ML18039A800

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Proposed Tech Specs,Reducing Allowable Value Used for Reactor Vessel Water Level - Low,Level 3 for Several Instrument Functions
ML18039A800
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 06/03/1999
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18039A799 List:
References
NUDOCS 9906150081
Download: ML18039A800 (17)
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Text

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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 Specifications Unit: 2 Unit 3 3.3-8 3.3-8 3.3-47 3.3-47 3.3-59 3.3-59 3.3-61 3.3-61 3.3-65 3.3-65 3.3-70 3.3-70 II. MAM<ED PAGES See attached.

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RPS Instrumentation 3.3.1.'I Table 3.3.1.1-1 (page 2 of3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOKVABLE SPECIFIED PER TMP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION D. I

2. Average Power Range Monitors (continued)
d. In op 1,2 3(b) SR 3.3.1.1.16 NA
e. 2-Out-Ofd Voter 1,2 SR 3.3.1.1.1 NA SR 3.3.1.1.14 SR 3.3.1.1.16
f. OPRM Upscale 3(b) 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
3. Reactor Vessel Steam Dome 1,2 SR 3.3.1.1.1 5 1090 psig Pressure - High SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.14 52S
4. Reactor Vessel Water Level- 1>2 SR 3.3.1.1.1 ches Low, Level 3 SR 3.3.1.1.8 above vessel SR 3.3.1.1.13 SR 3.3.1.1.14
5. Main Steam Isolation Valve- SR 3.3.1.1.8 5 10% closed Closure SR 3.3.1.1.13 SR 3.3.1.1.14
6. Drywall Pressure - High 1,2 SR 3.3.1.1.8 52.5 psig SR 3.3,1.1.13 SR 3.3.1.1.14
7. Scram Discharge Volume Water Level - High
a. Resistance Temperature 1,2 SR 3.3.1.1.8 5 50 gallons Detector SR 3.3.1.1.13 SR 3.3.1.1.14 5(a) H SR 3.3.1.1.8 5 $ 0 gallons SR 3.3.1.1.13 SR 3.3.1.1.14 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 APPLICABLE CONDITIONS MODES REQUIRED REFERENCED FUNCTION OR OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER REQUIRED REQUIREMENTS VALUE CONDITIONS FUNCTION ACTION A. I

4. ADS Trip System A (continued) 528
d. Reactor Vessel Water Level - . I, SR 3.3.5.1.1 44 nches Low, Level 3 (Confirmatory) 2(d) 3(d) SR 3.3.5.1.2 ab vessel SR 3.3.5.1.5 zero SR 3.3.5.1.6
e. Core Spray Pump Discharge I, SR 3.3.5.1.2 h 175 psig and Pressure - High 2(d) 3(d) SR 3.3.5.1.3 6 195 psig SR 3.3.5.1.6
f. Low Pressure Coolant I, SR 3.3.5.1.2 h 90 psig and Injection Pump Discharge 2(d) 3(d) SR 3.3.5.1.3 6 110 psig Pressure - High SR 3.3.5.1.6
g. Automatic Depressurization I, SR 3.3.5.1.5 6 322 seconds System High Dryweil 2(d) 3(d) SR 3.3.5.1.6 Pressure Bypass Timer
5. ADS Trip System B
a. Reactor Vessel Water Level- I, SR 3.3.5.1.1 3.3.5.1.2 I39S inches Low Low Low, Level 1 2(d) 3(d) SR above vessel SR 3.3.5.1.5 zero SR 3.3.5.1.6
b. Drywell Pressure - High I, SR 3.3.5.1.2 52.5 psig 2(d) 3(d) SR 3.3.5.1.5 SR 3.3.5.1.6
c. Automatic Depressurization I, SR 3.3.5.1.5 6 115 seco System initiation Timer 2(d) 3(d) SR 3.3.5.1.6 528
d. Reactor Vessel Water Level- I, SR 3.3.5.1.1 44 nches Low, Level 3 (Confirmatory) 2(d) 3(d) SR 3.3.5.12 ab vessel SR 3.3.5.1.5 zero SR 3.3.5.1.6 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 APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION C. I

