ML062610166

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Technical Specifications Change TS-453 - Instrument Setpoint Program - Supplement 2 (TAC Nos. MC9518, MC9519, & MC9520)
ML062610166
Person / Time
Site: Browns Ferry  
Issue date: 09/14/2006
From: Crouch W
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
TAC MC9518, TAC MC9519, TAC MC9520, TVA-BFN-TS-453S2
Download: ML062610166 (35)
v • d • e


Text

Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 September 14, 2006

,TVA-BFN-TS-453S2 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 2 (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 proposed TS change in TS-453.

TVA responded to the NRC request via letter (TS-453 Supplement 1) dated September 5, 2006.

In a follow-up teleconference, the NRC staff again requested that TVA modify the proposed TS change in TS-453 and TS-453 Supplement 1. This requested revision is in.

So03b

U.S. Nuclear Regulatory Commission Page 2 September 14, 2006 In regard to the proposed Supplemental TS 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.

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.

Encl'osure 2 provides a mark-up of the revised TS changes. 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.14th, 2006.

Sincerely, William D. Crouch Manager of Licensing And Industry Affairs

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 14, 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. Malcolm T.

Widmann, 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

U.S. Nuclear Regulatory Commission Page 4 September 14, 2006 DTL:BCM:BAB Enclosures cc (w/o Enclosures):

B. M. Aukland, POB 2C-BFN M. Bajestani, NAB 1A-BFN A.

S. Bhatnagar, LP 6A-C J.

C.

Fornicola, LP 6A-C R.

G. Jones, POB 2C-BFN G. V. Little, NAB lD-BFN R.

F. Marks, PAB 1A-BFN G. W. Morris, BR 4X-C B.

J. O'Grady, PAB 1E-BFN K. W. Singer, LP 6A-C P.

D. Swafford, LP 6A-C E.

J. Vigluicci, WT 6A-K NSRB Support, LP 5M-C EDMS WT CA-K s:lic/submit/TechSpec/TS-453 Instrument Setpoint Program Supplement2.doc Browns Ferry Nuclear Plant (BFN) Units 1, 2, and 3 Technical Specifications (TS)

Change TS-453S2 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.

TVA responded to the NRC request via letter in TS-453 Supplenment 1 (TS-453SI) dated September 5, 2006.

In a follow-up teleconference, the NRC staff again requested that TVA modify the proposed TS change in TS-453 and TS-453S1 as described below.

In regard to proposed TS

change, 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 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 and the September 5, 2006 Supplement a footnote was proposed to be added to the TS instrument function tables that specifies the actions to be taken I

for the applicable as-found instrument setpoints and references the NRC-approved TVA setpoint methodology.

In TS-453S1 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, and a listing of the setpoint design output documentation 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 in TS-453S1 to that shown next:

"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 6utput documentation shall be specified in Chapter 7 of the Updated Final Safety Analysis Report."

Accordingly, we have revised the TS 453S1 change to incorporate the revised footnote as shown in Enclosure 2.

The placement of the modified footnote is at the same locations asinl the January 10, 2006,and the TS-453S1 submittals.

For TVA documentation purposes, this proposed supplemental change is referred to as TS-453S2.

Refer to Enclosure 3 for a listing of the commitments.

2 Browns Ferry Nuclear Plant (BFN) Units 1, 2, and 3 Technical Specifications (TS)

Change TS-453S2 Instrument Setpoint Program Proposed Technical Specification Supplemental Changes (mark-up)

The following footnote will be added at the "INSERT FOOTNOTE" locations 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 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."

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 OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED CONDITIONS SYSTEM ACTION D.1 SURVEILLANCE ALLOWABLE REQUIREMENTS VALUE FUNCTION

2. Average Power Range Monitors (continued)
d. Downscale
e. Inop
3. Reactor Vessel Steam Dome Pressure - Hi s
4. Reactor Ve;Water Level-Low, Level dj
5.

Main Steam Isolation Valve -

Closure

6.

