ML18039A800
| ML18039A800 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 06/03/1999 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18039A799 | List: |
| References | |
| NUDOCS 9906150081 | |
| Download: ML18039A800 (17) | |
Text
~I~ENCLOSURE 2 TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)UNITS 2 AND 3 PROPOSED TECHNICAL SPECIFICATION (TS)CHANGE TS-397 MARKED PAGE S I.AFFECTED PAGE LIST Technical Unit: 2 3.3-8 3.3-47 3.3-59 3.3-61 3.3-65 3.3-70 Specifications Unit 3 3.3-8 3.3-47 3.3-59 3.3-61 3.3-65 3.3-70 II.MAM<ED PAGES See attached.990hi5008i
'%0603 PDR ADQCK 05000260 P PDR RPS Instrumentation 3.3.1.'I Table 3.3.1.1-1 (page 2 of 3)Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELSPER TMP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION D.I SURVEILLANCE REQUIREMENTS ALLOKVABLE VALUE 2.Average Power Range Monitors (continued) d.In op e.2-Out-Ofd Voter f.OPRM Upscale 3.Reactor Vessel Steam Dome Pressure-High 1,2 1,2 1,2 3(b)3(b)SR 3.3.1.1.16 SR 3.3.1.1.1 SR 3.3.1.1.14 SR 3.3.1.1.16 Sk 3.3.1.1.1 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16 SR 3.3.1.1.17 SR 3.3.1.1.1 SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.14 NA NA 5 1090 psig 52S 4.Reactor Vessel Water Level-Low, Level 3 5.Main Steam Isolation Valve-Closure 6.Drywall Pressure-High 1>2 1,2 SR 3.3.1.1.1 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3,1.1.13 SR 3.3.1.1.14 ches above vessel 5 10%closed 52.5 psig 7.Scram Discharge Volume Water Level-High a.Resistance Temperature Detector 1,2 5(a)H SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 5 50 gallons 5$0 gallons continue (a)With any control rod withdravm from a core cell containing one or more fuel assemblies.(b)Each APRM channel provides inputs to both trip systems.I BFN-UNIT 2 3.3-8 Amendment No.258 March 5, 1999 Ci ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 5 of 6)Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.I SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 4.ADS Trip System A (continued) d.Reactor Vessel Water Level-.I, Low, Level 3 (Confirmatory) 2(d)3(d)SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 44 nches ab vessel zero 528 e.Core Spray Pump Discharge Pressure-High I, 2(d)3(d)SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 h 175 psig and 6 195 psig f.Low Pressure Coolant Injection Pump Discharge Pressure-High I, 2(d)3(d)SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 h 90 psig and 6 110 psig g.Automatic Depressurization System High Dryweil Pressure Bypass Timer 5.ADS Trip System B a.Reactor Vessel Water Level-Low Low Low, Level 1 b.Drywell Pressure-High c.Automatic Depressurization System initiation Timer d.Reactor Vessel Water Level-Low, Level 3 (Confirmatory)
I, 2(d)3(d)I, 2(d)3(d)I, 2(d)3(d)I, 2(d)3(d)I, 2(d)3(d)SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.1 SR 3.3.5.12 SR 3.3.5.1.5 SR 3.3.5.1.6 6 322 seconds I 39S inches above vessel zero 52.5 psig 6 115 seco 44 nches ab vessel zero 528 continued (d)With reactor steam dome pressure>>150 psig.BFN-UNIT 2 3.3-47 Amendment No.253
~I I Primary Contain nt Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page I of 3)Primary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.I SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1.Main Steam Une Isolation a.Reactor Vessel Water Level-Low Low Low, Level 1 b.Main Steam Line Pressure-Low 1,2,3 D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 2 398 inches above vessel zero 2 825 psig c.Main Steam Une Flow-Hlgh 1,2P 2 pef MSL SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 6 140%rated stcam Itow d.Main Steam Tunnel Temperature