1. Main Steam Une Isolation
a. Reactor Vessel Water 1,2,3 D SR 3.3.6.1.1 2 398 inches Level - Low Low Low, SR 3.3.6.1.2 above vessel Level 1 SR 3.3.6.1.5 zero SR 3.3.6.1.6
b. Main Steam Line Pressure SR 3.3.6.1.2 2 825 psig

- Low SR 3.3.6.1.5 SR 3.3.6.1.6

c. Main Steam Une Flow- 1,2P 2 pef SR 3.3.6.1.1 6 140% rated Hlgh MSL SR 3.3.6.1.2 stcam Itow SR 3.3.6.1.5 SR 3.3.6.1.6
d. Main Steam Tunnel 1,2,3 SR 3.3.6.1.2 6200'F Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6
2. Primary Containment Isolation 528
a. Reactor Vessel Water 1,2,3 SR 3.3.6.1.1 nches Level - Low, Level 3 SR 3.3.6.1.2 a c vessel SR 3.3.6.1.5 SR 3.3.G.I.G
b. Drywell Pressure - High 1,2,3 SR 3.3.6.1.2 52.5 psig SR 3.3.6.1.5 SR 3.3.6.1.6
3. High Pressure Coolant Injection (HPCI) System Isolation
a. HPCI Steam Line Flow- 1>2>3 SR 3.3.6.1.2 590 psi Hlgh SR 3.3.6.1.5 SR 3.3.6.1.6
b. HPCI Steam Supply Line 1,2,3 SR 3.3.6.1.2 2 100 psig Pressure - Low SR 3.3.6.1.5 SR 3.3.6.1.6
c. HPCI Turbine 1,2,3 SR 3.3.G.1.2 S20 psig Exhaust Diaphragm SR 3.3.6.1.5 Pressure - High SR 3.3.6.1.6 continu BFN-UNIT 2 3.3-59 Amendment No. 253

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Primary Contain nt Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of3)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOtVABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION C. I

5. Reactor Water Cleanup (RWCU) System Iso'iation
a. Main Steam Valve Vault 1,2,3 SR 3.3.6.1.2 5 Rgt 88'F Area Temperature - High SR 3.3.6.1.4 SR 3.3.6.1.6
b. Pipe Trench Area 1,2>3 SR 3.3.6.1.2 5 1350F Temperature - High SR 3.3.6.1.4 SR 3.3.6.1.6
c. Pump Room A Area 1,2,3 SR 3.3.G.1.2 5 152oF Temperature - High SR 3.3.6.1.4 SR 3.3.6.1.G
d. Pump Room B Area 1,2,3 SR 3.3.6.1.2 5 152oF Temperature - High SR 3.3.G.1.4 SR 3.3.G.1.6
e. Heat Exchanger Room ,1,2,3 SR 3.3.6.1.2 6 143oF Area (West Wall) SR 3.3.6.1.4 Temperature - High SR 3.3.G;1.6
f. Heat Exchanger Room 1,2,3 SR 3.3.6.1.2 6 170>F Area (East Wall) SR 3.3.6.1.4 Temperature - High SR 3.3.6.1.6
g. SLC System Initiation 1>2 1(a) SR 3.3.6.1.G 528 NA'ches
h. Reactor Vessel Water 1,2,3 SR 3.3.6.1.1 Level - Low, Level 3 SR 3.3.G.1.2 ab e vessel SR 3.3.6.1.5 SR 3.3.G.I.G
6. Shutdown Cooling System Isolation
a. Reactor Steam Dome 1,2,3 SR 3.3.6.1.2 6 115 psig Pressure - High SR 3.3.G.1.5 SR 3.3.6.1.6 528
b. Reactor Vessel Water 3,4,5 2(b) SR 3.3.6.1.1 nches Level - Low, Level 3 SR 3.3.6.1.2 a e vessel SR 3.3.6.1.5 SR 3.3.6.1.6
c. Drywell Pressure - High 1,2>3 SR 3.3.6.1.2 S2.5 psig SR 3.3.6.1.5 SR 3.3.6.1.G (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 APPLICABLE MODES OR REQUIRED FUNCTION OTHER SPECIFIED CHANNELS SURVEILLANCE ALLOWABLE CONDITIONS PER REQUIREMENTS VAL TRIP SYSTEM 528