Drywell Pressure - High

7. Scram Discharge Volume Water Level - High
a. Resistance Temperature Detector
b.

Float Switch 1,2 1,2 1,2 1,2 1.2 5 (a) 1.2 5(a)

F SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.14 G

SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.14 G

SR 3.3.1.1.1 SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.14 G

SR 3.3.1.1.1 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 F

SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 G

SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14

_z 3% RTP NA s 1055 psig 538 inches above vessel zero

!5 10% closed

5 2.5 psig

< 50 gallons 5 50 gallons

< 50 gallons

!5 50 gallons (continued)

G H

G H

SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 (a)

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

(d)

INSERT FOOTNOTE BFN-UNIT 1 3.3-7 Amendment No. 234

RPS Instrumentation 3.3.1.1 Tabte 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

8. Turbine Stop Valve -

2 30% RTP 4

E SR 3.3.1.1.8 s 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 2! 30% RTP 2

E SR 3.3.1.1.8 2! 550 psig

CloI, Trip Oil Pressure -

SR 3.3.1.1.13 Lo

.d SR 3.3.1.1,14 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 (a)

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

(d) INSERT FOOTNOTE I

BFN-UNIT 1 3.3-8 Amendment No. 234

ECCS Instrumentation 3.3.5.1 Table 3.3.51-1 (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 -. Lw Low Low.

Level 1AJJ

b. Dryw*Pressure High*,j
c.

Reactor Steam Dome Pressure - Low (Injection Permissiv' nd ECCS Initiation)()

d. Core Spray Pump Discharge Flow - Low (Bypass)
e.

Core Spray Pump Start -

Time Delay Relay Pumps AB,C,D (with diesel power)

Pump A (with normal power)

Pump B (with normal power)

Pump C (with normal power) 1,2,3, 4(a), 5(a) 1,2,3 1.2.3 4(a), 5(a) 1,2,3.

4 (a), 5(a) 4(b) 4 (b) 4 (b) 2 per trip system 4

2 per trip system 2

1 per subsystem 4

1 per pump B

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 B

SSR SR SR C

SR SR SR B

SSR SR SR 3.3.5.1.2 3.3.5.1.5 3.3.5.1.6 3.3.5.1.2 3.3.5.1.4 3.3.5.1.6 3.3.5.1.2 3.3.5.1.4 3.3.5.1.6

_> 398 inches above vessel zero

< 2.5 psig Zt 435 psig and

!< 465 psig Z! 435 psig and

< 465 psig I

1,2,3, 4(a), 5(a) 1,2,3, 4 (a), 5(a) 1,2,3.

4 (a), 5(a) 1.2.3, 4(a). 5(a) 1 E

SR 3.3.5.1.2 2! 1647 gpm SR 3.3.5.1.5 and s 2910 gpm SR 3 3.5.1.5 2! 6 seconds SR 3.3.5.1.6 and

5 8 seconds C

SR 3.3.5.1.5

>_ 0 seconds SR 3.3.5.1.6 and is 1 second C

SR 3.3.5.1.5

- 6 seconds SR 3.3.5.1.6 and s 8 seconds C

SR 3.3.5.1.5

> 12 seconds SR 3.3.5.1.6 and

_< 16 seconds 1

(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

E 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)

2.

Low Pressure Coolant Injection (LPCI) System

a. Reactor Vessel Water Le]l

- Low Low Low, Level

b. Drywell Pressure - Higl-
c. Reactor Steam Dome Pressure - Low (Injection PermissiWnd ECCS Initiatiorkj,)
d. Reactor Steam Dome Pressure - Low (Recirculation DisSarge Valve Permissive) U,,2
e. Reactor Vessel Water Level

- Level 0 1,2,3, 4 (a), 5(a) 1 C

SR 3.3.5.1.5

> 18 seconds SR 3.3.5.1.6 and

< 24 seconds 1.2.3, 4 (a), 5 (a) 1,2.3 1,2,3 4 (a) 5(a) 1 (0,2(c),

3(c) 4 4

4 4

4 B

SR 3.3.5.1.1 SR 3.3 5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 B

SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 C

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 B

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3 5.1.6 C

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 B

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6

> 398 inches above vessel zero

!< 2.5 psig

_ 435 psig and s 465 psig a 435 psig and

< 465 psig

> 215 psig and S 245 psig I

1.2,3 2

1 per subsystem

Ž: 312 5/16 inches above vessel zeroi (continued)

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

(b) Deleted.

(c)

With associated recirculation pump discharge valve open.

(e) INSERT FOOTNOTE I

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 AB,C,D (with diesel 1.2,3.

4 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) 1,2,3, 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 2! 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

> 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

> 470 inches

- Low Low, Level 2'*)

2 (d) 3 (d)

SR 3.3.5.1.2 above vessell 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 J

BFN-UNIT 1 3.3-44 Amendment No.-234, 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
c.