-High 2.Primary Containment Isolation a.Reactor Vessel Water Level-Low, Level 3 1,2,3 1,2,3 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.G.I.G 6200'F c nches a c vessel 528 b.Drywell Pressure-High 3.High Pressure Coolant Injection (HPCI)System Isolation a.HPCI Steam Line Flow-Hlgh b.HPCI Steam Supply Line Pressure-Low c.HPCI Turbine Exhaust Diaphragm Pressure-High 1,2,3 1>2>3 1,2,3 1,2,3 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.G.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 52.5 psig 590 psi 2 100 psig S20 psig continu BFN-UNIT 2 3.3-59 Amendment No.253
~~
~>~Primary Contain nt Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 3)Primary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM SURVEILLANCE ALLOtVABLE REQUIRED REQUIREMENTS VALUE ACTION C.I 5.Reactor Water Cleanup (RWCU)System Iso'iation a.Main Steam Valve Vault Area Temperature
-High b.Pipe Trench Area Temperature
-High c.Pump Room A Area Temperature
-High d.Pump Room B Area Temperature
-High e.Heat Exchanger Room Area (West Wall)Temperature
-High f.Heat Exchanger Room Area (East Wall)Temperature
-High g.SLC System Initiation h.Reactor Vessel Water Level-Low, Level 3 1,2,3 1,2>3 1,2,3 1,2,3 ,1,2,3 1,2,3 1>2 1,2,3 1(a)SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.G.1.2 SR 3.3.6.1.4 SR 3.3.6.1.G SR 3.3.6.1.2 SR 3.3.G.1.4 SR 3.3.G.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.G;1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.G SR 3.3.6.1.1 SR 3.3.G.1.2 SR 3.3.6.1.5 SR 3.3.G.I.G 5 Rgt 88'F 5 1350F 5 152oF 5 152oF 6 143oF 6 170>F NA'ches ab e vessel 528 6.Shutdown Cooling System Isolation a.Reactor Steam Dome Pressure-High b.Reactor Vessel Water Level-Low, Level 3 1,2,3 3,4,5 2(b)SR 3.3.6.1.2 SR 3.3.G.1.5 SR 3.3.6.1.6 SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 6 115 psig nches a e vessel 528 c.Drywell Pressure-High 1,2>3 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.G S2.5 psig (a)One SLC System Initiation signal provides logic input to close both RWCU valves.(b)Only one channel per trip system required in MODES 4 and 5 when RHR Shutdovm Cooling System integrity maintained.
BF.N-UNIT 2 3.3-61 Amendment No.254 September 8, 1998 Secondary Contain nt Isolation Instrumentation 3.3.6.2 Table 3.3.G.2-1 (page I of I)Secondary Containment Isolation Instmmentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM SURVEILLANCE REQUIREMENTS ALLOWABLE VAL 528 1.Reactor Vessel Water Level-Low, Level 3 2.Drywell Pressure-High 3.Reactor Zone Exhaust Radiation-High 1,2,3, (a)1,2,3 1,2,3, (a)(b)SR 3.3.6.2.1 SR 3.3.G.2.2 SR 3.3.G.2.3 SR 3.3.6.2.4 SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.G.2.4 ches above veav zcfo 52.5 psig 6 100 mR/hr 4.Refueling Floor Exhaust Radiation-High 1,2P, (axb)SR 3.3.G.2.1 SR 3.3.G.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4 5 100 mR/hr (a)During operations with a potential for draining the reactor vessel.(b)During CORE ALTERATIONS and during movement of irradiated fuel assemblies In secondary containment.
BFN-UNIT 2 3.3-65 Amendment No.253 V System Instrumentation 3.3.7.1 Table 3.3.7.1-1 (page 1 of I)Control Room Emergency Ventilation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FRO>XI REQUIRED ACTION A.I SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 528 1.Reactor Vessel Water Level-Low, Level 3 2.Dryweil Pressure-High 3.Reactor Zone Exhaust Radiation-High 4.Refueling Floor Exhaust Radiation-High 5.Control Room Air Supply Duct Radiation-High 1,2,3,(a)I,2>3 1,2,3 (a)(b)1,2,3, (a)(b)1,2,3, (a)(b)SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.6 SR 3.3.7.1,2 SR 3.3.7.1.5 SR 3.3.7.1.6 SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.6 SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.6 SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.4 above vessel S 2.5 psig 6 100 mR/hr 6 100 mR/hr 6270 cpm above background (a)During operations with a potential for draining the reactor vessel.(b)During CORE ALTERATIONS and during movement of irradiated fuel assemblies in the secondary containment.