1. Reactor Vessel Water Level- 1,2,3, SR 3.3.6.2.1 ches above Low, Level 3 (a) SR 3.3.G.2.2 veav zcfo SR 3.3.G.2.3 SR 3.3.6.2.4
2. Drywell Pressure - High 1,2,3 SR 3.3.6.2.2 52.5 psig SR 3.3.6.2.3 SR 3.3.6.2.4
3. Reactor Zone Exhaust 1,2,3, SR 3.3.6.2.1 6 100 mR/hr Radiation - High (a)(b) SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.G.2.4
4. Refueling Floor Exhaust 1,2P, SR 3.3.G.2.1 5 100 mR/hr Radiation - High (axb) SR 3.3.G.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4 (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 APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FRO>XI SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION A. I 528

1. Reactor Vessel Water Level- 1,2,3,(a) SR 3.3.7.1.1 Low, Level 3 SR 3.3.7.1.2 above vessel SR 3.3.7.1.5 SR 3.3.7.1.6
2. Dryweil Pressure - High I,2>3 SR 3.3.7.1,2 S 2.5 psig SR 3.3.7.1.5 SR 3.3.7.1.6
3. Reactor Zone Exhaust 1,2,3 SR 3.3.7.1.1 6 100 mR/hr Radiation - High (a) (b) SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.6
4. Refueling Floor Exhaust 1,2,3, SR 3.3.7.1.1 6 100 mR/hr Radiation - High (a) (b) SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.6
5. Control Room Air Supply Duct 1,2,3, SR 3.3.7.1.1 6270 cpm Radiation - High (a) (b) SR 3.3.7.1.2 above SR 3.3.7.1.3 background SR 3.3.7.1.4 (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

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RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 of3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER ClfANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION D. I

2. Average Power Range Monitors (continued)
d. Inop 1,2 3(b) SR 3.3.1.1.1G
e. 2-Out-Of-4 Voter 1,2 SR 3.3.1.1.1 NA SR 3.3.1.1.14 SR 3.3.1.1.1G
3. Reactor Vessel Steam Dome 1,2 SR 3.3.1.1.1 5 1090 psig Pressure - High SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.14 528
4. Reactor Vessel Water Level- 1,2 SR 3.3.1.1.1 nches Low, Level 3 SR 3.3.1.1.8 a oe vessel SR 3.3.1.1.13 SR 3.3.1.1.14
5. Main Steam Isolation Valve- F SR 3.3.1.1.8 5 104/o closed Closure SR 3.3.1.1.13 SR 3.3.1.1.14
6. Drywell Pressure - High 1,2 SR 3.3.1.1.8 52.5 psig SR 3.3.1.1.13 SR 3.3.1.1.14
7. Scram Discharge Volume Water Level - High
a. Resistance Temperature 1,2 SR 3.3.1.1.8 5 50 gallons Detector SR 3.3.1.1.13 SR 3.3.1.1.14 5(a) SR 3.3.1.1.8 5 50 gallons SR 3.3.1.1.13 SR 3.3.1.1.14
b. Float Switch 1,2 SR 3.3.1.1.8 5 50 gallons SR 3.3.1.1.13 SR 3.3.1.1.14 5(a) SR 3.3.1.1.8 5 50 gallons SR 3.3.1.1.13 SR 3.3.1.1.14 (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 APPLICABLE CONDITIONS MODES REQUIRED REFERENCED FUNCTION OR OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER REQUIRED REQUIREMENTS VALUE CONDITIONS FUNCTION ACTION A. I

