ML062580119

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Technical Specification - Issuance of Amendments Regarding the Instrument Setpoint Program - Drift Susceptible Instruments (TAC Nos. MC9518, MC9519, and MC9520) (TS-453)
ML062580119
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 09/14/2006
From: Chernoff M
NRC/NRR/ADRO/DORL/LPLII-2
To:
Chernoff M, NRR/DORL, 415-4041
Shared Package
ML061680009 List:
References
TAC MC9518, TAC MC9519, TAC MC9520
Download: ML062580119 (33)
v • d • e


Text

(3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or equipment and instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:

Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 3293 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 257, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

For Surveillance Requirements (SRs) that are new in Amendment 234 to Facility Operating License DPR-33, the first performance is due at the end of the first surveillance interval that begins at implementation of the Amendment 234. For SRs that existed prior to Amendment 234, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the surveillance was last performed prior to implementation of Amendment 234.

Renewed License No. DPR-33 Amendmeht No. 257

RPS Ins~trumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION D.1

2. Average Power Range Monitors (continued)
d. Downscale 1 2 F SR 3.3.1.1.7 23%RTP SR 3.3.1.1.8 SR 3.3.1.1.14
e. Inop 1,2 2 G SR 3.3.1.1.7 NA SR 3.3.1.1.8 SR 3.3.1.1.14
3. Reactor Vessel Steam Dome 1,2 2 G SR 3.3.1.1.1 . 1055 psig Pressure - High(d) SR 3.3.1.1.8 SR 3.3.1.1.10 I SR 3.3.1.1.14
4. Reactor Vessel Water Level - 1,2 2 G SR 3.3.1.1.1  ;:538 inches Low, Level 3 (d) SR 3.3.1.1.8 above vessel SR 3.3.1.1.13 zero I SR 3.3.1.1.14
5. Main Steam Isolation Valve - 1 8 F SR 3.3.1.1.8 < 10% closed Closure SR 3.3.1.1.13 SR 3.3.1.1.14
6. Drywell Pressure - High 1,2 2 G SR 3.3.1.1.8 < 2.5 psig SR 3.3.1.1.13 SR 3.3.1.1.14
7. Scram Discharge Volume Watcr Level - High
a. Resistance Temperature 1,2 2 G SR 3.3.1.1.8 -<50 gallons Detector SR 3.3.1.1.13 SR 3.3.1.1.14 5 (a) 2 H SR 3.3.1.1.8 -<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.

(d) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by Its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the Instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified In Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT 1 3.3-7 Amendment No. 2347, 257

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 3 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION D.1

7. Scram Discharge Volume Water Level - High (continued)
b. Float Switch 1,2 2 G SR 3.3.1.1.8 < 50 gallons SR 3.3.1.1.13 SR 3.3.1.1.14 5 (a) 2 H SR 3.3.1.1.8 < 50 gallons SR 3.3.1.1.13 SR 3.3.1.1.14
8. Turbine Stop Valve Closure .30% RTP 4 E SR 3.3.1.1.8 -<10% closed SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15
9. Turbine Control Valve Fast 2!30% RTP 2 E SR 3.3.1.1.8 >550 psig Closure, Trip Oil Pressure - SR 3.3.1.1.13 Low(d) SR 3.3.1.1.14 SR 3.3.1.1.15 I
10. Reactor Mode Switch - 1,2 1 G SR 3.3.1.1.12 NA Shutdown Position SR 3.3.1.1.14 5 (a) 1 H SR 3.3.1.1.12 NA SR 3.3.1.1.14
11. Manual Scram 1,2 1 G SR 3.3.1.1.8 NA SR 3.3.1.1.14 5 (a) 1 H SR 3.3.1.1.8 NA SR 3.3.1.1.14
12. RPS Channel Test Switches 1,2 2 G SR 3.3.1.1.4 NA 5 (a) 2 H SR 3.3.1.1.4 NA (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(d) During Instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service In accordance with the Surveillance. Ifthe As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which Is incorporated by reference inthe Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

3.3-8 Amendment No. 234-, 2 57 BFN-UNIT 1

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 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.1

1. Core Spray System
a. Reactor Vessel Water 1,2,3, 4 (b) B SR 3.3.5.1.1 Ž398 inches Level - Low Low Low, 4 (a), 5 (a) SR 3.3.5.1.2 above vessel Level 1 (e) SR 3.3.5.1.5 zero SR 3.3.5.1.6
b. Drywell Pressure - 1.2.3 4 (b) B SR 3.3.5.1.2 :5 2.5 psig High(e) SR 3.3.5.1.5 SR 3.3.5.1.6
c. Reactor Steam Dome 1,2,3 4 (b) C SR 3.3.5.1.2 ;t 435 psig Pressure - Low (Injection 2 per trip SR 3.3.5.1.4 and Permissive and ECCS system SR 3.3.5.1.6 < 465 psig Initiation)(e) 4(a). 5(a) 4 B SR 3.3.5.1.2 2-435 psig 2 per trip SR 3.3.5.1A and system SR 3.3.5.1.6 5 465 psig
d. Core Spray Pump 1,2,3, 2 E SR 3.3.5.1.2 a 1647gpm Discharge Flow - Low 4 (a), 5 (a) 1 per SR 3.3.5.1.5 and (Bypass) subsystem :5 2910 gpm
e. Core Spray Pump Start -

Time Delay Relay Pumps A,B,C,D (with 1,2,3, 4 C SR 3.3.5.1.5 > 6 seconds diesel power) 4 (a), 5 (a) 1 per pump SR 3.3.5.1.6 and

_<8 seconds Pump A (with normal 1,2,3, 1 C SR 3.3.5.1.5 >0 seconds power) 4 (a), 5 (a) SR 3.3.5.1.6 and

_<1 second Pump B (with normal 1,2,3, C SR 3.3.5.1.5 'a6 seconds power) 4 (a), 5 (a) SR 3.3.5.1.6 and 5 8 seconds (continued)

(aa) When associated subsystem(s) are required to be OPERABLE.

(b) Channels affect Commorn Accident Signal Logic. Refer to LCO 3.8.1, "AC Sources - Operating."

