ML062500173

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Technical Specifications Change TS-453 - Instrument Setpoint Program - Supplement 1
ML062500173
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 09/05/2006
From: O'Grady B
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MC5920, TAC MC9518, TAC MC9519, TVA-BFN-TS-453S1
Download: ML062500173 (35)
v • d • e


Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 Brian O'Grady Vice President, Browns Ferry Nuclear Plant September 5, 2006 TVA-BFN-TS-453S1 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop: OWFN P1-35 Washington, D.C. 20555-0001 Gentlemen:

In the Matter of )) Docket Nos. 50-259 Tennessee Valley Authority 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) UNITS 1, 2, AND 3 -

TECHNICAL SPECIFICATIONS (TS) CHANGE TS-453 - INSTRUMENT SETPOINT PROGRAM - SUPPLEMENT 1 (TAC NOS. MC9518, MC9519, AND MC9520)

On January 10, 2006, TVA submitted a license amendment (TS-453) (ADAMS Accession No. ML060180452) for Licenses DPR-33, DPR-52, and DPR-68 for BFN Units 1, 2, and 3, respectively.

TS-453 adds provisions into the TS for specifying the methodology used for determining, setting, and evaluating as-found setpoints for instruments necessary to ensure compliance with a Safety Limit and for selected instruments, which are important in ensuring the fuel peak cladding temperature acceptance criterion is met. The purpose of including this information in the TS is to control critical instrument setpoints and to ensure compliance with 10 CFR 50.36 with respect to reactor core Safety Limits.

The NRC staff subsequently via teleconference requested that TVA modify the submitted TS change as described in Enclosure

1. In regard to the proposed supplemental change in , it is TVA's understanding this change will not prevent TVA from modifying the affected trip setpoints subject to evaluations under the regulatory requirements of 10 CFR 50.59. TVA requests this concord be included in the NRC safety evaluation for this TS amendment.

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U.S. Nuclear Regulatory Commission Page 2 September 5, 2006 TVA requests this amendment be approved expeditiously and that the implementation of this revised TS be within 90 days of NRC approval. The 90 day period is necessary due to the large number of surveillance requirement procedures that require revision in order to implement this change.

TVA has determined this supplemental change does not change the determination in the January 10, 2006, TS-453 submittal that there are no significant hazards considerations associated with the proposed change and that the TS change qualifies for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22(c) (9). provides TVA's evaluation of the proposed supplemental changes. Enclosure 2 provides a mark-up of the revised TS changes. Enclosure 3 provides a summary of the revised regulatory commitments associated with this TS change submittal.

If you have any questions about this amendment, please contact William D. Crouch (256) 729-2636.

I declare under penalty of perjury that the foregoing is true and correct. Executed on September 5, 2006.

Sincerely, Brian 0' y

Enclosures:

1. TVA Evaluation of the Proposed Supplemental TS Change
2. Proposed Technical Specifications - Supplemental Change (mark-up)
3. List of Regulatory Commitments

U.S. Nuclear Regulatory Commission Page 3 September 5, 2006 Enclosures cc (Enclosures):

State Health Officer Alabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 303017 Montgomery, AL 36130-3017 U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 Mr. Stephen J. Cahill, Branch Chief U.S. Nuclear Regulatory Commission Region II Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW, Suite 23T85 Atlanta, Georgia 30303-8931 NRC Senior Resident Inspector Browns Ferry Nuclear Plant 10833 Shaw Road Athens, AL 35611-6970 Margaret Chernoff, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)

One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739 Eva A. Brown, Project Manager U.S. Nuclear Regulatory Commission (MS 08G9)

One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852-2739

Enclosure 1 Browns Ferry Nuclear Plant (BFN) Units 1, 2, and 3 Technical Specifications (TS) Change TS-453SI Instrument Setpoint Program TVA Evaluation of Proposed Supplemental TS Change

1.0 DESCRIPTION

On January 10, 2006, TVA submitted a license amendment (TS-453)

(ADAMS Accession No. ML060180452) for Licenses DPR-33, DPR-52, and DPR-68 for BFN Units 1, 2, and 3, respectively. TS-453 adds provisions into the TS for specifying the methodology used for determining, setting, and evaluating as-found setpoints for instruments necessary to ensure compliance with a Safety Limit and for selected instruments, which are important in ensuring the fuel peak cladding temperature acceptance criterion is met. The purpose of including this information in the TS is to control critical instrument setpoints and to ensure compliance with 10 CFR 50.36 with respect to reactor core Safety Limits.