8FN-UNIT 2 3.3-70 Amendment No.253
~~RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 of 3)Reactor Protection System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED ClfANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION D.I SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 2.Average Power Range Monitors (continued) d.Inop e.2-Out-Of-4 Voter 3.Reactor Vessel Steam Dome Pressure-High 4.Reactor Vessel Water Level-Low, Level 3 5.Main Steam Isolation Valve-Closure 6.Drywell Pressure-High 7.Scram Discharge Volume Water Level-High a.Resistance Temperature Detector b.Float Switch 1,2 1,2 1,2 1,2 1,2 1,2 5(a)1,2 5(a)3(b)F SR 3.3.1.1.1G SR 3.3.1.1.1 SR 3.3.1.1.14 SR 3.3.1.1.1G SR 3.3.1.1.1 SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.14 SR 3.3.1.1.1 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 NA 5 1090 psig e nches a o vessel 5 104/o closed 52.5 psig 5 50 gallons 5 50 gallons 5 50 gallons 5 50 gallons 528 (continued)(a)With any control rod withdrawn from a core cell containing one or more fuel assemblies.(b)Each APRM channel provides inputs to both trip systems.BFN-UNIT 3 3.3-8 Amendment No.214 September 08, 1998 ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 5 of 6)Emergency Core Cooling System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER FUNCTION CONDITIONS REFERENCED FROM REQUIRED ACTION A.I SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 4.ADS Trip System A (continued) d.Reactor Vessel Water Level-Low, Level 3 (Confirmatory) e.Core Spray Pump Discharge Pressure-High f.Low Pressure Coolant tniection Pump Discharge Pressure-High g.Automatic Depressurization System High Drywall Pressure Bypass Timer 5.ADS Trip System B a.Reactor Vessel Water Level-Low Low Low, Level 1 I, 2(d)3(d)I, 2(d), 3(d)I, 2(d)3(d)I, 2(d),3(d)I, 2(d),3(d)SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 52S abo vessel zero 2 175 psig and 5 195 psig 290 psig and 6 110 psig 5 322 seconds 2 398 inches above vessel zero b.Drywell Pressure-High c.Automatic Depressurlzation System Initiation Timer d.Reactor Vessel Water Level-Low, Level 3 (Confirmatory)
I, 2(d)3(d)I, 2(d)3(d)I, 2(d),3(d)SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.5 SR 3.3.5.1.6 SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 62.5 psig 6 115 seco 528 nchcs ab c vessel zero continued (d)With reactor steam dome pressure)150 psig.BFN-UNIT 3 3.3-47 Amendment No.213 September 03, 1998 Primary Contain nt Isolation Instrumentation 3.3.6.'I Table 3.3.6.1-1 (page 1 of 3)Primary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.I SURVEILLANCE REQUIREMENTS ALLOWABLE VALUE 1.Main Steam Line Isolation a.Reactor Vessel Water Level-LowLowLow, Level 1 b.Main Steam Une Pressure-Low c.Main Steam Line Flow-High d.Main Steam Tunnel Temperature
-High 2.Primary Containment Isolation a.Reactor Vessel Water Level-Low, Level 3 b.Drywell Pressure-High 3.High Pressure Coolant Injection (HPCI)System Isolation a.HPCI Steam Une Flow-High b.HPCI Steam Supply Line Pressure-Low 1,2,3 1,2,3 1,2,3 1>2,3 1,2,3 1>2,3 1,2,3 2 pef MSL SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.G.1.5 SR 3.3.6.1.6 SR 3.3.G.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.1 SR 3.3.G.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.G.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 2 398 inches above vessel 2 825 psig 5 140%rated steam flow 52000F e nches ab e vessel 52.5 psig 590 psi h 100 psig 528 c.HPCI Turbine Exhaust Diaphragm Pressure-High 1,2,3 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 520 psig continued BFN-UNIT 3 3.3-59 Amendment No.213 September 03, 1998 0 i1 Primary Contain nt Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 3)Primary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION C.I SURVEILLANCE REQUIREMENTS ALLOtVABLE VALUE 5.Reactor Water Cleanup (RWCU)System Isolation a.Main Steam Valve Vault Area Temperature