(e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by Its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before retuming the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference In the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Toleranceband, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-IJNIT 1 3.3-42 Amendment No. 2,34- 257

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1 -1 (page 2 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.1

1. Core Spray System (continued) e.. Core Spray Pump Start -

Time Delay Relay (continued)

Pump C (with normal power) 1,2,3, 1 C SR 3.3.5.1.5 2 12 seconds 4 (a), 5 (a) SR 3.3.5.1.6 and

< 16 seconds Pump D (with normal power) 1,2,3, .1 C SR 3.3.5.1.5 ZŽ 18 seconds 4 (a), 5 (a) SR 3.3.5.1.6 and

_<24 seconds

2. Low Pressure Coolant Injection (LPCI) System
a. Reactor Vessel Water Level 1,2,3, 4 B SR 3.3.5.1.1 Ž398 inches Low Low Low, Level I(e) 4 (a), 5 (a) SR 3.3.5.1.2 above vessel SR 3.3.5.1.5 zero SR 3.3.5.1.6
b. Drywell Pressure - High(e) 1,2,3 4 B SR 3.3.5.1.2 _*2.5 psig SR 3.3.5.1.5 SR 3.3.5.1.6
c. Reactor Steam Dome 1,2,3 4 C SR 3.3.5.1.2 Ž!435 psig and Pressure - Low (Injection SR 3.3.5.1.4 < 465 psig Permissive and ECCS SR 3.3.5.1.6 Initiation)(e) 4 (a), 5 (a) 4 B SR 3.3.5.1.2 >435 psig and SR 3.3.5.1.4 *465 psig SR 3.3.5.1.6 (continued)

(a) When associated subsystem(s) are required to be OPERABLE.

(b) Deleted.

(e) During instrument calibrations, If the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by Its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT 1 3.3-43 Amendment No. 234 257

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 3 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.1

2. LPCI System (continued)
d. Reactor Steam Dome .1((c),2 c) 4 C SR 3.3.5.1.2 _215 psig Pressure - Low SR 3.3.5.1.4 and (Recirculation Discharge 3 (S)R 3.3.5.1.4 SR 3.3.5.1.6 and

_<245 psig Valve Permissive)(e)

e. Reactor Vessel Water Level 1,2,3 2 B SR 3.3.5.1.1 Z: 312 5/16

- Level 0 1 per SR 3.3.5.1.2 inches above subsystem SR 3.3.5.1.5 vessel zero SR 3.3.5.1.6

f. Low Pressure Coolant Injection Pump Start - Time

< 1 second Pump A (with normal power) 1.2,3, 1

_<1 second Pump B (with normal power) 1.2,3, 1 C SR 3.3.5.1.5 > 6 seconds 4 (a), 5 (a) SR 3.3.5.1.6 and

< 8 seconds Pump C (with normal power) 1,2,3, 1 C SR 3.3.5.1.5 Ž-12 seconds 4 (a), 5 (a) SR 3.3.5.1.6 and

_<16 seconds Pump D (with normal power) 1,2,3, C SR 3.3.5.1.5 . 18 seconds 4 (a), 5 (a) SR 3.3.5.1.6 and

_524 seconds (continued)

(a) When the associated subsystem(s) are required to be OPERABLE.

(c) With associated recirculation pump discharge valve open.

(e) During instrument calibrations, if the As Found channel setpoint Is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT 1 3.3-44 Amendment No. 234,250, 257

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 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.1

3. High Pressure Coolant Injection (HPCI) System
a. Reactor Vessel Water Level 1, 4 B SR 3.3.5.1.1 Zt 470 inches

- Low Low, Level 2 (e) 2 (d), 3 (d) SR 3.3.5.1.2 above vessel SR 3.3.5.1.5 zero SR 3.3.5.1.6

b. Drywell Pressure - High(e) 1, 4 B SR 3.3.5.1.2 :5 2.5 psig 2(d),3(d) SR 3.3.5.1.5 SR 3.3.5.1.6
c. Reactor Vessel Water Level 1, , 2 C SR 3.3.5.1.1 :5 583 inches

- High, Level 8 2 (d), 3 (d) SR 3.3.5.1.2 above vessel SR 3.3.5.1.5 zero SR 3.3.5.1.6

d. Condensate Header Level - 1D SR 3.3.5.1.2 Z: Elev. 551 Low 2 (d). 3 (d) SR 3.3.5.1.3 feet SR 3.3.5.1.6
e. Suppression Pool Water 1, 1 D SR 3.3.5.1.2 < 7 inches Level - High 2(d), 3(d SR 3.3.5.1.3 above SR 3.3.5.1.6 instrument zero
f. High Pressure Coolant 1, 1 E SR 3.3.5.1.2 Ž671 gpm Injection Pump Discharge 2 (d), 3 (d) SR 3.3.5.1.5 Flow - Low (Bypass) SR 3.3.5.1.6
4. Automatic Depressurization System (ADS) Trip System A
a. Reactor Vessel Water Level 1, 2 F SR 3.3.5.1.1  ; 398 inches

- Low Low Low, Level 1 (e) 2 (d), 3 (d) SR 3.3.5.1.2 above vessel SR 3.3.5.1.5 zero SR 3.3.5.1.6 (continued)

(d) With reactor steam dome pressure > 150 psig.

(e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside Its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT 1 3.3-45 Amendment No. 2,4_ 257

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.1

4. ADS Trip System A (continued)
b. Drywell Pressure - High(e) 1 2 F SR 3.3.5.1.2 _<2.5 psig 2 (d) 3 (d) SR 3.3.5.1.5 SR 3.3.5.1.6
c. Automatic Depressurization 1, 1 G SR 3.3.5.1.5 < 115 System Initiation Timer 2 (d), 3 (d) SR 3.3.5.1.6 seconds.
d. Reactor Vessel Water Level 1, F SR 3.3.5.1.1 > 544 inches

- Low, Level 3 2(d), 3(d) SR 3.3.5.1.2 above vessel (Confirmatory)(e) SR 3.3.5.1.5 zero SR 3.3.5.1.6

e. Core Spray Pump Discharge 1, 4 G SR 3.3.5.1.2 Z:175 psig Pressure - High 2 (d), 3 (d) SR 3.3.5.1.3 and SR 3.3.5.1.6 < 195 psig
f. Low Pressure Coolant 1, 8 G SR 3.3.5.1.2 2t 90 psig and Injection Pump Discharge 2 (d), 3 (d) SR 3.3.5.1.3 5 110 psig Pressure - High
g. Automatic Depressurization 1, 2 G SR 3.3.5.1.5 _s322 System High Drywell 2(d), 3(d) SR 3.3.5.1.6 seconds Pressure Bypass rimer
5. ADS Trip System B
a. Reactor Vessel Water Level 1, 2 F SR 3.3.5.1.1 >398 inches

- Low Low Low, Level 1 (e) 2 (d), 3 (d) SR 3.3.5.1.2 above vessel SR 3.3.5.1.5 zero SR 3.3.5.1.6

b. Drywell Pressure High(e) ,2 F 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 (continued)

(d) With reactor steam dome pressure > 150 psig.