The NRC staff subsequently via teleconference requested that TVA modify the proposed TS change in TS-453 as described below. In regard to proposed supplemental change, it is TVA's understanding this supplemental change will not prevent TVA from modifying the affected trip setpoints subject to evaluations under the regulatory requirements of 10 CFR 50.59. TVA requests this agreement be included in the NRC safety evaluation for this TS amendment.

TVA requests the amendment be approved expeditiously in order to allow the processing of the other associated proposed TS changes and that the implementation of the revised TS be within 90 days of NRC approval.

2.0 PROPOSED CHANGE

The proposed change in TS-453 affects selected drift susceptible instruments, which are either necessary to ensure compliance with a reactor Safety Limit or are important in ensuring fuel peak cladding temperature acceptance criterion of 10 CFR 50.46 is met.

In the January 10, 2006, TS-453 submittal, a footnote was proposed to be added to the TS instrument function tables that specifies the actions to be taken for the applicable as-found instrument setpoints and references the NRC-approved TVA setpoint

methodology. Specifically, in TS-453 TVA proposed the addition of following footnote to the earmarked instrument functions as follows:

"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. The methodology used to determine the nominal Trip Setpoint, the predefined As Found Tolerance, and the As Left Tolerance band shall be specified in Chapter 7 of the Updated Final Safety Analysis Report."

NRC staff subsequently via teleconference requested that TVA modify the last paragraph of the proposed footnote to that shown next:

"The nominal Trip Setpoint shall be specified on design output documentation. 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."

Accordingly, we have revised the January 10, 2006, TS-453 change to incorporate the revised footnote as shown in Enclosure 2.

The placement of the modified footnote is at the same locations as in the January 10, 2006, submittal. For TVA documentation purposes, this proposed supplemental change is referred to as TS-453S1.

NRC also requested that the associated TS Bases for the instrument functions where the footnote is being added be modified to state that the trip setpoint, including the as-left tolerances, is defined as the Limiting Safety System Setting.

TVA will make the TS Bases change in accordance with TS 5.5.10, "Technical Specifications (TS) Bases Control Program," during the

BFN implementation of TS-353S1. A commitment to this effect is provided in Enclosure 3 as commitment No. 3.

Commitment No. 2 from the January 10, 2006, TS-453 submittal is revised to reflect the proposed change in the footnote above.

Commitment No. 1 from the January 10, 2006, TS-453 submittal is being withdrawn in that TVA considers that, with incorporation of this supplemental TS change, the end objectives of TSTF-493 have been satisfied and, likewise, TVA has satisfied the intent of NRC Regulatory Issue Summary 2006-017, "NRC Staff Position on the Requirements of 10 CFR 50.36, "Technical Specifications,"

Regarding Limiting Safety System Settings During Periodic Testing and Calibration of Instrument Channels," dated August 24, 2006.

Refer to Enclosure 3 for a listing of the revised commitments.

Enclosure 2 Browns Ferry Nuclear Plant (BFN) Units 1, 2, and 3 Technical Specifications (TS) Change TS-453S1 Instrument Setpoint Program Proposed Technical Specification Supplemental Changes (mark-up)

The following footnote will be added where indicated "INSERT FOOTNOTE" on the attached BFN Unit 1, 2, and 3 TS pages:

"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. 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."

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. Downscale 1 F SR 3.3.1.1.7 2:3% RTP SR 3.3.1.1.8 SR 3.3.1.1.14
e. Inop 1,2 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 -<1055 psig Pressure - Hig SR 3.3.1.1.8 SR 3.3.1.1.10 I SR 3.3.1.1.14
4. Reactor VesWater Level - 1,2 G SR 3.3.1.1.1 > 538inches Low, Level 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 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 G SR 3.3.1.1.8 5 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 G SR 3.3.1.1.8 _<50 gallons Detector SR 3.3.1.1.13 SR 3.3.1.1.14 5 (a) H SR 3.3.1.1.8 <_50 gallons SR 3.3.1.1.13 SR 3.3.1.1.14
b. Float Switch 1,2 G SR 3.3.1.1.8 < 50 gallons SR 3.3.1.1.13 SR 3.3.1.1.14 5 (a) 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.