Reactor Vessel Water Level

- High, Level 8

d. Condensate Header Level -

Low

e. Suppression Pool Water Level - High
f.

High Pressure Coolant Injection Pump Discharge Flow - Low (Bypass)

4. Automatic Depressurization System (ADS) Trip System A
a. Reactor Vessel Water Level

- Low Low Low, Level 10

b.

Drywell Pressure - Higlt

c. Automatic Depressurization System Initiation Timer 1,

2(d),3(d) 1, 2 (d), 3 (d) 1.

2(d). 3(d) 1, 2 (d), 3(d) 1, 2(d). 3(d) 4 2

B SR SR SR C

SR SR SR SR D

SR SR SR D

SSR SR SR E

SSR SR SR 3.3.5.1.2 3.3.5.1.5 3.3.5.1.6 3.3.5.1.1 3.3.5.1.2 3.3.5.1.5 3.3.5.1.6 3.3.5.1.2 3.3.5.1.3 3.3.5.1.6 3.3.5.1.2 3.3.5.1.3 3.3.5.1.6 3.3.5.1.2 3.3.5.1.5 3.3.5.1.6

!5 2.5 psig

< 583 inches above vessel zero

> Elev. 551 feet

< 7 inches above instrument zero

> 671 gpm 1,'

2(d), 3(d) 1, 2 (d), 3 (d) 1, 2 (d), 3 (d) 2 2

F SSR SR SR SR F

SR SR SR 3.3.5.1.1 3.3.5.1.2 3.3.5.1.5 3.3.5.1.6 3.3.5.1.2 3.3.5.1.5 3.3.5.1.6

_> 398 inches above vessel zero

< 2.5 psig 1

G SR 3.3.5.1.5 SR 3.3.5.1.6

<115 seconds (continued)

(d)

With reactor steam dome pressure > 150 psig.

(e) INSERT FOOTNOTE 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

- Low, Level 3 (Confirmatory

e. Core Spray Pump Discharge Pressure - High
f.

Low Pressure Coolant Injection Pump Discharge Pressure - High

g. Automatic Depressurization System High Drywell Pressure Bypass Timer
5. ADS Trip System B
a. Reactor Vessel Water L§

- Low Low Low, Level 1i(ej

b.

Drywell Pressure - HighQ

c. Automatic Depressurization System Initiation Timer d

Reactor Vessel Water Level

- Low, Level 3 (Confirmatory)o 1,

2 (d), 3(d) 1, 2(d), 3 (d) 1, 2 (d), 3(d) 1, 2 (d), 3(d) 1, 2 (d), 3 (d) 1, 2 (d), 3(d) 1, 2 (d), 3 (d) 1, 2 (d), 3 (d) 1 4

8 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 G

SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 G

SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 Z:544 inches above vessel zero Z 175 psig and

5 195 psig zt 90 psig and

! 110 psig 2

G SR 33.5.1.5 5 322 SR 3 3.5.1.6 seconds 2

2 F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 F

SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6

_ 398 inches above vessel zero

< 2.5 psig 1

G SR 3.3.5.1.5

_ 115 SR 3.3.5.1.6 seconds F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 544 inches above vessel zero (continued)

(d)

With reactor steam dome pressure > 150 psig I (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 War Level -

4 B

SR 3.3.5.2.1

_>470 inches Low Low. Level 2 a 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 Level - Low Low Low, Level I
b. Main Steam Line Pressure - LowO
c.

Main Steam Line Flow -

High

d. Main Steam Tunnel Temperature - High
2. Primary Containment Isolation
a. Reactor Vessel Water Level - Low, Level 3
b. Drywell Pressure - High
3. High Pressure Coolant Injection (HPCI) System Isolation
a. HPCI Steam Line Flow -

High

b. HPCI Steam Supply Line Pressure - Low
c.

HPCI Turbine Exhaust Diaphragm Pressure - High 1.2.3 1

1,2.3 1.2.3 2

2 2 per MSL 8

D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 E

SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 D

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 D

SR 33.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 G

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 G

SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

_> 398 inches above vessel zero

> 825 psig

< 140% rated steam flow

_< 2001F 1,2.3 1,2.3 2

2

> 538 inches above vessel zero s 2.5 psig 1.2,3 1,2,3 1.2,3 1

3 F

SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3 6.1.6 F

SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F

SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

_< 90 psi

> 100 psig

_< 20 psig (continued)

I (c)

INSERT FOOTNOTE I

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

e. 2-Out-Of-4 Voter
f. OPRM Upscale
3.