(e) During instrument calibrations, if the As Found channel setpoint Is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by Its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. Ifthe As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT 1 3.3-46 Amendment No. 244- 257

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 6 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.1

5. ADS Trip System B (continued)
c. Automatic Depressurization 1, 1 G SR 3.3.5.1.5 _<115 System Initiation Timer 2 (d), 3 (d) SR 3.3.5.1.6 seconds
d. Reactor Vessel Water.Level 1, 1 F SR 3.3.5.1.1 _544 inches

- Low, Level 3 2(d), 3(d) SR 3.3.5.1.2 above vessel (Confirmatory)(e) SR 3.3.5.1.5 zero SR 3.3.5.1.6

e. Core Spray Pump Discharge 1, 4 G SR 3.3.5.1.2 2 175 psig Pressure High 2 (d). 3 (d) SR 3.3.5.1.3 and SR 3.3.5.1.6 < 195 psig
f. Low Pressure Coolant 1, 8 G SR 3.3.5.1.2  ; 90 psig and Injection Pump Discharge 2 (d), 3 (d) SR 3.3.5.1.3 110 psig Pressure - High SR 3.3.5.1.6
g. Automatic Depressurization 1, 2 G SR 3.3.5.1.5 < 322 System High Drywell 2 (d), 3 (d) SR 3.3.5.1.6 seconds Pressure Bypass Timer (d) With reactor steam dome pressure > 150 psig.

(e) During instrument calibrations, ifthe As Found channel setpoint is conservative with respect to the Allowable Value but outside Its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel seipoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT 1 3.3-47 Amendment No. 2-4. 257

RCIC System Instrumentation 3.3.5.2 Table 3.3.5.2-1 (page 1 of 1)

Reactor Core Isolation Cooling System Instrumentation CONDITIONS REQUIRED REFERENCED SURVEILLANCE ALLOWABLE FUNCTION CHANNELS PER FROM REQUIRED REQUIREMENTS VALUE FUNCTION ACTION A.1

1. Reactor Vessel Water Level - 4 B SR 3.3.5.2.1 > 470 inches Low Low, Level 2 (a) SR 3.3.5.2.2 above vessel I SR 3.3.5.2.3 zero SR 3.3.5.2.4
2. Reactor Vessel Water Level - 2 C SR 3.3.5.2.1 < 583 inches High, Level 8 SR 3.3.5.2.2 above vessel.

SR 3.3.5.2.3 zero SR 3.3.5.2.4 (a) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by Its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. Ifthe As Found Instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the Instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report..

BFN-UNIT 1 3.3-51 Amendment No. 2 257

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 1 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.1

1. Main Steam Line Isolation
a. Reactor Vessel Water 1,2,3 2 D SR 3.3.6.1.1  ;Ž 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 1 2 E SR 3.3.6.1.2 !825 psig

- Low(c) SR 3.3.6.1.5 SR 3.3.6.1.6 I 2 per

c. Main Steam Line Flow - 1,2,3 D SR 3.3.6.1.1 :5 140% rated High MSL SR 3.3.6.1.2 steam flow SR 3.3.6.1.5 SR 3.3.6.1.6
d. Main Steam Tunnel 1,2,3 D SR 3.3.6.1.2 s 200OF Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6
2. Primary Containment Isolation
a. Reactor Vessel Water 1,2,3 2 G SR 3.3.6.1.1 '538 inches Level - Low, Level 3 SR 3.3.6.1.2 above vessel SR 3.3.6.1.5 zero SR 3.3.6.1.6
b. Drywell Pressure - High 1,2,3 2 G SR 3.3.6.1.2 :5 2.5 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 1 F SR 3.3.6.1.2 -<90 psi High SR 3.3.6.1.5 SR 3.3.6.1.6
b. HPCI Steam Supply Line 1,2,3 3 F SR 3.3.6.1.2 > 100 psig Pressure - Low SR 3.3.6.1.5 SR 3.3.6.1.6
c. HPCI Turbine 1,2,3 3 F SR 3.3.6.1.2 20 psig Exhaust Diaphragm SR 3.3.6.1.5 Pressure - High SR 3.3.6.1.6 (continued)

(c) During instrument calibrations, ifthe As Found channel setpoint Is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. Ifthe As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference In the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT 1 3.3-58 Amendment No. 234, 257

sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or equipment and instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:

Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 3458 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 296, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

For Surveillance Requirements (SRs) that are new in Amendment 253 to Facility Operating License DPR-52, the first performance is due at the end of the first surveillance interval that begins at implementation of Amendment 253. For SRs that existed prior to Amendment 253, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the surveillance was last performed prior to implementation of Amendment 253.

(3) The licensee is authorized to relocate certain requirements included in Appendix A and the former Appendix B to licensee-controlled documents.

Implementation of this amendment shall include the relocation of these requirements to the appropriate documents, as described in the licensee's Renewed License No. DPR-52 Amendment No. 296

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION D.1

2. Average Power Range Monitors (continued)
d. Inop 1,2 3 (b) G SR 3.3.1.1.16 NA
e. 2-Out-Of-4 Voter 1,2 2 G SR 3.3.1.1.1 NA SR 3.3.1.1.14 SR 3.3.1.1.16
f. OPRM Upscale I 3 (b) I SR 3.3.1.1.1 NA 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 2 G SR 3.3.1.1.1 *51090 psig Pressure - High(d) SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.14
4. Reactor Vessel Water Level - 1,2 2 G SR 3.3.1.1.1 > 528inches Low, Level 3 (d) SR 3.3.1.1.8 above vessel SR 3.3.1.1.13 zero SR. 3.3.1.1.14
5. Main Steam Isolation Valve -1 8 F SR 3.3.1.1.8
6. Drywell Pressure - High 1,2 2 G SR 3.3.1.1.8 < 2.5 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 2 G SR 3.3.1.1.8  : 50 gallons Detector SR 3.3.11.13 SR 3.3.1.1.14 5 (a) 2 H 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.

(d) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by Its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. Ifthe As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 6f the Updated Final Safety Analysis Report.