F I

(d) INSERT FOOTNOTE BFN-UNIT 1 3.3-7 3,, Aedmn Amendment No. 234 No 3 m I

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

Reactor Piotection 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

8. Turbine Stop Valve - Ž30% RTP 4 E SR 3.3.1.1.8 _*10% closed Closure SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15
9. Turbine Control Valve Fast >30% RTP 2 E SR 3.3.1.1.8 550 psig CIu Trip Oil Pressure - SR 3.3.1.1.13 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 (d)

(a)

INSERT FOOTNOTE With any control rod withdrawn from a core cell containing one or more fuel assemblies.

BFN-UNIT 1 3.3-8 Amendment No. 234

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 > 398 inches Level -,Jow Low Low, 4 (a), 5 (a) SR 3.3.5.1.2 above vessel Level 1 Ue SR 3.3.5.1.5 zero SR 3.3.5.1.6
b. Dry.APressure 1,2,3 4 (b) B SR 3.3.5.1.2 !5 2.5 psig Higte SR 3.3.5.1.5 SR 3.3.5.1.6 I
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 Permissiv nd ECCS system SR 3.3.5.1.6 < 465 psig Initiation)Z,) I 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 > 1647 gpm Discharge Flow - Low 4 (a), 5 (a) 1 per SR 3.3.5.1.5 and (Bypass) subsystem < 2910 gpm
e. Core Spray Pump Start -

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

< 8 seconds Pump A (with normal 1,2A3, 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 ?6 seconds power) 4 (a), 5 (a) SR 3.3.5.1.6 and s 8 seconds Pump C (with normal 1,2.3, I C SR 3.3.5.1.5 > 12 seconds power) 4 (a), 5 (a) SR 3.3.5.1.6 and

< 16 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."

I (e) INSERT FOOTNOTE I I BFN-UNIT 1 3.3-42 Amendment No. 234

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

!5 24 seconds

2. Low Pressure Coolant Injection (LPCI) System
a. Reactor Vessel Water Leyl 1.2,3, 4 B SR 3.3.5.1.1 > 398 inches

- Low Low Low, Level 1W) 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 - Hige 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 Pressure - Low (Injection SR 3.3.5.1.4 and Permissiynd ECCS SR 3.3.5.1.6 <_465 psig Initiatior jn) 4 B SR 3.3.5.1.2 > 435 psig I

SR 3.3.5.1.4 and SR 3.3.5.1.6 _<465 psig

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 DiscD~ge 3 (c)

SR 3.3.5.1.6 5 245 psig I Valve PermissiveFe)

e. Reactor Vessel Water Level 1,2,3 2 B SR 3.3.5.1.1 ;Ž 312 5116

- 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 (continued)

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

(b) Deleted.

(c) With associated recirculation pump discharge valve open.

I (e) INSERT FOOTNOTE II BFN-UNIT 1 3.3-43 Amendment No. 234

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)
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 > 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 > 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 -a12 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

3. High Pressure Coolant Injection (HPCI) System
a. Reactor Vessel WatLevel 1, 4 B SR 3.3.5.1.1 Ž470 inches

- Low Low, Level 20i 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)

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

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

I (e) INSERT FOOTNOTE I I BFN-UNIT 1 3.3-44 Amendment No.-2-4 7, 250 April 1, 2004

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. HPCI System (continued)
b. Drywell Pressure - HighO 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 Vessel Water Level 1, 2 C SR 3.3.5.1.1 < 583 inches (d) SR 3.3.5.1.2 above vessel

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

d. Condensate Header Level - 1, D SR 3.3.5.1.2 > Elev. 551 Low (d), 3 (d)

SR 3.3.5.1.3 feet 2

SR 3.3.5.1.6

e. Suppression Pool Water 1, D SR 3.3.5.1.2 _<7 inches Level - High (d) SR 3.3.5.1.3 above 2 (d), 3 SR 3.3.5.1.6 instrument zero
f. High Pressure Coolant 1, E SR 3.3.5.1.2 _ 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 > 398 inches (d) SR 3.3.5.1.2 above vessel Low Low Low, Level le* 2 (d), 3 SR 3.3.5.1.5 zero SR 3.3.5.1.6
b. Drywell Pressure - Highe 1, 2 F SR 3.3.5.1.2 _<2.5 psig SR 3.3.5.1.5 2 (d), 3 (d)