Reactor Vessel Steam Dome Pressure - Higl,,

4.

Reactor VesssWater Level -

Low, Level

5.

Main Steam Isolation Valve -

Closure

6.

Drywell Pressure - High

7. Scram Discharge Volume Water Level - High
a. Resistance Temperature Detector 1.2 1,2 1,2 3(b) 2 3 (b) 2 G

SR 3.3.1.1.1 SR 3.3.1.1.14 SR 3.3.1.1.16 1

SR 3.3.1.1.1 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16 SR 3.3.1.1.17 G

SR 3.3.1.1.1 SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.14 G

SR 3.3.1.1.1 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 NA NA

!5 1090 psig z! 528 inches above vessel zero 5 10% closed 5 2.5 psig G

SR 3.3.1.1.16 NA 1.2 1

1,2 2

8 2

I F

SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 G

SR 3.3.1.1.8 SR 33.1.1.13 SR 3.3.1.1.14 G

SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 H

SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 1.2 2

s 50 gallons s 50 gallons 5 (a) 2 (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, 254, 258, 260 August 16, 1999

RPS Instrumentation 3.3.1.1 Table 3.3 11-1 (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 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 -

>- 30% RTP 4

E SR 3.3.1.1.8 5 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 Lob" SR 3.3.1.1.14 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 Level -,w Low Low, Level 1W
b. Dw Pressure -

High

c.

Reactor Steam Dome Pressure - Low (Injection Permissivl nd ECCS InitiationA(,e)

d.

Core Spray Pump Discharge Flow - Low (Bypass)

e. Core Spray Pump Start Time Delay Relay Pumps A,B.C,D (with diesel power)

Pump A (with normal power)

Pump B (with normal power)

Pump C (with normal power) 1,2,3.

4 (a), 5(a) 1,2,3 4(b) 4(b)

B SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 B

SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 C

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 B

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6

_> 398 inches above vessel zero

< 2.5 psig

Ž 435 psig and

< 465 psig

_Ž 435 psig and

< 465 psig I

1,2,3 4 (b) 2 per trip system 4(a), 5(a) 4 2 per trip system I

1,2,3, 4(a), 5(a) 2 1 per subsystem 4

1 per pump 1,2,3, 4(a), 5(a) 1,2,3, 4 (a), 5 (a) 1,2,3, 4 (a), 5(a) 1,2,3, 4 (a), 5(a) 1 E

SR 3.3.5.1.2

> 1647 gpm SR 3.3.5.1.5 and

_< 2910 gpm C

SR 3.3.5.1.5

_ 6 seconds SR 3.3.5.1.6 and

< 8 seconds C

SR 3.3.5.1.5

> 0 seconds SR 3.3.5.1.6 and

5 1 second C

SR 3.3.5.1.5 2! 6 seconds SR 3.3.5.1.6 and

< 8 seconds C

SR 3.3.5.1.5 2! 12 seconds SR 3.3.5.1.6 and

< 16 seconds 1

(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)

2.

Low Pressure Coolant Injection (LPCI) System

a. Reactor Vessel Water LeI

- Low Low Low, Level ib

b.

Drywell Pressure - HighQ

c. Reactor Steam Dome Pressure - Low (Injection Permissiv, nd ECCS InitiationAIV
d. Reactor Steam Dome Pressure - Low (Recirculation Discrge Valve Permissive)Ve
e. Reactor Vessel Water Level

- Level 0 1,2,3, 4 (a). 5 (a) 1 C

SR 3.3.5.1.5 a 18 seconds SR 3.3.5.1.6 and S 24 seconds 1.2.3.