BFN-UNIT 2 B N3.3-8 Amendment No. 253 254 258 260 296

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 3 of 3)

Reactor Protection System Instrumentation APPLICABLE' CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION D.1

7. Scram Discharge Volume Water Level - High (continued)
b. Float Switch 1,2 2 G SR 3.3.1.1.8 <_46 gallons SR 3.3.1.1.13 SR 3.3.1.1.14 5 (a) 2 H SR 3.3.1.1.8 < 46 gallons SR 3.3.1.1.13 SR 3.3.1.1.14
8. Turbine Stop Valve - Closure 2-30% RTP 4 E SR 3.3.1.1.8 < 10% closed SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15
9. Turbine Control Valve Fast Ž30% .RTP 2 E SR 3.3.1.1.8 > 550 psig Closure, Trip Oil Pressure - SR 3.3.1.1.13 Low(d) SR 3.3.1.1.14 SR 3.3.1.1.15 I
10. Reactor Mode Switch - 1,2 1 G SR 3.3.1.1.12 NA Shutdown Position SR 3.3.1.1.14 5 (a) 1 H SR 3.3.1.1.12 NA SR 3.3.1.1.14
11. Manual Scram 1.2 1 G SR 3.3.1.1.8 NA SR 3.3.1.1.14 5 (a) I H SR 3.3.1.1.8 NA SR 3.3.1.1.14
12. RPS Channel Test Switches 1,2 2 G SR 3.3.1.1.4 NA 5 (a) 2 H SR 3.3.1.1.4 NA
13. Deleted (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(d) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an Initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared Inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that Is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT 2 3.3-9 Amendment No. 259, 276, 296

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 of 6)

Emergency Core Cooling System Instrumentalion APPLICABLE CONDITIONS MODES REQUIRED REFERENCED FUNCTION OR OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER REQUIRED REQUIREMENTS VALUE CONDITIONS FUNCTION ACTION A.1

1. Core Spray System
a. Reactor Vessel Water 1,2,3, 4 (b) B SR 3.3.5.1.1 2!398 inches Level - Low Low Low, 4 (a), 5 (a) SR 3.3.5.1.2 above vessel Level I(e) SR 3.3.5.1.5 zero SR 3.3.5.1.6
b. Drywell Pressure - 1,2,3' 4 (b) B SR 3.3.5.1.2 < 2.5 psig High(e) 'SR 3.3.5.1.5 SR 3.3.5.1.6
c. Reactor Steam Dome 1,2,3 4 (b) C SR 3.3.5.1.2 2 435 psig Pressure - Low (Injection 2 per trip SR 3.3.5.1.4 and Permissive and ECCS system SR 3.3.5.1.6 < 465 psig Initiation)(e) 4 (a), 5 (a) 4 B SR 3.3.5.1.2 2 435 psig 2 per trip SR 3.3.5.1.4 and system SR 3.3.5.1.6 -<465 psig
d. Core Spray Pump 1.2,3, .2 E SR 3.3.5.1.2 a 1647gpm Discharge Flow - Low 4 (a), 5 (a) 1 per SR 3.3.5.1.5 and (Bypass) subsystem *52910 gpm
e. Core Spray Pump Start -

Time Delay Relay Pumps A,B,C,D (with 1,2,3, 4 C SR 3.3.5.1.5 6 seconds diesel power) 4 (a). 5 (a) 1 per pump SR 3.3.5.1.6 and

s 8 seconds Pump A (with normal 1,2,3, 1 C SR 3.3.5.1.5  ;* 0 seconds power) 4 (a). 5 (a) SR 3.3.5.1.6 and

< 1 second Pump B (with normal 1,2,3, 1 C SR 3.3.5.1.5 Zý6 seconds power) 4 (a), 5 (a) SR 3.3.5.1.6 and

< 8 seconds (continued)

(a) When associated subsystem(s) are required to be OPERABLE.

(b) Channels affect Common Accident Signal Logic. Refer to LCO 3.8.1, "AC Sources - Operating.

(e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. Ifthe As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that Is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable..

The nominal Trip Setpoint shall be specified on design output documentation which Isincorporated by reference In the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint. the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT 2 3.3-43 Amendment No.-.5, 296

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 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.1

1. Core Spray System (continued)
e. Core Spray Pump Start -

Time Delay Relay (continued)

Pump C (with normal power) 1,2,3, 1 C SR 3.3.5.1.5 >12 seconds 4 (a) 5 (a) SR 3.3.5.1.6 and

< 16 seconds Pump D (with normal power) 1,2.3, 1 C SR 3.3.5.1.5 > 18 seconds 4 (a), 5 (a) SR 3.3.5.1.6 and

< 24 seconds

2. Low Pressure Coolant Injection (LPCI) System
a. Reactor Vessel Water Level 1,2,3, 4 B SR 3.3.5.1.1 Ž398 inches

- Low Low Low, Level 1 (e) 4 (a), 5 (a) SR SR 3.3.5.1.2 3.3.5.1.5 above vessel zero I.

SR 3.3.5.1.6

b. Drywell Pressure - High(e) 1,2,3 4 B SR 3.3.5.1.2 2.5 psig SR 3.3.5.1.5 SR 3.3.5.1.6
c. Reactor Steam Dome 1,2,3 4 C SR 3.3.5.1.2 Ž:435 psig Pressure - Low (Injection SR 3.3.5.1.4 and Permissive and ECCS SR 3.3.5.1.6 < 465 psig Initiation)(e) 4(8), 5 (a) 4 B SR 3.3.5.1.2 Ž_435 psig SR 3.3.5.1.4 and SR 3.3.5.1.6 5 465 psig (continued)

(a) When associated subsystem(s) are required to be OPERABLE.

(b) Deleted.

(e) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by Its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found Instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is Incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN- UNIT 2 3.3-44 Amendment No.-2-&, 296

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 3 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.1

2. LPCI System (continued)
d. Reactor Steam Dome 1 (c), 2 (c), 4 C SR 3.3.5.1.2 Žt 215 psig Pressure - Low SR 3.3.5.1.4 and (Recirculation Discharge 3 (c) SR 3.3.5.1.6 < 245 psig Valve Permissive)(e) I
e. ReactorVessel Water Level 1,2,3 2 B SR. 3.3.5.1.1  ;Ž 312 5/16

- Level 0 1 per SR 3.3.5.1.2 inches above subsystem SR 3.3.5.1.5 vessel zero SR 3.3.5.1.6

f. Low Pressure Coolant Injection Pump Start -. Time Delay Relay Pump A,B,C,D (with diesel 1,2,3, 4 C SR 3.3.5.1.5 z 0 seconds power) 4 (a), 5 (a) SR 3.3.5.1.6 and

_<1 second Pump A (with normal power) 1,2,3, 1 C SR 3.3.5.1.5 0 seconds 4 (a), 5 (a) SR 3.3.5.1.6 and

_<1 second Pump B (with normal power) 1,2,3, 1 C SR 3.3.5.1.5 Ž6 seconds 4 (a), 5 (a) SR 3.3.5.1.6 and

<_8 seconds Pump C (with normal power) 1,2,3, 1 C SR 3.3.5.1.5 > 12 seconds 4 (a), 5 (a) SR 3.3.5.1.6 and

_<16 seconds Pump D (with normal power) 1,2,3, 1 C SR 3.3.5.1.5 > 18 seconds 4 (a), 5 (a) SR 3.3.5.1.6 and

< 24 seconds (continued)

(a) When the associated subsystem(s) are required to be OPERABLE.

