Text

Technical Requirements Manual, Revision 66
	ML18249A160
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Site:	Brunswick
Issue date:	08/13/2018
From:	; Duke Energy Progress
To:	; Office of Nuclear Reactor Regulation
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Technical Requirements Manual Brunswick Steam Electric Plant, Unit No. 2

Renewed Facility Operating License DPR-62

Revision 66

LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENTS MANUAL Brunswick Unit 2 LOEP-1 Revision No. 66

Page No. Revision No.

Title Page 66 3.0-1 23 3.0-2 23 List of Effective Pages 3.0-3 23

LOEP-1 66 3.1-1 23 LOEP-2 66 3.1-2 23 LOEP-3 66 LOEP-4 65 3.2-1 23 LOEP-5 65 3.3-1 23 0.0-1 55 3.3-2 23 0.0-2 66 3.3-3 23 0.0-3 45 3.3-4 36 0.0-4 23 0.0-5 23 3.4-1 60 0.0-6 23 3.4-2 29 3.4-3 60 1.1-1 23 1.1-2 23 3.5-1 32 1.1-3 23 3.5-2 23 3.5-3 23 1.2-1 23 1.2-2 23 3.6-1 31 1.2-3 23 3.6-2 23 3.6-3 23 1.3-1 23 1.3-2 23 3.7-1 23 1.3-3 23 1.3-4 23 3.8-1 31 1.3-5 23 3.8-2 23 1.3-6 23 1.3-7 23 3.9-1 47 1.3-8 23 3.9-2 47 1.3-9 23 3.9-3 47 1.3-10 23 1.3-11 23 3.10-1 31 1.3-12 23 3.11-1 23 1.4-1 23 3.11-2 51 1.4-2 23 3.11-3 51 1.4-3 23 1.4-4 23 3.12-1 23 1.4-5 23 3.12-2 57

2.0-1 23 (continued)

LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENTS MANUAL Brunswick Unit 2 LOEP-2 Revision No. 66

Page No. Revision No.

3.12-3 23 3.22-1 23 3.12-4 57 3.22-2 23 3.22-3 23 3.13-1 23 3.13-2 23 3.23-1 23 3.13-3 23 3.13-4 23 3.24-1 23

3.14-1 65 3.25-1 23 3.14-2 65 3.25-2 23 3.14-3 65 3.25-3 23 3.25-4 23 3.15-1 23 3.26-1 23 3.16-1 58 3.16-2 58 4.0-1 23 3.16-3 33 5.0-1 45 3.17-1 23 5.0-2 41 3.17-2 23 5.0-3 45 3.17-3 23 5.0-4 45 5.0-5 62 3.18-1 23 5.0-6 45 3.18-2 23 B 3.0-1 23 3.19-1 23 B 3.0-2 26 3.19-2 23 B 3.0-3 23 B 3.0-4 23 3.20-1 23 B 3.0-5 23 B 3.0-6 23 3.21-1 40 B 3.0-7 23 3.21-2 66 B 3.0-8 23 B 3.0-9 23 B 3.0-10 23 B 3.1-1 23 B 3.2-1 23 B 3.3-1 23 B 3.4-1 60

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LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENTS MANUAL Brunswick Unit 2 LOEP-3 Revision No. 66

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B 3.5-1 23 B 3.18-1 23 B 3.18-2 23 B 3.6-1 31 B 3.18-3 23

B 3.7-1 23 B 3.19-1 23 B 3.19-2 23 B 3.8-1 31 B 3.19-3 23

B 3.9-1 47 B 3.20-1 23 B 3.9-2 47 B 3.9-3 47 B 3.21-1 66 B 3.9-4 47 B 3.21-2 66 B 3.9-5 47 B 3.9-6 47 B 3.22-1 23 B 3.10-1 31 B 3.23-1 23 B 3.11-1 23 B 3.24-1 23 B 3.12-1 57 B 3.12-2 23 B 3.25-1 23 B 3.12-3 57 B 3.12-4 23 B 3.26-1 23

B 3.13-1 23 APPENDIX A 23 A-1 23 B 3.14-1 65 A-2 23 B 3.14-2 65 A-3 23 B 3.14-3 65 A-4 23 B 3.14-4 65 A-5 23 B 3.14-5 65 A-6 23 B 3.14-6 65 A-7 23 B 3.14-7 65 A-8 23 A-9 27 B 3.15-1 23 A-10 23 A-11 23 B 3.16-1 58 A-12 23 B 3.16-2 58 A-13 23 B 3.16-3 58 A-14 23 A-15 23 B 3.17-1 23 A-16 25 A-17 25 A-18 25 A-19 23

(continued)

LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENTS MANUAL Brunswick Unit 2 LOEP-4 Revision No. 65

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APPENDIX B 23 APPENDIX D 23 B-1 23 D-1 23 B-2 44 D-2 26 B-3 23 D-3 23 B-4 44 D-4 30 B-5 23 D-5 26 B-6 23 D-6 26 B-7 39 D-7 26 B-8 23 D-8 23 B-9 23 D-9 42 B-10 23 D-10 26 B-11 23 D-11 26 B-12 24 D-12 26 B-13 23 D-13 23 B-14 23 D-14 49 B-15 23 D-15 49 B-16 23 D-16 23 B-17 23 D-17 59 B-18 28 D-18 23 B-19 23 D-19 23 B-20 23 D-20 23 B-21 23 D-21 24 B-22 48 B-23 23 APPENDIX E 23 B-24 34 E-1 23 B-25 23 E-2 23 B-26 63 B-27 64 APPENDIX F 23 B-28 23 SFDP-1 23 B-29 23 SFDP-2 23 SFDP-3 23 APPENDIX C 23 SFDP-4 23 C-1 23 SFDP-5 23 C-2 44 SFDP-6 23 C-3 61 SFDP-7 23 C-4 28 SFDP-8 23 C-5 23 SFDP-9 23 C-6 23 SFDP-10 23 C-7 23 SFDP-11 23 C-8 47 SFDP-12 23 C-9 52 SFDP-13 23 C-10 51 SFDP-14 23 C-11 57 SFDP-15 23

(continued)

LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENTS MANUAL Brunswick Unit 2 LOEP-5 Revision 65

Page No. Revision No.

SFDP-16 23 SFDP-17 23 SFDP-18 23 SFDP-19 23 SFDP-20 23 SFDP-21 23 SFDP-22 23 SFDP-23 23 SFDP-24 23 SFDP-25 23 SFDP-26 23

B SFDP-1 23 B SFDP-2 23 B SFDP-3 23 B SFDP-4 23 B SFDP-5 23 B SFDP-6 23 B SFDP-7 23 B SFDP-8 23 B SFDP-9 23 B SFDP-10 23 B SFDP-11 23 B SFDP-12 23 B SFDP-13 23 B SFDP-14 23 B SFDP-15 23

Brunswick Unit 2 0.0-1 Revision No. 55 Carolina Power & Light Company Brunswick Unit 2 TITLE: Technical Requirements Manual Purpose, Control, and Contents PURPOSE: Provides information and guidance on requirements for various plant conditions, actions, and testing similar to the Technical Specifications, which is mainly required to support appropriate operation of the station in

accordance with commitments. The Technical Requirements Manual (TRM) is under the control of Carolina Power & Light (CP&L) Company

and all changes are to be evaluated for acceptance by performing

10 CFR 50.59 review.

SCOPE: This manual contains a wide variety of information on and requirements for various systems and processes, most of which existed in the

Technical Specifications at some previous point in time.

INTENDED USE: The TRM is intended to be used primarily by Operations to provide operating guidance for various plant equipment (similar to the Technical

Specifications) and as an aid for the Technical Specifications (e.g., valve

and instrument lists). The format of the requirements in the TRM is in

accordance with NUMARC 93-03, "Writers Guide for Restructured

Standard Technical Specifications".

Noncompliance with TRM requirements (i.e., Technical Requirements

Manual Specification (TRMS) and associated Required Compensatory

Measures not met or failure to perform a Test Requirement (TR) in

accordance with TR 3.0.2) requires the generation of a condition report

since the TRM requirements were violated, and other potential

consequences exist.

This manual is controlled in accordance with AD-LS-ALL-0015, "License

Amendment Request and Changes to SLC, TRM, and TS Bases."