4 (a), 5 (a) 1,2,3 1,2.3 4 (a), 5 (a) 1 (c), 2(c),

3 (c) 1,2,3 4

4 4

4 4

2 1 per subsystem B

SSR SR SR SR B

SSR SR SR C

SR SR SR B

SR SR SR C

SR SR SR B

SR SR SR SR 3.3.5.1.1 3.3.5.1.2 3.3.5.1.5 3.3.5.1.6 3.3.5.1.2 3.3.5.1.5 3.3.5.1.6 3.3.5.1.2 3.3.5.1.4 3.3.5.1.6 3.3.5.1.2 3.3.5.1.4 3.3.5.1.6 3.3.5.1.2 3.3.5.1.4 3.3.5.1.6 3.3.5.1.1 3.3.5.1.2 3.3.5.1.5 3.3.5.1.6

> 398 inches above vessel zero

< 2.5 psig

Ž 435 psig and

< 465 psi9

Ž_ 435 psig and

< 465 psig

Ž> 215 psig and

_< 245 psig I

I

> 312 5/16 inches above vessel zero (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 I I 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 2! 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

Ž! 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

> 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 WatrLevel 1,

4 B

SR 3.3.5.1.1

_470 inches

- Low Low, Level 2(

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 F

I I

BFN-UNIT 2 3.3-45 Amendment No.-2-53-, 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!o
c. Reactor Vessel Water Level

- High, Level 8

d. Condensate Header Level -

Low

e. Suppression Pool Water Level - High
f.

High Pressure Coolant Injection Pump Discharge Flow - Low (Bypass)

4. Automatic Depressurization System (ADS) Trip System A
a. Reactor Vessel Water Level

- Low Low Low, Level 10

b.

Drywell Pressure - High*

c. Automatic Depressurization System Initiation Timer 1,

2(d),3(d) 1, 2(d), 3(d) 1, 2 (d), 3(d) 1, 2 (d), 3 (d) 1.

2(d). 3(d) 4 2

B SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 C

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 D

SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 D

SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.35.1.6 E

SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 5 2.5 psig

!5 583 inches above vessel zero

> Elev. 551 feet s 7 inches above instrument zero 2! 671 gpm 1,

2 (d), 3(d) 1, 2 (d), 3 (d) 1, 2 (d), 3 (d) 2 2

F SR 3.3 5.1.1 SR 3.3,5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 F

SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6

> 398 inches above vessel zero

_ 2.5 psig 1

G SR 3.3.5.1.5 s 115 SR 3.3.5.1.6 seconds (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

- Low Level 3 (Confi;matory)o

e. Core Spray Pump Discharge Pressure - High
f.

Low Pressure Coolant Injection Pump Discharge Pressure - High

g. Automatic Depressurization System High Drywell Pressure Bypass Timer 1.

2 (d), 3(d) 1, 2 (d), 3(d) 1, 2 (d), 3 (d) 1, 2 (d), 3 (d) 1.

2 (d) 3(d) 1, 2 (d), 3 (d) 1, 2 (d), 3 (d) 1, 2 (d), 3(d) 1 4

8 2

F SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 G

SR 3.3.5.1.2 SR 3.3.5.1.3 SR 3.3.5.1.6 G

SR 3.3.5.1.2 SR 3 3.5.1.3 SR 3 3.5.1.6

> 528 inches above vessel zero

_> 175 psig and

< 195 psig

>_ 90 psig and

< 110 psig G

SR 3.3.5.1.5

< 322 SR 3.3.5.1.6 seconds

5. ADS Trip System B
a.

Reactor Vessel Water LeI

- Low Low Low, Level 16

b. Drywell Pressure - HighE
c. Automatic Depressurization System Initiation Timer
d.

Reactor Vessel Water Level

- Low, Level 3 (Confirmatory) 0 2

F SR 3.3.5.1.1 SIR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 F

SR 3.3.5.1.2 SR 3.3.5.1.5 SIR 3.3.5.1.6 2! 398 inches above vessel zero

< 2.5 psig 2

1 G

SR 3.3.5.1.5

< 115 SR 3.3.5.1.6 seconds F

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6

> 528 inches above vessel zero (continued)

(d)

With reactor steam dome pressure > 150 psig.

I I (e) INSERT FOOTNOTE I

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 W* Level -

B SR 3.3.5.2.1

_470 inches Low Low, Level a

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 FOOTNOTEI I

BFN-UNIT 2 3.3-52 Amendment No. 253

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 Level - Low Low Low.

Level 1

b.

Main Steam Line Pressure - LoO

c.

Main Steam Line Flow -

High

d. Main Steam Tunnel Temperature - High
2.

Primary Containment Isolation

a.

Reactor Vessel Water Level - Low, Level 3

b. Drywell Pressure - High
3.

High Pressure Coolant Injection (HPCI) System Isolation

a.