(c) With associated recirculation pump discharge valve open.

(e) During instrument calibrations, ifthe As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by Its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to retuming a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference inthe Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT 2 3.3-45 Amendment No. 253,,289, 296

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 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.1

3. High Pressure Coolant Injection (HPCI) System
a. Reactor Vessel Water Level 1, 4 B SR 3.3.5.1.1 Z-470 inches

- Low Low, Level 2 (e) 2 (d). 3 (d) SR 3.3.5.1.2 above vessel SR 3.3.5.1.5 zero SR 3.3.5.1.6

b. Drywell Pressure - High(e) 1, 4 B SR 3.3.5.1.2 _<2.5 psig 2 (d), 3 (d) SR 3.3.5.1.5 SR 3.3.5.1.6
c. Reactor VesselWater Level 1, 2 C SR 3.3.5.1.1 _<583 inches

- High, Level 8 2 (d), 3 (d) SR 3.3.5.1.2 above vessel SR 3.3.5.1.5 zero SR 3.3.5.1.6

d. Condensate Header Level - 1, 1 D SR 3.3.5.1.2 > Elev. 551 Low 2(d), 3(d) SR 3.3.5.1.3 feet SR 3.3.5.1.6
e. Suppression Pool Water 1, D SR 3.3.5.1.2  :-7 inches Level - High 2 (d), 3 (d) SR 3.3.5.1.3 above SR 3.3.5.1.6 instrument zero
f. High Pressure Coolant 1" 1 E SR 3.3.5.1.2 Ž671 gpm Injection Pump Discharge 2 (d), 3 (d) SR 3.3.5.1.5 Flow - Low (Bypass) SR 3.3.5.1.6
4. Automatic Depressurization System (ADS) Trip System A
a. Reactor Vessel Water Level 1, 2 F SR 3.3.5.1.1 a 398 inches

- Low Low Low, Level 1(e) 2 (d), 3 (d) SR 3.3.5.1.2 above vessel SR 3.3.5.1.5 zero SR 3.3.5.1.6 (continued)

(d). With reactor steam dome pressure > 150 psig.

(e) During instrument calibrations, if the As Found channel setpoint Is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. Ifthe As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpbint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT 2 3.3-46 Amendment No.-2& 296

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.1

4. ADS Trip System A (continued)
b. Drywell Pressure - High(e) 1, F SR 3.3.5.1.2 _<2.5 psig 2(d). 3 (d) SR 3.3.5.1.5 SR 3.3.5.1.6
c. Automatic Depressurization 1, G SR 3.3.5.1.5 -<115 System Initiation Timer 2 (d), 3 (d) SR 3.3.5.1.6 seconds
d. Reactor Vessel Water Level 1, 1 F SR 3.3.5.1.1 - 528 inches

- Low, Level 3 2(d), 3(d) SR 3.3.5.1.2 above vessel (Confirmatory)(e) SR 3.3.5.1.5 zero SR 3.3.5.1.6

e. Core Spray Pump Discharge 1, 4 G SR 3.3.5.1.2 2!175 psig Pressure - High 2 (d), 3 (d) SR 3.3.5.1.3 and SR 3.3.5.1.6 < 195 psig
f. Low Pressure Coolant 1, 8 G SR 3.3.5.1.2 > 90 psig and Injection Pump Discharge. 2 (d) 3 (d) SR 3.3.5.1.3 < 110 psig Pressure - High SR 3.3.5.1.6
g. Automatic Depressurization 1, 2 G SR 3.3.5.1.5 < 322 System High Drywell 2 (d), 3 (d) SR 3.3.5.1.6 seconds Pressure Bypass Timer
5. ADS Trip System B
a. Reactor Vessel Water Level 1, 2 F SR 3.3.5.1.1 Ž398 inches

- Low Low Low, Level 1 (e) 2 (d), 3 (d) SR 3.3.5.1.2 above vessel SR 3.3.5.1.5 zero SR 3.3.5.1.6 (continued)

(d) With reactor steam dome pressure > 150 psig.

(el During Instrument calibrations, If the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by Its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared Inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UN IT2 3.3-47 Amendment No. 253, 2,*- 296

ECCS Instrumentati0n 3.3.5.1 Table 3.3.5.1-1 (page 6 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.1

5. ADS Trip System B (continued)
b. Drywell Pressure - High(e) 1, 2 F SR 3.3.5.1.2 :5 2.5 psig 2 (d) 3 (d) SR 3.3.5.1.5 SR 3.3.5.1.6
c. Automatic Depressurization 1, 1 G SR 3.3.5.1.5 _5115 System Initiation Timer 2 (d), 3 (d) SR 3.3.5.1.6 seconds
d. Reactor Vessel Water Level 1, 1 F SR 3.3.5.1.1 Ž:528 inches

- Low, Level 3 2 (d), 3 (d) SR 3.3.5.1.2 above vessel (Confirmatory) (e) SR 3.3.5.1.5 zero SR 3.3.5.1.6

e. Core Spray Pump Discharge 1, 4 G SR 3.3.5.1.2 Z: 175 psig Pressure - High 2 (d), 3 (d) SR 3.3.5.1.3 and SR 3.3.5.1.6 -<195 psig
f. Low Pressure Coolant 1, 8 G SR 3.3.5.1.2 Ž 90 psig and Injection Pump Discharge 2 (d), 3 (d) SR 3.3.5.1.3 '_5110 psig Pressure - High SR 3.3.5.1.6
g. Automatic Depressurization 1, 2 G SR 3.3.5.1.5 < 322 System High Drywell 2(d), 3(d) SR 3.3.5.1.6 seconds Pressure Bypass Timer (d) With reactor steam dome pressure > 150 psig.