Changes previously initiated under 0AP-057 (prior to October 7, 2013)

may be completed using that process. The technical information in each

section, including the associated Bases, and the Appendices is the

responsibility of the group(s) identified in the responsibility matrix on the

following page. All changes to TRM sections shall be reviewed by the

Licensing Unit prior to approval. In addition, all changes shall be

reviewed and approved by the Plant Nuclear Safety Committee prior to

implementation. Changes to this manual may be made by CP&L

Company as long as the changes are reviewed in accordance with

10 CFR 50.59 requirements and do not constitute a change to the

Technical Specifications or require a license amendment. The

responsibility for the administrative control of the manual is assigned to

the Licensing Unit.

Brunswick Unit 2 0.0-2 Revision No. 66 Matrix of Responsible Group(s) for TRM Sections, associated Bases, and Appendices SECTION TITLE RESPONSIBLE GROUP 3.0 Technical Requirements Manual Specifications (TRM) and Test Requirements (TR) Applicability Licensing /

Regulatory Programs 3.1 Control Rod Drive Housing Support BESS - MECH 3.2 Not used. 3.3 Control Rod Block Instrumentation BESS - MECH ELEC/I&C 3.4 Accident Monitoring Instrumentation BESS - ELEC/I&C 3.5 Chloride Intrusion Monitors BESS - ELEC/I&C 3.6 Bus Power Monitors BESS - ELEC/I&C 3.7 Automatic Depressurization System (ADS) Inhibit Switch BESS - ELEC/I&C 3.8 Suppression Chamber Water Temperature Instrumentation BESS - ELEC/I&C 3.9 Seismic Monitoring Instrumentation BESS - ELEC/I&C 3.10 Intake Canal High Water Level Instrumentation BESS - ELEC/I&C 3.11 Primary Containment Isolation Instrumentation BESS - ELEC/I&C 3.12 Control Room Emergency Ventilation (CREV) System Instrumentation BESS - ELEC/I&C 3.13 Reactor Coolant System (RCS) Chemistry E&RC 3.14 Structural Integrity BESS -

TECHNICAL SERVICES 3.15 Not used. 3.16 Service Water System Operability - Shutdown BESS - MECH 3.17 Service Water System - Shutdown Operations BESS - MECH 3.18 Control Room Emergency Vent ilation (CREV) System - Smoke Protection Mode BESS - MECH 3.19 Control Room Emergency Ventilation (CREV) System - Chlorine Protection Mode BESS - MECH 3.20 Flood Protection OPERATIONS 3.21 Snubbers FLEET PROGRAM ENGINEERING 3.22 Sealed Source Contamination E&RC 3.23 Decay Time BESS - MECH 3.24 Communications OPERATIONS 3.25 Crane and Hoist Operability BESS - MECH 3.26 Crane Travel - Spent Fuel Storage Pool BESS - MECH 5.5.1 Offsite Dose Calculation Manual E&RC 5.5.2 Primary Coolant Sources Outside Containment BESS -

TECHNICAL SERVICES 5.5.3 Deleted. 5.5.4 Radioactive Effluent Controls Program E&RC 5.5.5 Component Cyclic or Transient Limit Program BESS - MECH Brunswick Unit 2 0.0-3 Revision No. 45 Matrix of Responsible Group(s) for TRM Sections, associated Bases, and Appendices SECTION TITLE RESPONSIBLE GROUP 5.5.6 Inservice Testing Program BESS - TECHNICAL SERVICES 5.5.7 Ventilation Filter Testing Program BESS - MECH 5.5.8 Explosive Gas and Storage T ank Radioactivity Monitoring Program E&RC 5.5.9 Diesel Fuel Oil Testing Program E&RC 5.5.10 Technical Specification Bases Control Program LICENSING /

REGULATORY PROGRAMS 5.5.11 Safety Function Determination Program OPERATIONS 5.5.12 Primary Containment Leakage Rate Testing Program BESS - TECHNICAL SERVICES 5.5.13 Control Room Envelope Habitability Program BESS - SYSTEMS ENGINEERING 5.5.14 Configuration Risk Management Program OUTAGE &

SCHEDULING 5.5.15 Inservice Inspection Program BESS - TECHNICAL SERVICES APPENDIX A Relocated Items Matrix LICENSING /

REGULATORY PROGRAMS APPENDIX B Technical Specifications Instrumentation Numbers and Trip Setpoints List BESS - ELEC/I&C APPENDIX C Technical Requirements Manual Instrumentation Numbers and Trip Setpoints List BESS - ELEC/I&C APPENDIX D Primary Containment Isolation Valve List BESS - TECHNICAL SERVICES APPENDIX E Secondary Containment Isolation Damper List BESS - MECH APPENDIX F Safety Function Determination Program OPERATIONS

Brunswick Unit 2 0.0-4 Revision No. 23 TABLE OF CONTENTS

1.0 USE AND APPLICATION ..................................................................................... 1.1-1

1.1 Definitions

....................................................................................................... 1.1-1

1.2 Logical

Connectors ......................................................................................... 1.2-1

1.3 Completion

Times ........................................................................................... 1.3-1

1.4 Frequency

..................................................................................................... 1.4-1 2.0 NOT USED ........................................................................................................... 2.0-1

3.0 TECHNICAL

REQUIREMENTS MANUAL SPECIFICATION (TRMS) AND TEST REQUIREMENTS (TR) APPLICABILITY ....................................................... 3.0-1 3.1 CONTROL ROD DRIVE HOUSING SUPPORT ............................................. 3.1-1 3.2 NOT USED .................................................................................................... 3.2-1

3.3 CONTROL

ROD BLOCK ................................................................................ 3.3-1

3.4 ACCIDENT

MONITORING INSTRUMENTATION ......................................... 3.4-1 3.5 CHLORIDE INTRUSION MONITORS ............................................................ 3.5-1 3.6 BUS POWER MONITORS ............................................................................. 3.6-1

3.7 AUTOMATIC

DEPRESSURIZATION SYSTEM (ADS) INHIBIT SWITCH ...... 3.7-1 3.8 SUPPRESSION CHAMBER WATER TEMPERATURE INSTRUMENTATION ................................................................................ 3.8-1 3.9 SEISMIC MONITORING INSTRUMENTATION ............................................. 3.9-1 3.10 INTAKE CANAL HIGH WATER LEVEL INSTRUMENTATION .................... 3.10-1 3.11 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION .................. 3.11-1 3.12 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM INSTRUMENTATION .............................................................................. 3.12-1 3.13 REACTOR COOLANT SYSTEM (RCS) CHEMISTRY ................................. 3.13-1 3.14 STRUCTURAL INTEGRITY ......................................................................... 3.14-1 3.15 NOT USED ................................................................................................... 3.15-1 3.16 SERVICE WATER SYSTEM OPERABILITY-SHUTDOWN ....................... 3.16-1 3.17 SERVICE WATER SYSTEM-SHUTDOWN OPERATIONS ....................... 3.17-1

(continued)

TABLE OF CONTENTS (continued)

Brunswick Unit 2 0.0-5 Revision No. 23 3.18 CONTROL ROOM EMERGENCY VENTILATION (CREV)

SYSTEM-SMOKE PROTECTION MODE ............................................. 3.18-1 3.19 CONTROL ROOM EMERGENCY VENTILATION (CREV)

SYSTEM-CHLORINE PROTECTION MODE ......................................... 3.19-1 3.20 FLOOD PROTECTION ................................................................................. 3.20-1 3.21 SNUBBERS .................................................................................................. 3.21-1 3.22 SEALED SOURCE CONTAMINATION ........................................................ 3.22-1 3.23 DECAY TIME ................................................................................................ 3.23-1 3.24 COMMUNICATIONS .................................................................................... 3.24-1 3.25 CRANE AND HOIST OPERABILITY ............................................................ 3.25-1 3.26 CRANE TRAVEL-SPENT FUEL STORAGE POOL ................................... 3.26-1 4.0 NOT USED ............................................................................................................ 4.0-1