HPCI Steam Line Flow -

High

b. HPCI Steam Supply Line Pressure - Low
c. HPCI Turbine Exhaust Diaphragm Pressure - High 1,2,3 1

1,2,3 1,2,3 2

2 2 per MSL 8

D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 E

SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 D

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 D

SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 G

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 G

SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 2! 398 inches above vessel zero

_> 825 psig 5 140% rated steam flow

!5 200OF I

1,2,3 1,2,3 2

2 2t 528 inches above vessel zero

_5 2.5 psig 1,2.3 1.2,3 1,2,3 1

3 F

SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F

SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F

SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

!< 90 psi

_Ž 100 psig

< 20 psig (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

2. Average Power Range Monitors (continued)
d.

Inop

e. 2-Out-Of-4 Voter
f.

OPRM Upscale

3.

Reactor Vessel_

Dome Pressure - Higu

4. Reactor Ves Waler Level Low, Level d)
5.

Main Steam Isolation Valve -

Closure

6.

Drywell Pressure - High

7. Scram Discharge Volume Water Level - High
a. Resistance Temperature Detector 1,2 1,2 1,2 1.2 3 (b) 2 3(b) 2 2

8 G

SR 3.3.1.1.16 NA G

SR 3.3.1.1.1 SR 3.3.1.1.14 SR 3.3.1.1.16 SR 3.31.1.1 SR 3.3.1.1.7 SR 3.3.1.1.13 SR 3.3.1.1.16 SR 3.3.1.1.17 G

SR 3.3.1.1.1 SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.14 G

SR 3.3.1.1.1 SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 NA NA

< 1090 psig

? 528 inches above vessel zero

< 10% closed s 2.5 psig F

SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 1,2 2

G SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 1,2 2

G SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 H

SR 3.3.1.1.8 SR 3.3.1.1.13 SR 3.3.1.1.14 5 (a) 2

_< 50 gallons

< 50 gallons (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 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 33.1.1.13 SR 3.3.1.1.14

8. Turbine Stop Valve -

Ž30% RTP 4

E SR 3.3.1.1.8 5 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 z! 30% RTP E

SR 3.3.1.1.8

>550 psig ClosLwe. Trip Oil Pressure SR 3.3.1.1.13 Low(d;.?

SR 3.3.1.1.14 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, 213, 221, 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_1 Low Low Low, Level
b. Drywell Pressure -

Higho

c. Reactor Steam Dome Pressure -

Low (Injection Permissiv~nd ECCS Initiation )

d. Core Spray Pump Discharge Flow -

Low (Bypass)

e.

Core Spray Pump Start-Time Delay Relay Pumps A.B,C,D (with diesel power)

Pump A (with normal power)

Pump B (with normal power)

Pump C (with normal power) 1.2.3, 4(a), 5(a) 1,2,3 4(b) 4(b) 1,2,3 4 (b) 2 per trip system B

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 B

SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 C

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 B

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 E

SR 3.3.5.1.2 SR 3.3.5.1.5 4(a), 5(a) 4 2 per trip system 1,2,3, 4 (a), 5(a) 2 1 per subsystem

_ 398 inches above vessel zero

_< 2.5 psig

_> 435 psig and

< 465 psig

> 435 psig and s 465 psig

> 1647 gpm and 5 2910 gpm

Ž 6 seconds and

< 8 seconds

- 0 seconds and 5 1 second k 6 seconds and s 8 seconds

> 12 seconds and

< 16 seconds (continued) 1.2.3, 4

4 (a), 5 (a) 1 per pump 1.2,3, 4(a). 5(a) 1,2.3, 4 (a), 5(a) 1.2.3.

4 (a), 5 (a)

SR 3.3.5.1.5 SR 3.3.5.1.6 C

SR 3.3.5 1.5 SR 3.3.5.1.6 C

SR 3.3.5.1.5 SR 3.3.5.1.6 C

SR 3.3.5.1.5 SR 3.3.5.1.6 (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

()

INSERT FOOTNOTE II 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)

2.

Low Pressure Coolant Injection (LPCI) System

a. Reactor Vessel Water LeI Low Low Low, Level ýb
b. Drywell Pressure -

Higl

c.

Reactor Steam Dome Pressure -

Low (Injection PermissiA and ECCS Initiation,)

d. Reactor Steam Dome Pressure -

Low (Recirculation Disc Mrge Valve Permissive) V)

e. Reactor Vessel Water Level Level 0 1,2,3, 1.2.3.