(c) During instrumcnt calibrations, if the As Found channcl sctpoint is conservative with respect to the Allowable Value but outside its-acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared Inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT 2 3.3-48 Amendment No.-2&3, 296

RCIC System Instrumentation 3.3.5.2 Table 3.3.5.2-1 (page 1 of 1)

Reactor Core Isolation Cooling System Instrumentation CONDITIONS REQUIRED REFERENCED SURVEILLANCE ALLOWABLE FUNCTION CHANNELS PER FROM REQUIRED REQUIREMENTS VALUE FUNCTION ACTION A.1

1. Reactor Vessel Water Level - 4 B SR 3.3.5.2.1 >470 inches Low Low, Level 2 (a) SR 3.3.5.2.2 above vessel I SR 3.3.5.2.3 zero SR 3.3.5.2.4
2. Reactor Vessel Water Level 2 C SR 3.3.5.2.1
  • 583 inches High, Level 8 SR 3.3.5.2.2 above vessel SR 3.3.5.2.3 zero SR 3.3.5.2.4 (a) During instrument calibrations, if the As Found channel setpoint Is conservative with respect to the Allowable Value but outside Its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. Ifthe As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpolnt design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT 2 3.3-52 Amendment No.-253 296

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 1 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.1

1. Main Steam Line Isolation
a. Reactor Vessel Water .1,2,3 2 D SR 3.3.6.1.1 Ž398 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 2 E SR 3.3.6.1.2 2:825 psig

- Low(c) SR 3.3.6.1.5 SR 3.3.6.1.6 I 2 per

c. Main Steam Line Flow - 1.2,3 D SR 3.3.6.1.1 <5140% rated High MSL SR 3.3.6.1.2 steam flow SR 3.3.6.1.5 SR 3.3.6.1.6
d. Main Steam Tunnel 1,2,3 8 D SR 3.3.6.1.2  ! 200°F Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6
2. Primary Containment Isolation
a. Reactor Vessel Water 1,2.3 2 G SR 3.3.6.1.1 > 528 Inches Level - Low, Level 3 SR 3.3.6.1.2 above vessel SR 3.3.6.1.5 zero SR 3.3.6.1.6
b. Drywell Pressure - High 1,2,3 2 G SR 3.3.6.1.2 :5 2.5 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 1 F SR 3.3.6.1.2 < 90 psi High SR 3.3.6.1.5 SR 3.3.6.1.6
b. HPCI Steam Supply Line 1,2,3 3 F SR 3.3.6.1.2 >100psig Pressure - Low SR 3.3.6.1.5 SR 3.3.6.1.6
c. HPCI Turbine 1,2,3 3 F SR 3.3.6.1.2 < 20 psig Exhaust Diaphragm SR 3.3.6.1.5 Pressure - High SR 3.3.6.1.6 (continued)

(c) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

'BFN-UNIT 2 3.3-59 Amendment No. 253, .26, 296

(3) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use at any time any byproduct, source, and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess, and use in amounts as required any byproduct, source, or special nuclear material without restriction to chemical or physical form for sample analysis or equipment and instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I:

Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 3458 megawatts thermal.

(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 254, except for Amendment No. 248, are hereby incorporated in the renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

For Surveillance Requirements (SRs) that are new in Amendment 212 to Facility Operating License DPR-68, the first performance is due at the end of the first surveillance interval that begins at implementation of the Amendment 212. For SRs that existed prior to Amendment 212, including SRs with modified acceptance criteria and SRs whose frequency of performance is being extended, the first performance is due at the end of the first surveillance interval that begins on the date the surveillance was last performed prior to implementation of Amendment 212.

Renewed License No. DPR-68 Amendment No. 254

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 2 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION D.1

2. Average Power Range Monitors (continued)
d. Inop 1,2 3 (b) G SR 3.3.1.1.16 NA
e. 2-Out-Of-4 Voter 1,2. 2 G SR 3.3.1.1.1 NA SR 3.3.1.1.14 SR 3.3.1.1.16
f. OPRM Upscale 1 3 (b) I SR 3.3.1.1.1 NA 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 2 G SR 3.3.1.1.1 _<1090 psig Pressure - High(d) SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.14
4. Reactor Vessel Water Level 1,2 2 G SR 3.3.1.1.1 _ 528 inches Low, Level 3 (d) SR 3.3.1.1.8 above vessel SR 3.3.1.1.13 zero SR 3.3.1.1.14
5. Main Steam Isolation Valve - 1 8 F SR 3.3.1.1.8  :* 10% dosed Closure SR 3.3.1.1.13 SR 3.3.1.1.14
6. Drywell Pressure - High 1,2 2 G SR 3.3.1.1.8 < 2.5 psig SR 3.3.1.1.13 SR 3.3.1.1.14 Volume
7. Scram Discharge Water Level - High
a. Resistance Temperature 1,2 2 G SR 3.3.1.1.8 < 50 gallons Detector SR 3.3.1.1.13 SR 3.3.1.1.14 5 (a) 2 H SR 3.3.1.1.8 .<q 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.

(d) During instrument calibrations, ifthe As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated Iey reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT 3 3.3-8 Amendment No 212213 214 219221 254

RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 3 of 3)

Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION D.1

7. Scram Discharge Volume Water Level - High
b. Float Switch 1,2 2 G SR 3.3.1.1.8 :5 46 gallons SR 3.3.1.1.13 SR 3.3.1.1.14 5 (a) 2 H SR 3.3.1.1.8 :5 46 gallons SR 3.3.1.1.13 SR 3.3.1.1.14
8. Turbine Stop Valve - Closure - 30% RTP 4 E SR 3.3.1.1.8 <_10% closed SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15
9. Turbine Control Valve Fast 2:30% RTP 2 E SR 3.3.1.1.8 550 psig Closure, Trip Oil Pressure - SR 3.3.1.1.13 Low(d) SR 3.3.1.1.14 SR 3.3.1.1.15 I
10. Reactor Mode Switch - 1,2 1 G SR 3.3.1.1.12 NA Shutdown Position SR 3.3.1.1.14 5 (a) 1 H.. SR 3.3.1.1.12 NA SR 3.3.1.1.14
11. Manual Scram 1,2 1 G SR 3.3.1.1.8 NA SR 3.3.1.1.14 5 (a) 1 H SR 3.3.1.1.8 NA SR 3.3.1.1.14
12. RPS Channel Test Switches 1,2 2 G SR 3.3.1.1.4 NA 5 (a) 2 H SR 3.3.1.1.4 NA
13. Deleted (a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

(d) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. Ifthe As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT 3 3.3-9 Amendment No. 212 213 221 235 254

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 1 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.1

1. Core Spray System
a. Reactor Vessel Water Level 1,2,3. 4 (b) B SR 3.3.5.1.1 2 398 inches

- Low Low Low, Level 1(f) 4 (a) 5 (a) SR SR 3.3.5.1.2 3.3.5.1.5 above vessel zero .1 SR 3.3.5.1.6

b. Drywell Pressure - High(f) 1,2,3 4 (b) B SR 3.3.5.1.2 £52.5 psig SR 3.3.5.1.5 SR 3.3.5.1.6
c. Reactor Steam Dome 1,2,3 4 (b) C SR 3.3.5.1.2 Z:435 psig and Pressure - Low (Injection 2 per trip SR 3.3.5.1.4 5 465 psig Permissive and ECCS system SR 3.3.5.1.6 Initiation)()

