ML062630096

Tech Spec Pages for Amendment 258, Regarding Allowable Value for Reactor Vessel Water Level (TS-434)

ML062630096
Person / Time
Site:	Browns Ferry
Issue date:	09/18/2006
From:	NRC/NRR/ADRO/DORL/LPLII-2
To:
Chernoff M, NRR/DORL, 415-4041
Shared Package
ML062630002	List: ML062140111 ML062630096
References
TAC MC2305
Download: ML062630096 (8)

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 1:

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 Sl~ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment 'No. 258,' 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 Amendment No.. 258

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 Monitors (continued)

d. Downscale 1 2 F SR 3.3.1.1.7 >-3% 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 G SR 3.3.1.1.1 !S1055 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 2!528 inches I 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 IF SR 3.3.1.1.8 :510% 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 Water Level - High

a. Resistance Temperature 1,2 2 G SR 3.3.1.1.8 ý550 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 assocated Surveillance Requirement procedure, then there shall be an initial determination to ensure confidence that the channof can perform as required before retumning the channel to service in accordance with the Surveillance. If the As Found in strument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to retumning 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 BEN-NIT1 33-7Amendment No. 234, 257 258

E.COS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 5 of 6)

Emergency Care 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 SIR 3.3.5.1.2 :5 2.5 psig SR 3.3.5.1.5 2 (d), 3 (d)

SR 3.3.5.1.6

c. Automatic Depressurization 1, G SIR 3.3.5.1.5 :5115 System Initiation Timer SR 3.3.5.1.6 seconds 2 (d), 3 (d)

d. Reactor Vessel Water Level 1, F SIR 3.3 .5.1.1 ýt528 inches I

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

SR 3.3.5.1.6

e. Core Spray Pump Discharge 4 G SIR 3.3.5.1.2 Ž-175 psig Pressure - High SIR 3.3.5.1.3 and 1, SR 3.3.5.1.6 <- 95 psig 2 (d), 3 (d) .8

f. Low Pressure Coolant G SIR 3.3.5.1.2 Žý90 psig and Injection Pump Discharge SIR 3.3.5.1.3 5 110 psig Pressure - High SIR 3.3.5.1.6 2 (d), 3 (d)

g. Automatic Depressurization 2 G SIR 3.3.5.1.5 :5 322 System High Drywell SR 3.3.5.1.6 seconds Pressure Bypass Timer 1,

5. ADS Trip System B (d),

2 3 (d)

a. Reactor Vessel Water Level 2 F SIR 3.3.5.1.1 2ý398 inches

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

b. Drywell Pressure - High(e) 2 F SIR 3.3.5.1.2 :5 2.5 psig SR 3.3.5.1.5 SR 3.3.5.1.6 (d) With reactor steam dome pressure > 150 psig.(cniud (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 3.3-46 BFN-NIT1 No. 234, 25:7, 258 3.-46Amendment

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 1I G SR 3.3.5.1.5 :5115 System Initiation Timer 2 (d), 3 (d) SIR 3.3.5.1.6 seconds

d. Reactor Vessel Water Level 1, 1 F SIR 3.3.5.1.1 Ž528 ince

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

a. Core Spray Pump Discharge 1, 4 G SIR 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 SIR 3.3.5.1.2 2:90 psig and Injection Pump Discharge 2 (d), 3 (d) SIR 3.3.5.1.3 < 110psig Pressure - High SIR 3.3.5.1.6

g. Automatic Depressurization 1. 2 G SIR 3.3.5.1.5 :5322 System High Drywell 2()()SIR 3.3.5.1.6 seconds Pressure Bypass Timer 2 d, 3 d (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 retumning the channel to service in accordance with the Surveillaince, if the As Found instrument channel setpoint is not conservative with respect to the Allowable Value, the channel shall be declared inoperable.

Prior to retumning 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 3.3-47 BEN-NITI No. 234, 257, 258 3.-47Amendment

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 1 of 31)

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 CA1

1. Main Steam Line Isolation

a. Reactor Vessel Water 1,2,3 2 D SR 3.3.6.1.1 Žt398 inches Level - Low Low Low, SR -3.3.6.1.2 above vessel Level 1 SR 3.3.6.1.5 zero SIR 3.3.6.1.6

b. Main Steam Line Pressure 1 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

c. Main Steam Line Flow - 1,2,3 2 per 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 8 D SR 3.3.6.1.2 5 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 2:528 inches I 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 :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 F SR 3.3.6.1.2 :5 90 psi High SR 3.3.6.1.5 1 SR 3.3.6.1.6

b. HPCI Steam Supply Line 1.2.3 F SR 3.3.6.1.2 k 100 psig Pressure - Low SR 3.3.6.1.5 3 SR 3.3.6.1.6

c. HPCI Turbine 1.2,3 F SR 3.3.6.1.2 ,q20 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. 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 Selpoint. the predefined As Found Tolerance, and the As Left Tolerance band, and a listing of the setpoint design output documentation shall be specified inChapter 7 of the Updated Final Safety Analysis Report.