-High b.Pipe Trench Area Temperature
-High c.Pump Room A Area Temperature
-High d.Pump Room B Area Temperature
-High e.Heat Exchanger Room Area (West Wall)Temperature
-High f.Heat Exchanger Room Area (East Wall)Temperature
-High g.SLC System Initiation h.Reactor Vessel Water Level-Low, Level 3 l>2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2,3 1,2 1>2,3 1(a)SR 3.3.G.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.G.1.4 SR 3.3.6.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.G.1.6 SR 3.3.6.1.2 SR 3.3.G.1.4 SR 3.3.G.1.6 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.6 SR 3.3.6.1.6 SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 5 201'F 135oF 5 152'F 5 152oF 6 143oF 5 170oF NA nches c vessel 52S 6.Shutdown Cooling System Isolation a.Reactor Steam Dome Pressure-High b.Reactor Vessel Water Level-Low, Level 3 1,2,3 3,4,5 2(b)SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.G 5'115 psig 52S c.Drywell Pressure-High 1,2,3 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 52.5 psig (a)One SLC System Initiation signal provides logic input to close both RWCU vatves.(b)Only one channel per trip system required In MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.
BFN-UNIT 3 3.3-61 Amendment No.213 September 03, 1998 Secondary Contain nt Isolation Instrumentation 3.3.6.2 Table 3.3.6.2-1 (page I of I)Secondary Containment Isolation Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM SURVEILLANCE ALLO'tVABLE REQUIREMENTS VAL 528 Reactor Vessel Water Level-Low, Level 3 2.Drywell Pressure-High 1,2,3, 1,2,3 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4 SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4 nches above v~zero S 2.5 psig 3.Reactor Zone Exhaust Radiation-High 4.Refueling Floor Exhaust Radiation-High 1,2,3, (aX>>1,2,3, ()(b)SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4 SR 3.3.6.2.1 SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4 S 100 mR/hr 5 100 mR/hr (a)During operations viith a potential (or draining the reactor vessel.(b)During CORE ALTERATIONS and during movement of Irradiated fuel assemblies In secondary containment.
8FN-UNIT 3 3.3-65 Amendment No.213 September 03, 1998
~(4 V System Instrumentation 3.3.7.1 Table 3.3.7.1-1 (page I of I)Control Room Emergency Ventilation System Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER TRIP SYSTEM CONDITIONS REFERENCED FROM REQUIRED ACTION A.I SURVEILLANCE REQUIREMENTS ALLOEVABLE VALUE 52S 1.Reactor Vessel Water Level-Low, Level 3 1,2,3,(a)SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.6 nches a e vessel 2.Drywell Pressure-High 1,2,3 SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.G 52.5 psig 3.Reactor Zone Exhaust Radiation-High 4.Refueling Floor Exhaust Radiation-High 5.Control Room Air Supply Duct Radiation-High I>2,3 (a).(b)1,2,3, (a)(b)1,2,3, (a),(b)SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.G SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.G SR 3.3.7.1.1 SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.4 5 100 mR/hr 8 100 mR/hr 5270 cpm above background (a)During operations with a potential for draining the reactor vessel (b)During CORE AI.TERATIONS and during movement of irradiated fuel assemblies in the secondary containment.
BFN-UNIT 3 3.3-70 Amendment No.213 September 03, 1998 0 0'