5.0 PROGRAMS

AND MANUALS ............................................................................... 5.0-1 B 3.0 TECHNICAL REQUIREMENTS MANUAL SPECIFICATION (TRMS) AND TEST REQUIREMENT (TR) APPLICABILITY ..................... B 3.0-1 B 3.1 CONTROL ROD DRIVE HOUSING SUPPORT ......................................... B 3.1-1 B 3.2 NOT USED ................................................................................................ B 3.2-1 B 3.3 CONTROL ROD BLOCK INSTRUMENTATION ........................................ B 3.3-1 B 3.4 ACCIDENT MONITORING INSTRUMENTATION ..................................... B 3.4-1 B 3.5 CHLORIDE INTRUSION MONITORS ........................................................ B 3.5-1 B 3.6 BUS POWER MONITORS ......................................................................... B 3.6-1 B 3.7 AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) INHIBIT SWITCH ................................................................................................. B 3.7-1 B 3.8 SUPPRESSION CHAMBER WATER TEMPERATURE INSTRUMENTATION ............................................................................ B 3.8-1 B 3.9 SEISMIC MONITORING INSTRUMENTATION ......................................... B 3.9-1 (continued)

TABLE OF CONTENTS (continued)

Brunswick Unit 2 0.0-6 Revision No. 23 B 3.10 INTAKE CANAL HIGH WATER LEVEL INSTRUMENTATION ................ B 3.10-1 B 3.11 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION .............. B 3.11-1 B 3.12 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM INSTRUMENTATION .......................................................................... B 3.12-1 B 3.13 REACTOR COOLANT SYSTEM (RCS) CHEMISTRY ............................. B 3.13-1 B 3.14 STRUCTURAL INTEGRITY ..................................................................... B 3.14-1 B 3.15 NOT USED ............................................................................................... B 3.15-1 B 3.16 SERVICE WATER SYSTEM OPERABILITY-SHUTDOWN ................... B 3.16-1 B 3.17 SERVICE WATER SYSTEM-SHUTDOWN OPERATIONS ................... B 3.17-1 B 3.18 CONTROL ROOM EMERGENCY VENTILATION (CREV)

SYSTEM-SMOKE PROTECTION MODE ......................................... B 3.18-1 B 3.19 CONTROL ROOM EMERGENCY VENTILATION (CREV)

SYSTEM-CHLORINE PROTECTION MODE .................................... B 3.19-1 B 3.20 FLOOD PROTECTION ............................................................................. B 3.20-1 B 3.21 SNUBBERS .............................................................................................. B 3.21-1 B 3.22 SEALED SOURCE CONTAMINATION .................................................... B 3.22-1 B 3.23 DECAY TIME ............................................................................................ B 3.23-1 B 3.24 COMMUNICATIONS ................................................................................ B 3.24-1 B 3.25 CRANE AND HOIST OPERABILITY ........................................................ B 3.25-1 B 3.26 CRANE TRAVEL-SPENT FUEL STORAGE POOL ............................... B 3.26-1

APPENDIX A RELOCATED ITEMS MATRIX APPENDIX B TECHNICAL SPECIFICATION (TS) INSTRUMENT LIST APPENDIX C TECHNICAL REQUIREMENTS MANUAL (TRM) INSTRUMENT LIST APPENDIX D PRIMARY CONTAINMENT ISOLATION VALVE (PCIV) LIST APPENDIX E SECONDARY CONTAINMENT ISOLATION DAMPER (SCID) LIST APPENDIX F SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)

Definitions

1.1 Brunswick

Unit 2 1.1-1 Revision No. 23 1.0 USE AND APPLICATION

TRMS 1.1 Definitions

NOTE -----------------------------------------------------------

The defined terms of this section appear in capitalized type and are applicable throughout these

Technical Requirements Manual Specifications and Bases.

Term Definition CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within

the necessary range and accuracy to known values of the

parameter that the channel monitors. The CHANNEL

CALIBRATION shall encompass the entire channel, including

the required sensor, alarm, display, and trip functions, and

shall include the CHANNEL FUNCTIONAL TEST. Calibration

of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace

qualitative assessment of sensor behavior and normal

calibration of the remaining adjustable devices in the channel.

The CHANNEL CALIBRATION may be performed by means

of any series of sequential, overlapping, or total channel

steps so that the entire channel is calibrated.

CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This

determination shall include, where possible, comparison of

the channel indication and status to other indications or

status derived from independent instrument channels

measuring the same parameter.

CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the

sensor as practicable to verify OPERABILITY, including

required alarm, interlock, display, and trip functions, and

channel failure trips. The CHANNEL FUNCTIONAL TEST

may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel

is tested.

(continued)

Definitions

1.1 Brunswick

Unit 2 1.1-2 Revision No. 23 TRMS 1.1 Definitions (continued)

CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor

vessel with the vessel head removed and fuel in the vessel.

The following exceptions are not considered CORE

ALTERATIONS:

a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore

probes, or special movable detectors (including

undervessel replacement); and b. Control rod movement, provided there are no fuel assemblies in the associated core cell.

Suspension of CORE ALTERATIONS shall not preclude

completion of movement of a component to a safe position. LOGIC SYSTEM FUNCTIONAL A LOGIC SYSTEM FUNCTIONAL TEST shall be a test TEST of all required logic components (i.e., all required relays and contacts, trip units, solid state logic elements, etc.) of a logic

circuit, from as close to the sensor as practicable up to, but

not including, the actuated device, to verify OPERABILITY.

The LOGIC SYSTEM FUNCTIONAL TEST may be performed

by means of any series of sequential, overlapping, or total

system steps so that the entire logic system is tested.

MODE A MODE shall be as required by Technical Specifications.

OPERABLE-OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of

performing its specified safety function(s) and when all

necessary attendant instrumentation, controls, normal or

emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for

the system, subsystem, division, component, or device to

perform its specified safety function(s) are also capable of

performing their related support function(s).

(continued)

Definitions

1.1 Brunswick

Unit 2 1.1-3 Revision No. 23 TRMS 1.1 Definitions (continued)

RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 2923 MWt.

THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

Logical Connectors

1.2 Brunswick

Unit 2 1.2-1 Revision No. 23 1.0 USE AND APPLICATION

TRMS 1.2 Logical Connectors

PURPOSE The purpose of this section is to explain the meaning of logical connectors.

Logical connectors are used in Technical Requirements

Manual Specifications (TRMS) to discriminate between, and

yet connect, discrete Conditions, Required Compensatory

Measures, Completion Times, Tests, and Frequencies. The

only logical connectors that appear in TRMS are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.

BACKGROUND Several levels of logic may be used to state Required Compensatory Measures. These levels are identified by the

placement (or nesting) of the logical connectors and by the

number assigned to each Required Compensatory Measure.

The first level of logic is identified by the first digit of the

number assigned to a Required Compensatory Measure and

the placement of the logical connector in the first level of

nesting (i.e., left justified with the number of the Required

Compensatory Measure). The successive levels of logic are

identified by additional digits of the Required Compensatory

Measure number and by successive indentions of the logical

connectors.

When logical connectors are used to state a Condition, Completion Time, Test, or Frequency, only the first level of

logic is used, and the logical connector is left justified with the

statement of the Condition, Completion Time, Test, or

Frequency.

EXAMPLES The following examples illustrate the use of logical connectors.

(continued)

Logical Connectors

1.2 Brunswick

Unit 2 1.2-2 Revision No. 23 TRMS 1.2 Logical Connectors

EXAMPLES EXAMPLE 1.2-1 (continued)

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. TRMS not met. A.1 Verify . . .

AND A.2 Restore . . .

In this example the logical connector AND is used to indicate that when in Condition A, both Required Compensatory Measures A.1 and A.2 must

be completed.

(continued)

Logical Connectors

1.2 Brunswick

Unit 2 1.2-3 Revision No. 23 TRMS 1.2 Logical Connectors

EXAMPLES EXAMPLE 1.2-2 (continued)

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. TRMS not met. A.1 Trip . . .

OR A.2.1 Verify . . .

AND A.2.2.1 Reduce . . .

OR A.2.2.2 Perform . . .

OR A.3 Align . . .

This example represents a more complicated use of logical connectors.

Required Compensatory Measures A.1, A.2, and A.3 are alternative

choices, only one of which must be performed as indicated by the use of

the logical connector OR and the left justified placement. Any one of these three Compensatory Measures may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical

connector AND. Required Compensatory Measure A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical

connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.

Completion Times

1.3 Brunswick

Unit 2 1.3-1 Revision No. 23 1.0 USE AND APPLICATION

TRMS 1.3 Completion Times

PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.