BFN-UNIT I 3.3-58 BFNUNI I3.358AmendmenF No. 3-q2A -.

n-r72058

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1 -1 (page 3 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 CA1

5. Reactor Water Cleanup (RWCU) System Isolation

a. Main Steam Valve Vault 1,2.3 2 F SR 3.3.6.1.2 :5201*F Area Temperature - High SR 3.3.6.1.4 SR 3.3.6.1.6

b. Pipe Trench Area 1,2,3 2 F SR 3.3.6.1.2 !5135*F Temperature - High SR 3.3.6.1.4 SR 3.3.6.1.6

c. Pump Room A Area 1,2,3 2 F SR 3.3.6.1.2 *5152*F Temperature - High SR 3.3.6.1.4 SR 3.3.6.1.6

d. Pump Room B Area 1,2,3 2 F SR 3.3.6.1,2 :5 152*F Temperature - High SR 3.3.6.1.4 SR 3.3.6.1.6

e. Heat Exchanger Room 1.2,3 2 F SR 3.3.6.1.2 :5 143*F Area (West Wall) SR 3.3.6.1.4 Temperature - High SR 3.3.6.1.6

f. Heat Exchanger Room 1.2.3 2 F SR 3.3.6.1.2 :5 170*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)

H SR 3.3.6.1.6 NA

h. Reactor Vessel Water 1,2,3 2 F SR 3,3.6.1.1 Ž!528 inches I SR 3.3.6.1.2 above vessel Level - Low, Level 3 SR 3.3.6.1.5 zero SR 3.3.6.1.6

6. Shutdown Coaling System Isolation

a. Reactor Steam Dome 1.2,3 F SR 3.3.6.1.2 :5 115 psig Pressure - High SR 3.3.6.1.5 SR 3.3.6.1.6

b. Reactor Vessel Water 3A45 1 SR 3.3.6.1.1 2: 528 Inches 2 (b) I 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

c. Drywell Pressure - High 1.2,3 2 F SR 3.3.8.1.2 :52.5 psig SR 3.3.6.1.5 SR 3.3.6.1.6 (a) One SLO: System Initiation signal provides logic input to clise both RWCU valves.

(b) Only one channel per trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.

BFN-UNIT 1 - 3.3-60 BFN-NIT1 3.-60Amendment No.-234-; 258

Secondary Containment Isolation Instrumentation 3.3.6.2 Table 3.3.6.2-1 (page 1 of 1)

Secondary Containment Isolation Instrumentation APPLICABLE MODES OR REQUIRED FUNCTION OTHER CHANNELS SURVEILLANCE ALLOWABLE SPECIFIED PER REQUIREMENTS VALUE CONDITIONS TRIP SYSTEM

1. Reactor Vessel Water Level - 1,2A3 2 SR 3.3.6.2.1 Ž:528 inches I Low, Level 3 (a) SR 3.3.6.2.2 above vessel zero SR 3.3.6.2.3 SR 3.3.6.2.4

2. Drywell Pressure - High 1,2,3 2 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, 1 SR 3.3.6.2.1 :5 100 mRlhr Radiation - High (a) SR 313.6.2.2 SR 3.3.6.2.3 SIR 3.3.6.2.4

4. Refueling Floor Exhaust 1.2,3, 1 SR 3.3.6.2.1 *5100 mR/hr Radiation - High (a) SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.4 (a) During operations with a potential for draining the reactor vessel.

BFN-UNIT 1 3.3-64 BEN-NITI 3.-64Amendment No. 234, 251, 258

CREV System Instrumentation 3.3.7.1 Table 3.3.7.1-1 (page 1 of 1)

Control Room Emergency Ventilation System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED FUNCTION OTHER CHANNELS FROM SURVEILLANCE ALLOWABLE SPECIFIED PER TRIP REQUIRED REQUIREMENTS VALUE CONDITIONS SYSTEM ACTION A.1

1. Reactor Vessel Water Level - 1,2,3,(a) 2 B SR 3.3.7.1.1 2!528 inches I Low, Level 3 SR 3.3.7.1.2 above vessel SR 3.3.7.1.5 zero SR 3.3.7.1.6

2. Drywell Pressure - High 1,2,3 *2 B SR 3.3.7.1.2 <52.5 psig SR 3.3.7.1.5 SR 3.3.7.1.6

3. Reactor Zone Exhaust 1,2,3 1 C SR 3.3.7.1.1 *5 100 mRlhr Radiation - High (a) 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, 1 C SR 3.3.7.1.1 :5100 mR/hr Radiation - High (a) SR 3.3.*7.1.2 SIR 3.3.7.1.5 SR 3.3.7.1.6

5. Control Room Air Supply Dtict 1,2,3, 1 D SR 3.3.7.1.1 *5270 cpm Radiation - High (a) 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.

BFN-UNIT 1 3.3-69 BFN-NIT1 3.-69Amendment No. 234, 251, 258