SR 3.3.5.1.6

c. Automatic Depressurization 1, 1 G SR 3.3.5.1.5 cnn115 System Initiation Timer (d) SR 3.3.5.1.6 seconds 2 (d), 3 (continued)

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

I (e) INSERT FOOTNOTE I BFN-UNIT 1 3.3-45 Amendment No. 234

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)
d. Reactor Vessel Water Level 1, F SR 3.3.5.1.1 > 544 inches

- Low, Level 3 (d) SR 3.3.5.1.2 above vessel 2 (d). 3 (Confirmatory0 SR 3.3.5.1.5 zer SR 3.3.5.1.6

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

- Low Low Low, Level 1lk ) 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 - HighS 1, F SR 3.3.5.1.2 -<2.5 psig (d), 3 (d)

SR 3.3.5.1.5 2

SR 3.3.5.1.6

c. Automatic Depressurization 1, G SR 3.3.5.1.5 _ 115 System Initiation Timer SR 3.3.5.1.6 2 (d), 3 (d) seconds
d. Reactor Vessel Water Level 1, F SR 3.3.5.1.1 > 544 inches

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

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

(e) INSERT FOOTNOTE I

BFN-UNIT 1 3.3-46 Amendment No. 234

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 Wajr Level - 4 B SR 3.3.5.2.1 > 470 inches Low Low, Level a0 SR 3.3.5.2.2 above vessel 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 1 (a) INSERT FOOTNOTE I

BFN-UNIT 1 3.3-51 Amendment No. 234

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  ? 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 Lin 1 2 E SR 3.3.6.1.2 2 825 psig Pressure - Lob 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 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 !52001F 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 2 538 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)

I (c) INSERT FOOTNOTE BFN-UNIT 1 3.3-58 Amendment No. 234

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 1
f. OPRM Upscale 3 (b) 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 Sm Dome 1,2 2 G SR 3.3.1.1.1 < 1090 psig Pressure - Higl,) SR 3.3.1.1.8 SR 3.3.1.1.10 I SR 3.3.1.1.14
4. Reactor VessWater Level - 1.2 2 G SR 3.3.1.1.1 ý 528 inches Low, Level SR 3.3.1.1.8 above vessel SR 3.3.1.1.13 I zero SR 3.3.1.1.14
5. Main Steam Isolation Valve - 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 _s2.5 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 3.3.1.1.13 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.

(b) Each APRM channel provides inputs to both trip systems.

I (d) INSERT FOOTNOTE I BFN-UNIT 2 3.3-8 Amendment No. 253, 251, 25, 260 August 16, 1999

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 - > 30% RTP 4 E SR 3.3.1.1.8 < 10% closed Closure SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15
9. Turbine Control Valve Fast >30% RTP 2 E SR 3.3.1.1.8 >550 psig Close, Trip Oil Pressure - SR 3.3.1.1.13 Lov*2," SR 3.3.1.1.14 I

SR 3.3.1.1.15

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) INSERT FOOTNOTE BFN-UNIT 2 3.3-9 Amendment No. 2-58, 276 April 08, 2002

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 1,2A3 4 (b)

B SR 3.3.5.1.1 _ 398 inches Level -A,,w Low Low, 4 (a), 5 (a) SR 3.3.5.1.2 above vessel Level 1*,2i SR 3.3.5.1.5 zero SR 3.3.5.1.6

b. DryvTJPressure High--

- 1,2,3 4 (b)

B SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6

< 2.5 psig I

c. Reactor Steam Dome 1,2,3 4 (b) C SR 3.3.5.1.2 _>435 psig Pressure - Low (Injection 2 per trip SR 3.3.5.1.4 and Permissivnd ECCS system SR 3.3.5.1.6 5 465 psig Initiation e) I 4(a), 5(a) 4 B SR 3.3.5.1.2 Ž 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 > 1647 gpm Discharge Flow - Low 4 (a), 5 (a) 1 per SR 3.3.5.1.5 and (Bypass) subsystem < 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 2!6 seconds diesel power) 4 (a), 5 (a) 1 per pump SR 3.3.5.1.6 and

_58 seconds Pump A (with normal 1,2.3, 1 C SR 3.3.5.1.5 2t 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 > 6 seconds power) 4 (a), 5 (a) SR 3.3.5.1.6 and 1

_<16 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."