BACKGROUND Technical Requirements Manual Spec ifications (TRMS) specify minimum requirements for unit systems or variables. The COMPENSATORY

MEASURES associated with a TRMS state Conditions that typically

describe the ways in which the requirements of the TRMS can fail to be

met. Specified with each stated Condition are Required Compensatory

Measure(s) and Completion Times(s).

DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Compensatory Measure. It is referenced to the time of

discovery of a situation (e.g., inoperable equipment or variable not within

limits) that requires entering a COMPENSATORY MEASURES Condition

unless otherwise specified, providing the unit is in a MODE or specified

condition stated in the Applicability of the TRMS. Required

Compensatory Measures must be completed prior to the expiration of the

specified Completion Time. A COMPENSATORY MEASURES Condition

remains in effect and the Required Compensatory Measures apply until

the Condition no longer exists or the unit is not within the TRMS

Applicability.

If situations are discovered that require entry into more than one

Condition at a time within a single TRMS (multiple Conditions), the

Required Compensatory Measures for each Condition must be performed

within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from

the time of discovery of the situation that required entry into the Condition.

Once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition, discovered to be

inoperable or not within limits, will not result in separate entry into the Condition unless specifically stated. The Required Compensatory

Measures of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.

(continued)

Completion Times

1.3 Brunswick

Unit 2 1.3-2 Revision No. 23 TRMS 1.3 Completion Times

DESCRIPTION However, when a subsequent division, subsystem, component, (continued) or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended. To apply this

Completion Time extension, two criteria must first be met. The

subsequent inoperability:

a. Must exist concurrent with the first inoperability; and b. Must remain inoperable or not within limits after the first inoperability is resolved.

The total Completion Time allowed for completing a Required

Compensatory Measure to address the subsequent inoperability shall be

limited to the more restrictive of either:

a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ; or b. The stated Completion Time as measured from discovery of the subsequent inoperability.

The above Completion Time extension does not apply to those TRMS

that have exceptions that allow completely separate re-entry into the

Condition (for each division, subsystem, component or variable

expressed in the Condition) and separate tracking of Completion Times

based on this re-entry. These exceptions are stated in individual TRMS.

The above Completion Time extension does not apply to a Completion

Time with a modified "time zero." This modified "time zero" may be

expressed as a repetitive time (i.e., "once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ," where the

Completion Time is referenced from a previous completion of the

Required Compensatory Measures versus the time of Condition entry) or

as a time modified by the phrase "from discovery . . ." Example 1.3-3

illustrates one use of this type of Completion Time. The 10 day

Completion Time specified for Condition A and B in Example 1.3-3 may

not be extended.

(continued)

Completion Times

1.3 Brunswick

Unit 2 1.3-3 Revision No. 23 TRMS 1.3 Completion Times (continued)

EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.

EXAMPLE 1.3-1 COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME B. Required Compensatory

Measure and

associated

Completion

Time not met. B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Condition B has two Required Compensatory Measures. Each Required

Compensatory Measure has its own separate Completion Time. Each

Completion Time is referenced to the time that Condition B is entered.

The Required Compensatory Measures of Condition B are to be in

MODE 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND in MODE 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . A total of 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months is allowed for reaching MODE 3 and a total of 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months (not

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ) is allowed for reaching MODE 4 from the time that Condition B

was entered. If MODE 3 is reached within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , the time allowed for

reaching MODE 4 is the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months because the total time allowed for

reaching MODE 4 is 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

If Condition B is entered while in MODE 3, the time allowed for reaching

MODE 4 is the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

(continued)

Completion Times

1.3 Brunswick

Unit 2 1.3-4 Revision No. 23 TRMS 1.3 Completion Times

EXAMPLES EXAMPLE 1.3-2 (continued)

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One pump inoperable. A.1 Restore pump to OPERABLE status. 7 days B. Required Compensatory

Measure and

associated

Completion

Time not met. B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months When a pump is declared inoperable, Condition A is entered. If the pump

is not restored to OPERABLE status within 7 days, Condition B is also

entered and the Completion Time clocks for Required Compensatory

Measures B.1 and B.2 start. If the inoperable pump is restored to

OPERABLE status after Condition B is entered, Condition A and B are

exited, and therefore, the Required Compensatory Measures of

Condition B may be terminated.

(continued)

Completion Times

1.3 Brunswick

Unit 2 1.3-5 Revision No. 23 TRMS 1.3 Completion Times

EXAMPLES EXAMPLE 1.3-3 (continued)

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One Function X subsystem

inoperable.

A.1 Restore Function X

subsystem to

OPERABLE status. 7 days AND 10 days from

discovery of failure

to meet the TRMS B. One Function Y subsystem

inoperable.

B.1 Restore Function Y

subsystem to

OPERABLE status. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months AND 10 days from

discovery of failure

to meet the TRMS C. One Function X subsystem

inoperable.

AND One Function Y subsystem

inoperable.

C.1 Restore Function X

subsystem to

OPERABLE status. OR C.2 Restore Function Y

subsystem to

OPERABLE status. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months (continued)

Completion Times

1.3 Brunswick

Unit 2 1.3-6 Revision No. 23 TRMS 1.3 Completion Times

EXAMPLES EXAMPLE 1.3-3 (continued) When one Function X subsystem and one Function Y subsystem are

inoperable, Condition A and Condition B are concurrently applicable. The

Completion Times for Condition A and Condition B are tracked separately

for each subsystem, starting from the time each subsystem was declared

inoperable and the Condition was entered. A separate Completion Time

is established for Condition C and tracked from the time the second

subsystem was declared inoperable (i.e., the time the situation described

in Condition C was discovered).

If Required Compensatory Measure C.2 is completed within the specified

Completion Time, Conditions B and C are exited. If the Completion Time

for Required Compensatory Measure A.1 has not expired, operation may

continue in accordance with Condition A. The remaining Completion

Time in Condition A is measured from the time the affected subsystem

was declared inoperable (i.e., initial entry into Condition A).

The Completion Times of Conditions A and B are modified by a logical

connector, with a separate 10 day Completion Time measured from the

time it was discovered the TRMS was not met. In this example, without

the separate Completion Time, it would be possible to alternate between

Conditions A, B, and C in such a manner that operation could continue

indefinitely without ever restoring systems to meet the TRMS. The

separate Completion Time modified by the phrase "from discovery of

failure to meet the TRMS" is designed to prevent indefinite continued

operation while not meeting the TRMS. This Completion Time allows for

an exception to the normal "time zero" for beginning the Completion Time "clock". In this instance, the Completion Time "time zero" is specified as

commencing at the time the TRMS was initially not met, instead of at the

time the associated Condition was entered.

(continued)

Completion Times

1.3 Brunswick

Unit 2 1.3-7 Revision No. 23 TRMS 1.3 Completion Times

EXAMPLES EXAMPLE 1.3-4 (continued)

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One or more valves inoperable. A.1 Restore valve(s) to OPERABLE

status. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B. Required Compensatory

Measure and

associated

Completion

Time not met. B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months A single Completion Time is used for any number of valves inoperable at

the same time. The Completion Time associated with Condition A is

based on the initial entry into Condition A and is not tracked on a per

valve basis. Declaring subsequent valves inoperable, while Condition A

is still in effect, does not trigger the tracking of separate Completion

Times.

Once one of the valves has been restored to OPERABLE status, the

Condition A Completion Time is not reset, but continues from the time the

first valve was declared inoperable. The Completion Time may be

extended if the valve restored to OPERABLE status was the first

inoperable valve. The Condition A Completion Time may be extended for

up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months provided this does not result in any subsequent valve being

inoperable for > 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

If the Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months (plus the extension) expires while one

or more valves are still inoperable, Condition B is entered.

(continued)

Completion Times

1.3 Brunswick

Unit 2 1.3-8 Revision No. 23 TRMS 1.3 Completion Times

EXAMPLES EXAMPLE 1.3-5 (continued)

COMPENSATORY MEASURES

NOTE --------------------------------------------

Separate Condition entry is allowed for each inoperable valve.

CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One or more valves inoperable. A.1 Restore valve to OPERABLE status. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months B. Required Compensatory

Measure and

associated

Completion

Time not met. B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months The Note above the COMPENSATORY MEASURES Table is a method

of modifying how the Completion Time is tracked. If this method of

modifying how the Completion Time is tracked was applicable only to a

specific Condition, the Note would appear in that Condition rather than at

the top of the COMPENSATORY MEASURES Table.