4 (a) 5 (a) 4 B SR 3.3.5.1.2 2 435 psig and 2 per trip SR 3.3.5.1.4 < 465 psig system SR 3.3.5.1.6

d. Core Spray Pump Discharge 1,2,3, 2 E SR 3.3.5.1.2 > 1647 gpm Flow-Low (Bypass) 4 (a), 5 (a) 1 per SR 3.3.5.1.5 and subsystem < 2910 gpm
e. Core Spray Pump Start -

Time Delay Relay Pumps A,B,C,D (with diesel 1,2,3, 4 C SR 3.3.5.1.5 > 6 seconds power) 4 (a), 5 (a) I per pump SR 3.3.5.1.6 and

< 8 seconds Pump A (with normal power) 1,2,3, 1 C SR 3.3.5.1.5 > 0 seconds 4 (a), 5 (a) SR 3.3.5.1.6 and

5 1 second Pump B (with normal power) 1,2,3, 1 C SR 3.3.5.1.5 > 6 seconds 4 (a), 5 (a) SR 3.3.5.1.6 and 5 8 seconds (continued)

(a) When associated subsystem(s) are required to be OPERABLE.

(b) Channels affect Common Accident Signal Logic. Refer to LCO 3.8.1, *AC Sources - Operating."

(f) During instrument calibrations, If the As Found channel setpoint is conservative with respect to the Allowable Value but outside Its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an Initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the Instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which Is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-LýNIT 3 3.3-43 Amendment No.-94--,254

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 2 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.1

1. Core Spray System (continued)
e. Core Spray Pump Start-Time Delay Relay (continued)

Pump C (with normal power) 1,2,3, 1 C SR 3.3.5.1.5 > 12 seconds 4 (a), 5 (a) SR 3.3.5.1.6 and

16 seconds Pump D (with normal power) 1,23. 1 C SR 3.3.5.1.5 a 18 seconds 4 (a) 5 (a) SR 3.3.5.1.6 and
<24 seconds
2. Low Pressure Coolant Injection (LPCI) System
a. Reactor Vessel Water Level 1,2,3, 4 B SR 3.3.5.1.1 Ž 398 inches

-Low Low Low, Level 1(f) 4 (a), 5 (a) SR 3.3.5.1.2 above vessel SR 3.3.5.1.5 zero SR 3.3.5.1.6

b. Drywell Pressure - Hightf) 1,2,3 4 B SR 3.3.5.1.2 <2.5 psig SR 3.3.5.1.5 SR 3.3.5.1.6
c. Reactor Steam Dome 1,2.3 4 C SR 3.3.5.1.2 > 435 psig and Pressure-- Low (Injection SR 3.3.5.1.4 5 465 psig Permissive and ECCS SR 3.3.5.1.6 Initiation)(f) 4 (a), 5 (a) 4 B SR 3.3.5.1.2 Ž435 psig and SR 3.3.5.1.4 :5465 psig SR 3.3.5.1.6 (continued)

(a) When associated subsystem(s) are required to be OPERABLE.

(b) Deleted.

(f) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which Is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT.3 3.3-44 Amendment No.-243-,254

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 3 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.1

2. LPCI System (continued)
d. Reactor Steam Dome 1 (c),2(c), 4 C SR 3.3.5.1.2 *a215 psig Pressure - Low 3 (c) SR 3.3.5.1.4 and :s 245 psig (Recirculation Discharge SR 3.3.5.1.6 Valve Permissive)(f I
e. Reactor Vessel Water Level 1,2.3 2 SR 3.3.5.1.1 2!312 5/16 Level 0 1 per SR 3.3.5.1.2 Inches above subsystem SR 3.3.5.1.5 vessel zero SR 3.3.5.1.6
f. Low Pressure Coolant Injection Pump Start -Time Delay Relay Pump A,B,C,D (with diesel 1,2,3, 4 C SR 3.3.5.1.5 Ž0 seconds power) 4 (a), 5 (a) SR 3.3.5.1.6 and

!51 second Pump A (with normal power) 1,2,3, 1 C SR 3.3.5.1.5 > 0 seconds 4 (a). 5 (a) SR 3.3.5.1.6 and

51 second

£ 8 seconds Pump C (with normal power) 1.2,3, 1 C SR 3.3.5.1.5 2t12 seconds 4 (a), 5 (a) SR 3.3.5.1.6 and

5 16 seconds Pump D (with normal power) 1,2,3, 1 C SR 3.3.5.1.5 a 18 seconds 4 (a), 5 (a) SR 3.3.5.1.6 and

_<24 seconds (continued)

(a) When the associated subsystem(s) are required to be OPERABLE.

(c) With associated recirculation pump discharge valve open.

(1) During instrument calibrations, Ifthe As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. Ifthe As Found instrument channel setpoint Is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that Is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design 0Otput documentation.shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT 3 . 3.3-45 \ Amendment No.-243-,254

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 4 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.1

3. High Pressure Coolant Injection (HPCI) System.
a. Reactor Vessel Water Level 1, 4 B SR 3.3.5.1.1 > 470 in'ches

- Low Low, Level 2(0 2 (d) 3 (d) SR 3.3.5.1.2 above vessel SR 3.3.5.1.5 zero SR 3.3.5.1.6

b. Drywell Pressure - High(f) 1, B SR 3.3.5.1.2 s 2.5 psig 2(d),3(d) SR 3.3.5.1.5 SR 3.3.5.1.6
c. Reactor Vessel Water Level 1, 2 C SR 3.3.5.1.1 _ 583 inches High, Level 8 2 (d), 3 (d) SR 3.3.5.1.2 above vessel SR 3.3.5.1.5 zero SR 3.3.5.1.6
d. Condensate Header Level - 1, 1 D SR 3.3.5.1.2 Ž Elev. 551 Low 2 (d), 3 (d) SR 3.3.5.1.3 feet SR 3.3.5.1.6
e. Suppression Pool Water 1, D SR 3.3.5.1.2 _<7 inches Level - High 2 (d). 3 (d) SR 3.3.5.1.3 above SR 3.3.5.1.6 instrument zero
f. High Pressure Coolant 1, E SR 3.3.5.1.2 Ž:671 gpm Injection Pump Discharge 2 (d), 3 (d) SR 3.3.5.1.5 Flow-Low (Bypass) SR 3.3.5.1.6
4. Automatic Depressurization System (ADS) Trip System A
a. Reactor Vessel Water Level 1, 2 F SR 3.3.5.1.1 Ž398 inches Low Low Low. Level 1(0 2 (d) 3 (d) SR 3.3.5.1.2 above vessel SR 3.3.5.1.5 zero SR 3.3.5.1.6 (continued)

(d) With reactor steam dome pressure > 150 psig.