I (e) INSERT FOOTNOTE I I BFN-UNIT 2 3.3-43 Amendment No. 253

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 D (with normal power) 1,2,3, 1 C SR 3.3.5.1.5 Ž 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 Ley. 1,2,3, 4 B SR 3.3.5.1.1 > 398 inches

- Low Low Low, Level 1b,)) 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 - HighO 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 Pressure - Low (Injection SR 3.3.5.1.4 and Permissiv.gnd ECCS SR 3.3.5.1.6 <465 psig Initiationj), I 4 (a), 5 (a) 4 B SR 3.3.5.1.2 _435 psig SR 3.3.5.1.4 and SR 3.3.5.1.6 <465 psig
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 Discrge 3(c) SR 3.3.5.1.6 5 245 psig Valve Permissive)%,l
e. Reactor Vessel Water Level 1,2,3 2 B SR 3.3.5.1.1 > 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 (continued)

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

(b) Deleted.

(c) With associated recirculation pump discharge valve open.

1(e) INSERT FOOTNOTE BFN-UNIT 2 3.3-44 Amendment No. 253

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)
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 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  ;>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 > 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 -a18 seconds 4 (a), 5 (a) SR 3.3.5.1.6 and

< 24 seconds

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

- Low Low, Level 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)

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

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

(e) INSERT FOOTNOTE I I BFN-UNIT 2 3.3-45 Amendment No.-243- 289 April 1, 2004

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. HPCI System (continued)
b. Drywell Pressure - Hig "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 Vessel Water Level 1, 2 C SR 3.3.5.1.1 < 583 inches

- High, Level 8 (d), 3 (d)

SR 3.3.5.1.2 above vessel 2

SR 3.3.5.1.5 zero SR 3.3.5.1.6

d. Condensate Header Level - 1, D SR 3.3.5.1.2 -eElev. 551 Low (d), 3 (d)

SR 3.3.5.1.3 feet 2

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 -e671 gpm Injection Pump Discharge (d), 3 (d)

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

b. Drywell Pressure - HighO 1, 2 F SR 3.3.5.1.2 :5 2.5 psig (d) SR 3.3.5.1.5 2 (d), 3 SR 3.3.5.1.6
c. Automatic Depressurization 1, 1 G SR 3.3.5.1.5 _<115 System Initiation Timer (d), 3 (d) SR 3.3.5.1.6 seconds 2

(continued)

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

(e) INSERT FOOTNOTE I BFN-UNIT 2 3.3-46 Amendment No. 253

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)
d. Reactor Vessel Water Level 1, 1 F SR 3.3.5.1.1  ; 528 inches

- Low, Level 3 (d) SR 3.3.5.1.2 above vessel 2 (d), 3 (Confirmatory)QO , 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 > 175 psig Pressure - High 2(d). 3 (d) SR 3.3.5.1.3 and SR 3.3.5.1.6 s 195 psig
f. Low Pressure Coolant 1, 8 G SR 3.3.5.1.2 2t 90 psig and Injection Pump Discharge (d) SR 3.3.5.1.3 _5110 psig Pressure - High 2 (d), 3 SR 3.3.5.1.6
g. Automatic Depressurization 1, 2 G SR 3.3.5.1.5 < 322 System High Drywell (d) SR 3.3.5.1.6 seconds Pressure Bypass Timer 2 (d), 3
5. ADS Trip System B
a. Reactor Vessel Water Le;I 1, 2 F SR 3.3.5.1.1 > 398 inches (d) SR 3.3.5.1.2 above vessel

- Low Low Low, Level 1 2 (d), 3 SR 3.3.5.1.5 zero SR 3.3.5.1.6

b. Drywell Pressure - High . 1, 2 F SR 3.3.5.1.2 s 2.5 psig (d) SR 3.3.5.1.5 2 (d), 3 SR 3.3.5.1.6
c. Automatic Depressurization 1, G SR 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, I 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)O SR 3.3.5.1.5 zero SR 3.3.5.1.6 (continued)