The Note allows Condition A to be entered separately for each inoperable

valve, and Completion Times tracked on a per valve basis. When a valve

is declared inoperable, Condition A is entered and its Completion Time

starts. If subsequent valves are declared inoperable, Condition A is

entered for each valve and separate Completion Times start and are

tracked for each valve.

(continued)

Completion Times

1.3 Brunswick

Unit 2 1.3-9 Revision No. 23 TRMS 1.3 Completion Times

EXAMPLES EXAMPLE 1.3-5 (continued)

If the Completion Time associated with a valve in Condition A expires, Condition B is entered for that valve. If the Completion Times associated

with subsequent valves in Condition A expire, Condition B is entered

separately for each valve and separate Completion Times start and are

tracked for each valve. If a valve that caused entry into Condition B is

restored to OPERABLE status, Condition B is exited for that valve.

Since the Note in this example allows multiple Condition entry and

tracking of separate Completion Times, Completion Time extensions do

not apply.

EXAMPLE 1.3-6 COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One channel inoperable.

A.1 Perform TR 3.x.x.x.

OR A.2 Reduce THERMAL POWER to 50% RTP.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months B. Required Compensatory

Measure and

associated

Completion

Time not met. B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

Completion Times

1.3 Brunswick

Unit 2 1.3-10 Revision No. 23 TRMS 1.3 Completion Times

EXAMPLES EXAMPLE 1.3-6 (continued)

Entry into Condition A offers a choice between Required Compensatory

Measure A.1 or A.2. Required Compensatory Measure A.1 has a "once

per" Completion Time, which qualifies for the 25% extension, per

TR 3.0.2, to each performance after the initial performance. The initial

8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval of Required Compensatory Measure A.1 begins when

Condition A is entered and the initial performance of Required

Compensatory Measure A.1 must be completed within the first 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

interval. If Required Compensatory Measure A.1 is followed and the

Required Compensatory Measure is not met within the Completion Time (plus the extension allowed by TR 3.0.2), Condition B is entered. If

Required Compensatory Measure A.2 is followed and the Completion

Time of 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months is not met, Condition B is entered.

If after entry into Condition B, Required Compensatory Measure A.1

or A.2 is met, Condition B is exited and operation may then continue in

Condition A.

(continued)

Completion Times

1.3 Brunswick

Unit 2 1.3-11 Revision No. 23 TRMS 1.3 Completion Times

EXAMPLES EXAMPLE 1.3-7 (continued)

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One subsystem inoperable. A.1 Verify affected subsystem

isolated.

AND A.2 Restore subsystem to

OPERABLE status. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

thereafter

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Required Compensatory

Measure and

associated

Completion

Time not met. B.1 Be in MODE 3.

AND B.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Required Compensatory Measure A.1 has two Completion Times. The

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Completion Time begins at the time the Condition is entered and

each "Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter" interval begins upon performance of

Required Compensatory Measure A.1.

If after Condition A is entered, Required Compensatory Measure A.1 is

not met within either the initial 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or any subsequent 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months interval

from the previous performance (plus the extension allowed by TR 3.0.2),

Condition B is entered. The Completion Time clock for Condition A does

not stop after Condition B is entered, but continues from the (continued)

Completion Times

1.3 Brunswick

Unit 2 1.3-12 Revision No. 23 TRMS 1.3 Completion Times

EXAMPLES EXAMPLE 1.3-7 (continued) time Condition A was initially entered. If Required Compensatory

Measure A.1 is met after Condition B is entered, Condition B is exited and

operation may continue in accordance with Condition A, provided the

Completion Time for Required Compensatory Measure A.2 has not

expired.

IMMEDIATE When "Immediately" is used as a Completion Time, the Required COMPLETION TIME Compensatory Measure should be pursued without delay and in a controlled manner.

Frequency

1.4 Brunswick

Unit 2 1.4-1 Revision No. 23 1.0 USE AND APPLICATION

TRMS 1.4 Frequency

PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.

DESCRIPTION Each Test Requirement (TR) has a specified Frequency in which the Test must be met in order to meet the associated Technical Requirements

Manual Specification (TRMS). An understanding of the correct

application of the specified Frequency is necessary for compliance with

the TR.

The "specified Frequency" is referred to throughout this section and each

of the Specifications of Section 3.0, Test Requirement (TR) Applicability.

The "specified Frequency" consists of the requirements of the Frequency

column of each TR, as well as certain Notes in the Test column that

modify performance requirements.

Sometimes special situations dictate when the requirements of a Test are

to be met. They are "otherwise stated" conditions allowed by TR 3.0.1.

They may be stated as clarifying Notes in the Test, as part of the Test, or

both. Example 1.4-4 discusses these special situations.

Situations where a Test could be required (i.e., its Frequency could

expire), but where it is not possible or not desired that it be performed

until sometime after the associated TRMS is within its Applicability, represent potential TR 3.0.4 conflicts. To avoid these conflicts, the TR (i.e., the Test or the Frequency) is stated such that it is only "required" when it can be and should be performed. With a TR satisfied, TR 3.0.4

imposes no restriction.

The use of "met or "performed" in these instances conveys specific

meanings. A Test is "met" only when the acceptance criteria are

satisfied. Known failure of the requirements of a Test, even without a

Test specifically being "performed," constitutes a Test not "met."

"Performance" refers only to the requirement to specifically determine the (continued)

Frequency

1.4 Brunswick

Unit 2 1.4-2 Revision No. 23 TRMS 1.4 Frequency

DESCRIPTION ability to meet the acceptance criteria. TR 3.0.4 restrictions would not (continued) apply if both the following conditions are satisfied: a. The Test is not required to be performed; and

b. The Test is not required to be met or, even if required to be met, is not known to be failed.

EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the TRMS (TRMS not

shown) is MODES 1, 2, and 3.

EXAMPLE 1.4-1 TEST REQUIREMENTS TEST FREQUENCY Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Example 1.4-1 contains the type of TR most often encountered in the

TRMS. The Frequency specifies an interval (12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ) during which the

associated Test must be performed at least one time. Performance of the

Test initiates the subsequent interval. Although the Frequency is stated

as 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , an extension of the time interval to 1.25 times the interval

specified in the Frequency is allowed by TR 3.0.2 for operational

flexibility. The measurement of this interval continues at all times, even

when the TR is not required to be met per TR 3.0.1 (such as when the

equipment is inoperable, a variable is outside specified limits, or the unit

is outside the Applicability of the TRMS). If the interval specified by

TR 3.0.2 is exceeded while the unit is in a MODE or other specified

condition in the Applicability of the TRMS, and the performance of the

Test is not otherwise modified (refer to Examples 1.4-3 and 1.4-4), then

TR 3.0.3 becomes applicable.

(continued)

Frequency

1.4 Brunswick

Unit 2 1.4-3 Revision No. 23 TRMS 1.4 Frequency

EXAMPLES EXAMPLE 1.4-1 (continued)

If the interval as specified by TR 3.0.2 is exceeded while the unit is not in

a MODE or other specified condition in the Applicability of the TRMS for

which performance of the TR is required, the Test must be performed

within the Frequency requirements of TR 3.0.2 prior to entry into the

MODE or other specified condition. Failure to do so would result in a

violation of TR 3.0.4.

EXAMPLE 1.4-2 TEST REQUIREMENTS TEST FREQUENCY Verify flow is within limits.

Once within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 25% RTP AND 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter Example 1.4-2 has two Frequencies. The first is a one time performance

Frequency, and the second is of the type shown in Example 1.4-1. The

logical connector "AND" indicates that both Frequency requirements must be met. Each time reactor power is increased from a power level

< 25% RTP to 25% RTP, the Test must be performed within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The use of "once" indicates a single performance will satisfy the specified

Frequency (assuming no other Frequencies are connected by "AND

"). This type of Frequency does not qualify for the extension allowed by

TR 3.0.2.

(continued)

Frequency

1.4 Brunswick

Unit 2 1.4-4 Revision No. 23 TRMS 1.4 Frequency

EXAMPLES EXAMPLE 1.4-2 (continued) "Thereafter" indicates future performances must be established per

TR 3.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example). If reactor power decreases to < 25% RTP, the measurement of both intervals stops. New intervals start upon

reactor power reaching 25% RTP.

EXAMPLE 1.4-3 TEST REQUIREMENTS TEST FREQUENCY

NOTE----------------------------

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after 25% RTP.

