINATION The limitations on removable contamination for sources reauirine leak testina, includino alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakace from byproduct, source, and soecial nuclear material sources will not exceed allowable intake values.
3/4.7.10 FIRE SUPPRESSION 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 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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