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

I(e) INSERT FOOTNOTE BFN-UNIT 2 3.3-47 Amendment No. 2-53, 260 August 16, 1999

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 WZr Level - 4 B SR 3.3.5.2.1 _ 470 inches Low Low, Level kay SR 3.3.5.2.2 above vessel 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

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 'a398 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 1 2 E SR 3.3.6.1.2 > 825 psig SR 3.3.6.1.5 Pressure - Lovo I SR 3.3.6.1.6 2 per
c. Main Steam Line Flow - 1,2,3 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 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 > 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 < 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 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)

I (c) INSERT FOOTNOTE I

BFN-UNIT 2 3.3-59 Amendment No. 2-53, 260 August 16, 1999

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 Range

2. Average Power
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) 1 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 ,@ Dome 1,2 2 G SR 3.3.1.1.1 _<1090 psig Pressure - Higk SR 3.3.1.1.8 SR 3.3.1.1.10 I SR 3.3.1.1.14
4. Reactor VessWater Level - 1,2 2 G SR 3.3.1.1.1 ý 528 inches Low, Level U 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% 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 <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 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) INSERT FOOTNOTE I I BFN-UNIT 3 3.3-8 Amendment No. 221 212, 213, 214, 219 September 27, 1999

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 _<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 - g 30% RTP 4 E SR 3.3.1.1.8 < 10% closed Closure SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.15
9. Turbine Control Valve Fast 2t 30% RTP 2 E SR 3.3.1.1.8 > 550 psig Closjjw, Trip Oil Pressure - SR 3.3.1.1.13 Loj,*d) SR 3.3.1.1.14 I

SR 3.3.1.1.15

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) INSERT FOOTNOTE BFN-UNIT 3 3.3-9 Amendment No. 212, 2.1.3, -224, 235 April 08, 2002

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 Le I 1.2,3, 4 (b) B SR 3.3.5.1.1 > 398 inches 4 (a), 5 (a) SR 3.3.5.1.2 above vessel

- Low Low Low, Level 0 SR 3.3.5.1.5 zero SR 3.3.5.1.6 1,2,3 4 (b) B SR 3.3.5.1.2 < 2.5 psig

b. Drywell Pressure - HighO 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 > 435 psig and Pressure - Low (Injection 2 per trip SR 3.3.5.1.4 < 465 psig Permissivlnd 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 >Ž1647 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 2 6 seconds power) 4 (a), 5 (a) 1 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 2! 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 > 6 seconds 4 (a) 5 (a) SR 3.3.5.1.6 and

< 16 seconds (continued)

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

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

S(0) INSERT FOOTNOTE BFN-UNIT 3 3.3-43 Amendment No. 213 September 03, 1998

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 D (with normal power) 1,2,3A I C SR 3.3.5.1.5 e 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 LeI 1,2,3, 4 B SR 3.3.5.1.1 _ 398 inches 4 (a), 5 (a) SR 3.3.5.1.2 above vessel

- Low Low Low, Level 75 SR 3.3.5.1.5 zero SR 3.3.5.1.6

b. Drywell Pressure - Higle 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 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 InitiationI)1 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

>_215 psig

d. Reactor Steam Dome I (c), 2 (c), 4 C SR 3.3.5.1.2 Pressure - Low SR 3.3.5.1.4 and < 245 psig 3 (c)

(Recirculation Discp4ýrge SR 3.3.5.1.6 Valve Permissive) V2,

e. Reactor Vessel Water Level 1,2,3 2 B SR 3.3.5.1.1 312 5116

- 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 (continued)

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

(b) Deleted.

(c) With associated recirculation pump discharge valve open.