4. ADS Trip System A (continued) 52S
d. Reactor Vessel Water Level I, SR 3.3.5.1.1 Low, Level 3 (Confirmatory) 2(d) 3(d) SR 3.3.5.1.2 abo vessel zero SR 3.3.5.1.5 SR 3.3.5.1.6
e. Core Spray Pump Discharge I, SR 3.3.5.1.2 2 175 psig and Pressure High 2(d), 3(d) SR 3.3.5.1.3 5 195 psig SR 3.3.5.1.6
f. Low Pressure Coolant I, SR 3.3.5.1.2 290 psig and tniection Pump Discharge 2(d) 3(d) SR 3.3.5.1.3 6 110 psig Pressure High SR 3.3.5.1.6
g. Automatic Depressurization I, SR 3.3.5.1.5 5 322 seconds System High Drywall 2(d),3(d) SR 3.3.5.1.6 Pressure Bypass Timer
5. ADS Trip System B
a. Reactor Vessel Water Level I, SR 3.3.5.1.1 2 398 inches Low Low Low, Level 1 2(d),3(d) SR 3.3.5.1.2 above vessel zero SR 3.3.5.1.5 SR 3.3.5.1.6
b. Drywell Pressure High I, SR 3.3.5.1.2 62.5 psig 2(d) 3(d) SR 3.3.5.1.5 SR 3.3.5.1.6
c. Automatic Depressurlzation I, SR 3.3.5.1.5 6 115 seco System Initiation Timer 2(d) 3(d) SR 3.3.5.1.6 528
d. Reactor Vessel Water Level I, SR 3.3.5.1.1 nchcs Low, Level 3 (Confirmatory) 2(d),3(d) SR 3.3.5.1.2 ab c vessel zero SR 3.3.5.1.5 SR 3.3.5.1.6 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 of3)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION C. I

1. Main Steam Line Isolation
a. Reactor Vessel Water 1,2,3 SR 3.3.6.1.1 2 398 inches Level - LowLowLow, SR 3.3.6.1.2 above vessel Level 1 SR 3.3.G.1.5 SR 3.3.6.1.6
b. Main Steam Une Pressure SR 3.3.G.1.2 2 825 psig

- Low SR 3.3.6.1.5 SR 3.3.6.1.6

c. Main Steam Line Flow- 1,2,3 2 pef SR 3.3.6.1.1 5 140% rated High MSL SR 3.3.G.1.2 steam flow SR 3.3.6.1.5 SR 3.3.6.1.6
d. Main Steam Tunnel 1,2,3 SR 3.3.6.1.2 52000F Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6
2. Primary Containment Isolation 528
a. Reactor Vessel Water 1>2,3 SR 3.3.6.1.1 nches Level - Low, Level 3 SR 3.3.6.1.2 ab e vessel SR 3.3.6.1.5 SR 3.3.6.1.6
b. Drywell Pressure - High 1,2,3 SR 3.3.6.1.2 52.5 psig SR 3.3.6.1.5 SR 3.3.6.1.6
3. High Pressure Coolant Injection (HPCI) System Isolation
a. HPCI Steam Une Flow- 1>2,3 SR 3.3.6.1.2 590 psi High SR 3.3.6.1.5 SR 3.3.6.1.6
b. HPCI Steam Supply Line 1,2,3 SR 3.3.G.1.2 h 100 psig Pressure - Low SR 3.3.6.1.5 SR 3.3.6.1.6
c. HPCI Turbine 1,2,3 SR 3.3.6.1.2 520 psig Exhaust Diaphragm SR 3.3.6.1.5 Pressure - High SR 3.3.6.1.6 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 of3)

Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOtVABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION C. I