(f) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside Its acceptable As Found band as defined by Its associated Surveillance Requirement procedure, then there shall bean initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT 3 3.3-46 Amendmrent No.-244r-1254

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.1

4. ADS Trip System A (continued) 2 F SR 3.3.5.1.2 < 2.5 psig
b. Drywell Pressure - High(O 2(d).1,3 (d) SR 3.3.5.1.5 SR 3.3.5.1.6
c. Automatic Depressurization 1, 1 G SR 3.3.5.1.5 :5 115 seconds System Initiation Timer 2 (d), 3 (d) SR 3.3.5.1.6
d. Reactor Vessel Water Level 1, 1 F SR 3.3.5.1.1 2 528 inches

- Low, Level 3 2 (d), 3 (d) SR 3.3.5.1.2 above vessel (Confirmatory)(f) SR 3.3.5.1.5 zero SR 3.3.5.1.6

e. Core Spray Pump Discharge 1, 4 G SR 3.3.5.1.2 2 175 psig and Pressure - High 2 (d) 3 (d) SR 3.3.5.1.3 < 195 psig SR 3.3.5.1.6
f. Low Pressure Coolant 1, 8 G SR 3.3.5.1.2 2: 90 psig and Injection Pump Discharge 2 (d) 3 (d) SR 3.3.5.1.3 < 110 psig Pressure - High SR 3.3.5.1.6
g. Automatic Depressurization .1, 2 G SR 3.3.5.1.5 5 322 seconds System High Drywell 2(d), 3(d) SR 3.3.5.1.6 Pressure Bypass Timer
5. ADS Trip System B
a. Reactor Vessel Water Level 1, 2 F SR 3.3.5.1.1  ; 398 inches

- Low Low Low, Level 1(0 2 (d), 3 (d) SR 3.3.5.1.2 above vessel SR 3.3.5.1.5 zero SR 3.3.5.1.6 (continued)

(d) With reactor steam dome pressure > 150 psig.

(f) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by Its associated Surveillance Requirement procedure, then there shall be an Initial determination to ensure confidence that the channel can perform as required before returning the channel to service In accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared Inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference inthe Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT 3 3.3-47 Amendment No. 212, 213, 219, 254

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 6 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.1

5. ADS Trip System B (continued)
b. Drywell Pressure - High(f) 1, 2 F SR 3.3.5,1.2 *s2.5 psig 2 (d), 3 (d)

SR 3.3.5.1.5 SR 3.3.5.1.6

c. Automatic Depressurization 1, 1 G SR 3.3.5.1.5 < 115 seconds System Initiation Timer 2 (d) 3 (d) SR 3.3.5.1.6
d. Reactor Vessel Water Level 1, 1 F SR 3.3.5.1.1 z: 528 inches

- Low, Level 3 2(d) 3(d) SR 3.3.5.1.2 above vessel (Confirmatory(O) SR 3.3.5.1.5 zero SR 3.3.5.1.6

e. Core Spray Pump Discharge 1, 4 G SR 3.3.5.1.2 2:175 psig and Pressure - High 2 (d). 3 (d) SR 3.3.5.1.3 < 195 psig SR 3.3.5.1.6
f. Low Pressure Coolant 1, 8 G SR 3.3.5.1.2 k 90 psig and Injection Pump Discharge 2 (d), 3 (d) SR '3.3.5.1.3
g. Automatic Depressurization 1, 2 G SR 3.3.5.1.5 -<322 seconds System High Drywell 2(d) 3(d) SR 3.3.5.1.6 Pressure Bypass Timer (d) With reactor steam dome pressure > 150 psig.

(i) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared Inoperable.

Prior to returning a channel to service, the Instrument channel setpolnt shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified In Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT 3 .3.3-48 Amendment No.-21-3-, 254

RCIC System Instrumentation 3.3.5.2 Table 3.3.5.2-1 (page 1 of 1)

Reactor Core Isolation Cooling System Instrumentation CONDITIONS REQUIRED REFERENCED SURVEILLANCE ALLOWABLE FUNCTION CHANNELS PER FROM REQUIRED REQUIREMENTS VALUE FUNCTION ACTION A.1

1. Reactor Vessel Water Level - B SR 3.3.5.2.1 Ž:470 inches Low Low, Level 2 (a) SR 3.3.5.2.2 above vessel I SR 3.3.5.2.3 zero SR 3.3.5.2.4
2. Reactor Vessel Water Level - 2 C SR 3.3.5.2.1 < 583 inches High, Level 8 SR 3.3.5.2.2 above vessel SR 3.3.5.2.3 zero SR 3.3.5.2.4 (a) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. Ifthe As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint; otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-.UNIT 3 3.3-52 Amendment No. 254

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 1 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.1

1. Main Steam Line Isolation
a. Reactor Vessel Water 1.2,3 2 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 1 2 E SR 3.3.6.1.2 > 825 psig Low(c) SR 3.3.6.1.5 SR 3.3.6.1.6 I
c. Main Steam Line Flow - 1,2,3 2 per D SR 3.3.6.1.1 < 140% rated High MSL SR 3.3.6.1.2 steam flow SR 3.3.6.1.5 SR 3.3.6.1.6
d. Main Steam Tunnel 1,2,3 "8 D SR 3.3.6.1.2 < 200OF Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.6
2. Primary Containment Isolation
a. Reactor Vessel Water 1,2,3 .2 G SR 3.3.6.1.1 S528 inches Level - Low, Level 3 SR 3.3.6.1.2 above vessel SR 3.3.6.1.5 zero SR 3.3.6.1.6
b. Drywell Pressure !. High 1,2,3 2 G SR 3.3.6.1.2 < 2.5 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 1 F SR 3.3.6.1.2 90 psi

-High SR 3.3.6.1.5 SR 3.3.6.1.6

b. HPCI Steam Supply Line 1,2,3 3 F SR 3.3.6.1.2  : 100 psig Pressure - Low SR 3.3.6.1.5 SR 3.3.6.1.6
c. HPCI Turbine 1,2,3 3 F 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)

(c) During instrument calibrations, if the As Found channel setpoint is conservative with respect to the Allowable Value but outside its acceptable As Found band as defined by its associated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channel can perform as required before returning the channel to service in accordance with the Surveillance. If the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to returning a channel to service, the instrument channel setpoint shall be calibrated to a value that is within the acceptable As Left tolerance of the setpoint: otherwise, the channel shall be declared inoperable.

The nominal Trip Setpoint shall be specified on design output documentation which is incorporated by reference in the Updated Final Safety Analysis Report. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT,3 3.3-59 Amendment No. 212, 213, 219, 254

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