4 (a), 5(a) 1.2,3 1,2,3 4 (a), 5(a) 1(c),2 (c),

3 (c) 1 C

SR 3.3.5.1.5 SR 3.3.5.1.6 4

4 4

4 B

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 B

SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 C

SR 3.3.5.1.2 SR 3 3.5.1.4 SR 3.3.5.1.6 B

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 C

SR 3.3.5.1.2 SR 3.3.5.1.4 SR 3.3.5.1.6 B

SR 3.3.5.1.1 SR 3.3.5.1.2 SR 3.3.5.1.5 SR 3.3.5.1.6 2! 18 seconds and

< 24 seconds

_> 398 inches above vessel zero

< 2.5 psig 2! 435 psig and

<_ 465 psig

> 435 psig and 5 465 psig

> 215 psig and 5 245 psig zŽ 312 5/16 inches above vessel zero 1,2,3 2

1 per subsystem (continued)

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

(b)

Deleted.

(c)

With associated recirculation pump discharge valve open.

(ft) 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 AB,C,D (with diesel 1.2,3.

8(e)

C SR 3.3.5.1.5

-e 0 seconds power) 4 (a), 5 (a)

SR 3.3.5.1.6 and

_< 1 second Pump A (with normal power) 1,2,3.

2 C

SR 3.3.5.1.5 Z! 0 seconds 4 (a), 5 (a) 1 per trip SR 3.3.5.1.6 and system 5 1 second Pump B (with normal power) 1,2.3, 2

C SR 3.3.5.1.5

> 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 WateSLJLevel 1,

4 B

SR 3.3.5.1.1

Ž 470 inches Low Low, Level 2VD 2(d). 3(d)

SR 3.3.5.1.2 above vessel SR 3.3.5.1.5 zero SR 33.5.1.6 (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).

(f)

INSERT FOOTNOTE 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. DrywellPressure-Hig..
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 3.35.1.1

< 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,

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 3.35.1.2 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 Levl 1,

2 F

SR 3.3.5.1.1

> 398 inches Low Low Low, Level 1i,,

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

< 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 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)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

Ž.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

Ž90 psig and Injection Pump Discharge 2(d), 3(d)

SR 3.3.5.1.3 s 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

>398 inches Low Low Low, Level 1W 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

!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

< 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

Ž528 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.

(f) INSERT FOOTNOTEI BFN-UNIT 3 3.3-47 Amendment No. 242,-213, 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 Wglr Level -

4 B

SR 3.3.5.2.1

> 470 inches Low Low, Level a

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 I(a)

INSERT FOOTNOTE I

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 Level - Low Low Low, Level 1
b.

Main Steam Lin,,,

Pressure - Lo%4DS

c.

Main Steam Line Flow -

High

d. Main Steam Tunnel Temperature - High
2.

Primary Containment Isolation

a.

Reactor Vessel Water Level - Low, Level 3

b. Drywell Pressure - High
3.

High Pressure Coolant Injection (HPCI) System Isolation

a.

HPCI Steam Line Flow -

High

b.

HPCI Steam Supply Line Pressure - Low

c.

HPCI Turbine Exhaust Diaphragm Pressure - High 1,2.3 1

1,2.3 1.2,3 2

2 2 per MSL 8

D SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 E

SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 D

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 D

SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 G

SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3,6.1.6 G

SR 3.3.6.1.2 SR 3.36.1.5 SR 3.3.6.1.6

_> 398 inches above vessel zero z! 825 psig

< 140% rated steam flow

!5 200OF 1.2,3 1.2,3 2

2

_ 528 inches above vessel zero

< 2.5 psig 1,2.3 1.2.3 1,2.3 3

3 F

SR 3.3.6.1.2 SR 3.3,6.1.5 SR 3.3.6.1.6 F

SR 3.36.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6 F

SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.6

< 90 psi

> 100 psig

< 20 psig (continued)

I (c)

INSERT FOOTNOTE I

BFN-UNIT 3 3.3-59 Amendment No. 242, 2!3, 219 August 16, 1999 Browns Ferry Nuclear Plant (BFN) Units 1, 2, and 3 Technical Specifications (TS)

Change TS-453S2 Instrument Setpoint Program List of 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 for the instrument functions-for which -the footnote is being added 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.

3.

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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