5. Reactor Water Cleanup (RWCU) System Isolation
a. Main Steam Valve Vault l>2,3 SR 3.3.G.1.2 5 201'F Area Temperature - High SR 3.3.6.1.4 SR 3.3.6.1.6
b. Pipe Trench Area 1,2,3 SR 3.3.6.1.2 135oF Temperature - High SR 3.3.6.1.4 SR 3.3.6.1.6
c. Pump Room A Area 1,2,3 SR 3.3.6.1.2 5 152'F Temperature - High SR 3.3.G.1.4 SR 3.3.6.1.6
d. Pump Room B Area 1,2,3 SR 3.3.6.1.2 5 152oF Temperature - High SR 3.3.6.1.4 SR 3.3.G.1.6
e. Heat Exchanger Room 1,2,3 SR 3.3.6.1.2 6 143oF Area (West Wall) SR 3.3.G.1.4 Temperature - High SR 3.3.G.1.6
f. Heat Exchanger Room 1,2,3 SR 3.3.6.1.2 5 170oF Area (East Wall) SR 3.3.6.1.4 Temperature - High SR 3.3.6.1.6
g. SLC System Initiation 1,2 1(a) SR 3.3.6.1.6 NA 52S
h. Reactor Vessel Water 1>2,3 SR 3.3.6.1.1 nches Level - Low, Level 3 SR 3.3.6.1.2 c vessel SR 3.3.6.1.5 SR 3.3.6.1.6
6. Shutdown Cooling System Isolation
a. Reactor Steam Dome 1,2,3 SR 3.3.6.1.2 5'115 psig Pressure - High SR 3.3.6.1.5 SR 3.3.6.1.6 52S
b. Reactor Vessel Water 3,4,5 2(b) SR 3.3.6.1.1 Level - Low, Level 3 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.G
c. Drywell Pressure - High 1,2,3 SR 3.3.6.1.2 52.5 psig SR 3.3.6.1.5 SR 3.3.6.1.6 (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 APPLICABLE MODES OR REQUIRED FUNCTION OTHER SPECIFIED CHANNELS SURVEILLANCE ALLO'tVABLE CONDITIONS PER REQUIREMENTS VAL TRIP SYSTEM 528 Reactor Vessel Water Level- 1,2,3, SR 3.3.6.2.1 nches above Low, Level 3 SR 3.3.6.2.2 v~ zero SR 3.3.6.2.3 SR 3.3.6.2.4

2. Drywell Pressure - High 1,2,3 SR 3.3.6.2.2 S 2.5 psig SR 3.3.6.2.3 SR 3.3.6.2.4
3. Reactor Zone Exhaust 1,2,3, SR 3.3.6.2.1 S 100 mR/hr Radiation - High (aX>> SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4
4. Refueling Floor Exhaust 1,2,3, SR 3.3.6.2.1 5 100 mR/hr Radiation - High ( )(b) SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4 (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 APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOEVABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION A. I 52S

1. Reactor Vessel Water Level- 1,2,3,(a) SR 3.3.7.1.1 nches Low, Level 3 SR 3.3.7.1.2 a e vessel SR 3.3.7.1.5 SR 3.3.7.1.6
2. Drywell Pressure - High 1,2,3 SR 3.3.7.1.2 52.5 psig SR 3.3.7.1.5 SR 3.3.7.1.G
3. Reactor Zone Exhaust I>2,3 SR 3.3.7.1.1 5 100 mR/hr Radiation - High (a).(b) SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.G
4. Refueling Floor Exhaust 1,2,3, SR 3.3.7.1.1 8 100 mR/hr Radiation - High (a) (b) SR 3.3.7.1.2 SR 3.3.7.1.5 SR 3.3.7.1.G
5. Control Room Air Supply Duct 1,2,3, SR 3.3.7.1.1 5270 cpm Radiation - High (a),(b) SR 3.3.7.1.2 above SR 3.3.7.1.3 background SR 3.3.7.1.4 (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

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