Perform channel adjustment.

7 days The interval continues whether or not the unit operation is < 25% RTP

between performances.

As the Note modifies the required performance of the Test, it is construed to be part of the "specified Frequency." Should the 7 day interval be

exceeded while operation is < 25% RTP, this Note allows 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

power reaches 25% RTP to perform the Test. The Test is still considered to be within the "specified Frequency." Therefore, if the Test

were not performed within the 7 day interval (plus the extension allowed

by TR 3.0.2), but operation was < 25% RTP, it would not constitute a

failure of the TR or failure to meet the TRMS. Also, no violation of

TR 3.0.4 occurs when changing MODES, even with the 7 day Frequency

not met, provided operation does not exceed 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with power 25% RTP.

(continued)

Frequency

1.4 Brunswick

Unit 2 1.4-5 Revision No. 23 TRMS 1.4 Frequency

EXAMPLES EXAMPLE 1.4-3 (continued)

Once the unit reaches 25% RTP, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months would be allowed for

completing the Test. If the Test were not performed within this 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

interval, there would then be a failure to perform a Test within the

specified Frequency, and the provisions of TR 3.0.3 would apply.

EXAMPLE 1.4-4 TEST REQUIREMENTS TEST FREQUENCY

NOTE-------------------------

Only required to be met in MODE 1.

Verify leakage rates are within limits.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Example 1.4-4 specifies that the requirements of this Test do not have to

be met until the unit is in MODE 1. The interval measurement for the

Frequency of this Test continues at all times, as described in

Example 1.4-1. However, the Note constitutes an "otherwise stated" exception to the Applicability of this Test. Therefore, if the Test were not

performed within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (plus the extension allowed by TR 3.0.2)

interval, but the unit was not in MODE 1, there would be no failure of the

TR nor failure to meet the TRMS. Therefore, no violation of TR 3.0.4

occurs when changing MODES, even with the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency

exceeded, provided the MODE change was not made into MODE 1. Prior

to entering MODE 1 (assuming again that the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Frequency were

not met), TR 3.0.4 would require satisfying the TR.

Brunswick Unit 2 2.0-1 Revision No. 23 2.0 Not used.

TRMS Applicability

3.0 Brunswick

Unit 2 3.0-1 Revision No. 23 3.0 TECHNICAL REQUIREMENTS MANUAL SPECIFICATION (TRMS) APPLICABILITY

TRMS 3.0.1 TRMSs shall be met during the MODES or other specified conditions in the Applicability, except as provided in TRMS 3.0.2.

TRMS 3.0.2 Upon discovery of a failure to meet a TRMS, the Required Compensatory Measures of the associated Conditions shall be met, except as provided

in TRMS 3.0.5.

If the TRMS is met or is no longer applicable prior to the expiration of the

specified Completion Times(s), completion of the Required

Compensatory Measure(s) is not required, unless otherwise stated.

TRMS 3.0.3 Not used.

TRMS 3.0.4 When a TRMS is not met, entry into a MODE or other specified condition in the Applicability shall not be made except when the associated

COMPENSATORY MEASURES to be entered permit continued operation

in the MODE or other specified condition in the applicability for an

unlimited period of time. This TRMS shall not prevent changes in

MODES or other specified conditions in the Applicability that are required

to comply with COMPENSATORY MEASURES, or that are part of a

shutdown of the unit.

Exceptions to this TRMS are stated in the individual TRMSs. These

exceptions allow entry into MODES or other specified conditions in the

Applicability when the associated COMPENSATORY MEASURES to be

entered allow unit operation in the MODE or other specified condition in

the Applicability only for a limited period of time.

TRMS 3.0.5 Equipment removed from serv ice or declared inoperable to comply with COMPENSATORY MEASURES may be returned to service under

administrative control solely to perfo rm testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an

exception to TRMS 3.0.2 for the system returned to service under

administrative control to perform the required testing.

TR Applicability

3.0 Brunswick

Unit 2 3.0-2 Revision No. 23 3.0 TEST REQUIREMENT (TR) APPLICABILITY

TR 3.0.1 TRs shall be met during the MODES or other specified conditions in the Applicability for individual TRMSs, unless otherwise stated in the TR.

Failure to meet a Test whether such failure is experienced during the

performance of the Test or between performances of the Test, shall be

failure to meet the TRMS. Failure to perform a Test within the specified

Frequency shall be failure to meet the TRMS except as provided in TR

3.0.3. Tests

do not have to be performed on inoperable equipment or

variables outside specified limits.

TR 3.0.2 The specified Frequency for each TR is met if the Test is performed within 1.25 times the interval specified in the Frequency, as measured

from the previous performance or as measured from the time a specified condition of the Frequency is met.

For Frequencies specified as "once," the above interval extension does

not apply. If a Completion Time requires periodic performance on a "once

per " basis, the above Frequency extension applies to each

performance after the initial performance.

Exceptions to this TRMS are stated in the individual TRMSs.

TR 3.0.3 If it is discovered that a Test was not performed within its specified Frequency, then compliance with the requirement to declare the TRMS

not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up

to the limit of the specified Frequency, whichever is less. This delay

period is permitted to allow performance of the Test.

If the Test is not performed within the delay period, the TRMS must

immediately be declared not met, and the applicable Condition(s) must be

entered.

When the Test is performed within the delay period and the Test is not

met, the TRMS must immediately be declared not met, and the applicable

Condition(s) must be entered.

(continued)

TR Applicability

3.0 Brunswick

Unit 2 3.0-3 Revision No. 23 3.0 TR APPLICABILITY (continued)

TR 3.0.4 Entry into a MODE or other specified condition in the Applicability of a TRMS shall not be made unless the TRMS's Tests have been met within

their specified Frequency. This provision shall not prevent entry into

MODES or other specified conditions in the Applicability that are required

to comply with COMPENSATORY MEASURES or that are part of a

shutdown of the unit.

Control Rod Drive Housing Support

3.1 Brunswick

Unit 2 3.1-1 Revision No. 23 3.1 CONTROL ROD DRIVE HOUSING SUPPORT TRMS 3.1 The control rod drive housing support shall be in place.

APPLICABILITY: MODES 1, 2, and 3.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. Control rod drive housing support not in place. A.1 Be in MODE 3

AND A.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Control Rod Drive Housing Support

3.1 Brunswick

Unit 2 3.1-2 Revision No. 23 TEST REQUIREMENTS TEST FREQUENCY TR 3.1.1 Verify the control rod drive housing support is in place by inspection after reassembly.

Once prior to

startup any time

control rod drive

housing support

has been disassembled

AND Once prior to

startup any time

maintenance has

been performed in

the control rod

drive housing

support area

Brunswick Unit 2 3.2-1 Revision No. 23 3.2 Not used.

Control Rod Block Instrumentation

3.3 Brunswick

Unit 2 3.3-1 Revision No. 23 3.3 CONTROL ROD BLOCK INSTRUMENTATION TRMS 3.3 The control rod block instrumentation for each Function in Table 3.3-1 shall be OPERABLE. APPLICABILITY: According to Table 3.3-1.

COMPENSATORY MEASURES

NOTE -----------------------------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. --------------NOTE---------------

Only applicable for

Functions 1, 2 and 3.

One or more functions with one or more required

channels inoperable. A.1 Restore channel(s) to OPERABLE status.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months B. One or more functions with control rod block capability

not maintained.

OR Required Compensatory Measures and associated

Completion Time of

Condition A not met. B.1 Place one channel in trip. 1 hour`

Control Rod Block Instrumentation

3.3 Brunswick

Unit 2 3.3-2 Revision No. 23 TEST REQUIREMENTS

NOTES ----------------------------------------------------------

1. Refer to Table 3.3-1 to determine which TRs apply for each Control Rod Block Instrumentation Function. 2. When a channel is placed in an inoperable status solely for performance of required Tests, entry into associated Conditions and Required Compensatory Measures may be delayed

for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains control rod block capability. ------------------------------------------------------------------------------------------------------------------------------- TEST FREQUENCY TR 3.3.1 ---------------------------------NOTE-------------------------------

Not required to be performed when entering MODE 2

from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

7 days TR 3.3.2 Perform CHANNEL FUNCTIONAL TEST.

92 days TR 3.3.3 --------------------------------NOTES------------------------------

Neutron detectors are excluded.

Perform CHANNEL CALIBRATION.