(1) INSERT FOOTNOTE I

BFN-UNIT 3 3.3-44 Amendment No. 213 September 03, 1998

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)
f. Low Pressure Coolant Injection Pump Start -Time Delay Relay Pump A,B,C,D (with diesel 1,2A3, 8 (e) C SR 3.3.5.1.5 Ž 0 seconds power) 4 (a), 5 (a) SR 3.3.5.1.6 and

< 1 second Pump A (with normal power) 1,2A3, 2 C SR 3.3.5.1.5 >0 seconds 4 (a), 5 (a) 1 per trip SR 3.3.5.1.6 and system

  • 1 second Pump B (with normal power) 1,2,3, 2 C SR 3.3.5.1.5 2 6 seconds 4 (a), 5 (a) 1 per trip SR 3.3.5.1.6 and system < 8 seconds Pump C (with normal power) 1,2,3, 2 C SR 3.3.5.1.5  ? 12 seconds 4 (a), 5 (a) 1 per trip SR 3.3.5.1.6 and system < 16 seconds Pump D (with normal power) 1,2,3, 2 C SR 3.3.5.1.5 > 18 seconds 4 (a), 5 (a) 1 per trip SR 3.3.5.1.6 and system < 24 seconds
3. High Pressure Coolant Injection (HPCI) System
a. Reactor Vessel Wate,.Level 1. 4 SR 3.3.5.1.1 > 470 inches

- Low Low, Level 219 (d), 3 (d) SR 3.3.5.1.2 above vessel 2

SR 3.3.5.1.5 zero SR 3.3.5.1.6 (continued)

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

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

(e) Pumps A, B, C, and D have 2 relays each (1 per trip system).

m INSERT FOOTNOTE I

BFN-UNIT 3 3.3-45 Amendment No. 213 September 03, 1998

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. HPCI System (continued)
b. Drywell Pressure - Higo 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 Vessel Water Level 1. 2 C SR 3.3.5.1.1 5 583 inches

-High Level 8 2(d), 3 (d) SR SR 3.3.5.1.2 3.3.5.1.5 above vessel 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, 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 2!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 Ž!398inches

- Low Low Low, Level 1Q,) 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 - Higl 2 1, 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
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 (continued)

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

(f) INSERT FOOTNOTE BFN-UNIT 3 3.3-46 Amendment No. 213 September 03, 1998

ECCS Instrumentation 3.3.5.1 Table 3.3.5.1-1 (page 5 of 6)

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

4. ADS Trip System A (continued)
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) 0 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 > 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 > 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 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 Lev 1, 2 F SR 3.3.5.1.1 Ž_398 inches

- Low Low Low. Level,,, 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- Higho 1, 2 F SR 3.3.5.1.2
  • 2.5 psig b

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 > 528inches

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

(f)

(d)

INSERT FOOTNOTE With reactor steam dome pressure> 150 psig.

BFN-UNIT 3 3.3-47 Amendment No. 242*2123, 219 August 16, 1999

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 Wr Level - 4 B SR 3.3.5.2.1 > 470 inches Low Low, Level -ap SR 3.3.5.2.2 above vessel 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) INSERT FOOTNOTE BFN-UNIT 3 3.3-52 Amendment No. 213 September 03, 1998

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 > 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 Lin 2 E SR 3.3.6.1.2 > 825 psig Pressure - Lo4t SR 3.3.6.1.5 SR 3.3.6.1.6 I 1,2,3
c. Main Steam Line Flow - 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 1,2,3
d. Main Steam Tunnel 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 > 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 _<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 F SR 3.3.6.1.2 < 90 psi High SR 3.3.6.1.5 3 SR 3.3.6.1.6
b. HPCI Steam Supply Line 1,2,3 F SR 3.3.6.1.2 2>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 !520 psig Exhaust Diaphragm SR 3.3.6.1.5 Pressure - High SR 3.3.6.1.6 BFN-UNIT 3 3.3-59 Amendment No. 2!2, 213, 219 August 16, 1999

Enclosure 3 Browns Ferry Nuclear Plant (BFN) Units 1, 2, and 3 Technical Specifications (TS) Change TS-453SI Instrument Setpoint Program List of Revised Regulatory Commitments

1. Commitment Retracted - TVA will evaluate the final Technical Specification Task Force change related to resolution of the setpoint issue within 90 days after its approval by the NRC.
2. Revised Commitment - The nominal Trip Setpoint shall be specified on design output documentation. 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. New Commitment - The TS Bases for the instrument functions for which the footnote is being added in this license amendment will be modified to state that the trip setpoint, including the as-left tolerances, is defined as the Limiting Safety System Setting. The Bases change will be made during implementation of this the TS change in accordance with TS 5.5.10, "Technical Specifications (TS) Bases Control Program."
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