24 months TR 3.3.4 Adjust recirculation drive flow to conform to reactor flow. Once within

7 days after

reaching equilibrium

conditions

following refueling

outage (continued)

Control Rod Block Instrumentation

3.3 Brunswick

Unit 2 3.3-3 Revision No. 23 TEST REQUIREMENTS (continued)

TEST FREQUENCY TR 3.3.5 ---------------------------------NOTE-------------------------------

For Function 1.d, not required to be performed when

entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after

entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

184 days Control Rod Block Instrumentation

3.3 Brunswick

Unit 2 3.3-4 Revision No. 36 Table 3.3-1 (page 1 of 1)

Control Rod Block Instrumentation

FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS

REQUIRED CHANNELS

TEST REQUIREMENTS

ALLOWABLE VALUE

1. Average Power Range Monitors

a. Upscale (Flow Biased)

b. Inoperative

c. Downscale

d. Upscale (Fixed)

1

1,2 1 2

3

3 3 3

TR 3.3.3 TR 3.3.4 TR 3.3.5 TR 3.3.5 TR 3.3.5

TR 3.3.3 TR 3.3.5

0.55W + 55.0%RTP (a) and 109.3% RTP NA 1.1% APRM power 14% RTP

2. Source Range Monitors

a. Detector Not Full In

b. Upscale

c. Inoperative

d. Downscale

2 (b),5 2(c),5 2(c),5 2 (b),5

2 2 2 2

TR 3.3.1 TR 3.3.1

NA 5 x 10 5 cps NA 3 cps

3. Intermediate Range Monitors

a. Detector Not Full In

b. Upscale

c. Inoperable

d. Downscale

2,5 2,5

2,5 2 (e),5

6 6

TR 3.3.1 TR 3.3.1

NA 108/125 of full scale

NA 3/125 of full scale 4. Scram Discharge Volume Water Level-High

1,2,5(f) 1 (g) TR 3.3.2 TR 3.3.3 73 gallons

(a) [0.55(W - W) + 55.0% RTP] when Technical Specification 3.3.1.1, Function 2.b, is reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating." The value of W is defined in plant procedures. (b) Bypassed when detector is reading > 100 cps or Intermediate Range Monitor (IRM) channels are on Range 3 or higher.

(c) Bypassed when associated IRM channels are on Range 8 or higher.

(d) Deleted.

(e) Bypassed when IRM channels are on Range 1.

(f) With any control rod withdrawn from a core cell containing one or more fuel assemblies. Not applicable to control rods removed per Technical Specification 3.10.5, "Single Control Rod Drive (CRD) Removal-Refueling," or 3.10.6, "Multiple Control Rod Withdrawal-Refueling." (g) Signal is contained in Channel A logic only.

Accident Monitoring Instrumentation

3.4 Brunswick

Unit 2 3.4-1 Revision No. 60 3.4 ACCIDENT MONITORING INSTRUMENTATION TRMS 3.4 The accident monitoring instrumentation for each Function in Table 3.4-1 shall be OPERABLE. APPLICABILITY: According to Table 3.4-1.

COMPENSATORY MEASURES

NOTES ----------------------------------------------------------

1. TRMS 3.0.4 is not applicable.

2. Separate Condition entry is allowed for each Function.

CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. --------------NOTE---------------

Only applicable to

Functions 1, 2, 3, 6, and 7.

One or more Functions with one required channel

inoperable. A.1 Restore required channel to OPERABLE status.

31 days B. One or more Functions with two required channels

inoperable.

OR --------------NOTE--------------

Only applicable to

Functions 4 and 5.

One or more Functions with one required channel

inoperable. B.1 Restore one required channel to OPERABLE

status. 7 days (continued)

Accident Monitoring Instrumentation

3.4 Brunswick

Unit 2 3.4-2 Revision No. 29 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME C. Required Compensatory Measure and associated

Completion Time not met. C.1 Submit a Special Report to the NRC outlining the

preplanned alternate

monitoring method, the

cause of the inoperability, and plans for restoring the

instrumentation to

OPERABLE status.

14 days TEST REQUIREMENTS TEST FREQUENCY TR 3.4.1 Perform CHANNEL CHECK.

31 days TR 3.4.2 Perform CHANNEL CALIBRATION except for Drywell and Suppression Chamber H 2 and O 2 Analyzers.

24 months TR 3.4.3 Perform CHANNEL CALIBRATION of the Drywell and Suppression Chamber H 2 and O 2 Analyzers.

92 days Accident Monitoring Instrumentation

3.4 Brunswick

Unit 2 3.4-3 Revision No. 60 Table 3.4-1 (page 1 of 1)

Accident Monitoring Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS 1. Suppression Chamber Atmosphere Temperature 2. Drywell Radiation

3. Safety/Relief Valve Position Indication

a. Primary-Sonic

b. Secondary-Temperature 4. Turbine Building Ventilation Monitor 5. Offgas Stack Ventilation Monitor

6. Drywell and Suppression Chamber H 2 Analyzer 7. Drywell and Suppression Chamber O 2 Analyzer 1,2 1,2,3 1,2

1,2,3 1,2,3 1,2 1,2 2 2 1 per valve

1 1 1 1

Chloride Intrusion Monitors

3.5 Brunswick

Unit 2 3.5-1 Revision No. 32

3.5 CHLORIDE

INTRUSION MONITORS TRMS 3.5 The chloride intrusion monitor channels for each Function in Table 3.5-1 shall be OPERABLE. APPLICABILITY: MODE 1 and 2.

COMPENSATORY MEASURES

NOTE -----------------------------------------------------------

Operation may continue with one or two Functions inoperable.

CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. Three or four Functions with one or more required

channels inoperable. A.1 Sample one parameter monitored by the

inoperable Function(s).

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months AND Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

thereafter

Chloride Intrusion Monitors

3.5 Brunswick

Unit 2 3.5-2 Revision No. 23 TEST REQUIREMENTS

NOTE -----------------------------------------------------------

Refer to Table 3.5-1 to determine which TRs apply for each Chloride Intrusion Monitor Function.

TEST FREQUENCY TR 3.5.1 Perform CHANNEL CHECK.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TR 3.5.2 Perform CHANNEL FUNCTIONAL TEST.

31 days TR 3.5.3 Perform CHANNEL CALIBRATION.

184 days TR 3.5.4 Perform CHANNEL CALIBRATION.

24 months

Chloride Intrusion Monitors

3.5 Brunswick

Unit 2 3.5-3 Revision No. 23 Table 3.5-1 (page 1 of 1)

Chloride Intrusion Monitors FUNCTION REQUIRED CHANNELS TEST REQUIREMENTS ALLOWABLE VALUE 1. Chloride Leak Detectors in the Condenser Hotwell

Outlet Headers 2. Chloride Leak Detector in the Condensate Pump

Discharge (Wide Range or

Narrow Range)

a. Wide Range

b. Narrow Range 3. Chloride Leak Detector in the Inlet to the Condensate

Filter Demineralizer 4. Chloride Leak Detector in the Inlet to the Deep Bed

Demineralizer 4

1

1 1 TR 3.5.1

TR 3.5.2

TR 3.5.4

TR 3.5.1

TR 3.5.2

TR 3.5.3

TR 3.5.1

TR 3.5.2

TR 3.5.3

TR 3.5.1

TR 3.5.2

TR 3.5.3 2.0 mhos/cm

10 mhos/cm 0.5 mhos/cm 0.5 mhos/cm 0.5 mhos/cm Bus Power Monitors

3.6 Brunswick

Unit 2 3.6-1 Revision No. 31 3.6 BUS POWER MONITORS TRMS 3.6 The alarm function of the Emergency Core Cooling System (ECCS) and Reactor Core Isolation Cooling (RCIC) System actuation instrumentation

bus power monitors in Table 3.6-1 shall be OPERABLE.

NOTE---------------------------------------------

The annunciator function may be removed from operation for performance of troubleshooting for up to 30 minutes provided no work on the associated

power supplies is in progress. --------------------------------------------------------------------------------------------------

APPLICABILITY: According to Table 3.6-1.

COMPENSATORY MEASURES

NOTE -----------------------------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One or more channels inoperable. A.1 Verify bus power availability to the system's

logic. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

thereafter B. Required Compensatory Measure and associated

Completion Time not met. B.1 Declare associated supported equipment

inoperable.

Immediately

Bus Power Monitors

3.6 Brunswick

Unit 2 3.6-2 Revision No. 23 TEST REQUIREMENTS TEST FREQUENCY TR 3.6.1 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months

Bus Power Monitors

3.6 Brunswick

Unit 2 3.6-3 Revision No. 23 Table 3.6-1 (page 1 of 1)

Bus Power Monitors FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER BUS 1. Core Spray System Bus Power Monitor 2. Low Pressure Coolant Injection (Residual Heat Removal System)

Bus Power Monitor 3. High Pressure Cooling Injection System Bus Power Monitor 4. Automatic Depressurization System Bus Power Monitor 5. RCIC System Bus Power Monitor 1,2,3 4 (a),5 (a) 1,2,3 4 (a),5 (a) 1,2,3 1,2 (a),3 (a) 1,2,3 1 1 1 1 1 (a) When associated subsystems are required to be OPERABLE.

ADS Inhibit Switch

3.7 Brunswick

Unit 2 3.7-1 Revision No. 23 3.7 AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) INHIBIT SWITCH TRMS 3.7 Two channels of the ADS Inhibit Switch Function shall be OPERABLE.

APPLICABILITY: MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One or both ADS Inhibit Switches not in the

automatic position. A.1 Place both ADS Inhibit Switches in the automatic

position.

AND A.2 Declare ADS inoperable.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. One or both ADS Inhibit Switch channels inoperable.B.1 Declare ADS inoperable. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

TEST REQUIREMENTS TEST FREQUENCY TR 3.7.1 Verify ADS Inhibit Switches are in the automatic position.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TR 3.7.2 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months

Suppression Chamber Water Temperature

3.8 Brunswick

Unit 2 3.8-1 Revision No. 31

3.8 SUPPRESSION

CHAMBER WATER TEMPERATURE INSTRUMENTATION TRMS 3.8 Two suppression chamber water temperature instrumentation channels shall be OPERABLE with 11 OPERABLE RTD inputs per channel.

NOTE---------------------------------------------

The annunciator function may be removed from operation for performance of troubleshooting for up to 30 minutes provided the associated function

maintains monitoring capability. --------------------------------------------------------------------------------------------------

APPLICABILITY: MODE 1, 2 and 3.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One suppression chamber water temperature

instrumentation channel

inoperable. A.1 Restore channel to OPERABLE status.

7 days B. Two suppression chamber water temperature

instrumentation channels

inoperable. B.1 Restore one channel to OPERABLE status.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months C. Required Compensatory Measure and associated

Completion Time not met. C.1 Verify suppression chamber water

temperature is within

required limits.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

thereafter

Suppression Chamber Water Temperature Instrumentation

3.8 Brunswick

Unit 2 3.8-2 Revision No. 23 TEST REQUIREMENTS TEST FREQUENCY TR 3.8.1 Perform CHANNEL CHECK.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TR 3.8.2 Perform CHANNEL FUNCTIONAL TEST.

31 days TR 3.8.3 Perform CHANNEL CALIBRATION. The Allowable Value of the alarm shall be 95°F. 24 months Seismic Monitoring Instrumentation

3.9 Brunswick

Unit 2 3.9-1 Revision No. 47 3.9 SEISMIC MONITORING INSTRUMENTATION TRMS 3.9 Seismic monitoring instrumentation in Table 3.9-1 shall be OPERABLE.

APPLICABILITY: At all times.

COMPENSATORY MEASURES

NOTE -----------------------------------------------------------

Separate Condition entry is allowed for each instrument.

CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One or more seismic monitoring instruments

inoperable. A.1 Restore seismic monitoring instrument to

OPERABLE status.

31 days B. Required Compensatory Measure A.1 and associated

Completion Time not met. B.1 Submit a Special Report to the NRC outlining the

cause of the malfunction

and plans for restoring the

instrument to OPERABLE

status. 14 days C. --------------NOTE---------------

Required Compensatory

Measures C.2 and C.3 shall

be completed whenever

Condition C is entered.

OBE exceedance light is

energized. C.1 Restore seismic monitoring instrument to

OPERABLE status.

AND C.2 Perform TR 3.9.3.

AND C.3 Submit a Special Report to the NRC describing the

magnitude and frequency

spectrum and effect upon

facility features important

to safety. The magnitude

and frequency spectrum of

the event shall be based

upon data retrieved and

analyzed from the

actuated instruments.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

10 days

14 days Seismic Monitoring Instrumentation

3.9 Brunswick

Unit 2 3.9-2 Revision No. 47 TEST REQUIREMENTS

NOTE -----------------------------------------------------------

Refer to Table 3.9-1 to determine which TRs apply to each seismic monitoring instrument.

TEST FREQUENCY TR 3.9.1 Perform CHANNEL CHECK.

31 days TR 3.9.2 Perform CHANNEL FUNCTIONAL TEST.

184 days TR 3.9.3 Perform CHANNEL CALIBRATION.

24 months

Seismic Monitoring Instrumentation

3.9 Brunswick

Unit 2 3.9-3 Revision No. 47 Table 3.9-1 (page 1 of 1)

Seismic Monitoring Instrumentation INSTRUMENTS AND SENSOR LOCATIONS MEASUREMENT RANGE REQUIRED INSTRUMENTS TEST REQUIREMENTS 1. Passive Triaxial Peak Shock Recorders

a. Reactor Building Basement/Equipment

Drain Tank (-17' level) b. Reactor Building RHR Heat Exchanger Support

(+20' level) c. Reactor Building Refueling Area (+117'

level) 2-25 Hz 2-25 Hz 2-25 Hz 1 1 1 TR 3.9.3 TR 3.9.3 TR 3.9.3 2. Active Triaxial Accelerometers

a. Reactor Building

(+89'4" level)

b. Reactor Building

(-17' level)

3. Active Seismic Recording System

a. Control Room 0-1.0g 0-1.0g

0-1.0g 1 1

1 TR 3.9.1

TR 3.9.2

TR 3.9.3

TR 3.9.1

TR 3.9.2

TR 3.9.3

TR 3.9.1

TR 3.9.2

TR 3.9.3

Intake Canal High Water Level Instrumentation 3.10 Brunswick Unit 2 3.10-1 Revision No. 31 3.10 INTAKE CANAL HIGH WATER LEVEL INSTRUMENTATION TRMS 3.10 The intake canal high water level instrumentation shall be OPERABLE.

NOTE---------------------------------------------

The annunciator function may be removed from operation for performance of troubleshooting for up to 30 minutes provided a method to monitor water

level is maintained. --------------------------------------------------------------------------------------------------

APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. Intake canal high water level instrumentation inoperable. A.1 Verify intake canal water level is 17'6" mean sea level USGS datum.

Immediately

AND Once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

thereafter

TEST REQUIREMENTS TEST FREQUENCY TR 3.10.1 Perform CHANNEL FUNCTIONAL TEST.

92 days TR 3.10.2 Perform CHANNEL CALIBRATION.

24 months

Primary Containment Isolation Instrumentation 3.11 Brunswick Unit 2 3.11-1 Revision No. 23 3.11 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION TRMS 3.11 The primary containment instrumentation for each Function in Table 3.11-1 shall be OPERABLE. APPLICABILITY: MODES 1, 2, and 3.

COMPENSATORY MEASURES

NOTE -----------------------------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One or more required channels inoperable.

A.1 ---------------NOTE-------------

An inoperable channel

need not be placed in trip

where this would cause

the isolation to occur. In

this case, if the channel is

not restored to

OPERABLE status within

the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Completion

Time, Condition B must be

entered.

-- Place channel in trip.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (continued)

Primary Containment Isolation Instrumentation 3.11 Brunswick Unit 2 3.11-2 Revision No. 51 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME B. Required Compensatory Measure and associated

Completion Time not met.

OR One or more functions with isolation capability not

maintained. B.1 Restore isolation capability.

OR B.2.1 Prepare a plan to restore channel(s) to OPERABLE

status and assign a

responsible individual to

ensure the restoration plan

is carried out.

AND B.2.2 Initiate a condition report.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months TEST REQUIREMENTS

NOTE -----------------------------------------------------------

When a channel is placed in an inoperable status solely for performance of required Tests, entry into associated Conditions and Required Compensatory Measures may be delayed for up

to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains isolation capability.

TEST FREQUENCY TR 3.11.1 Perform CHANNEL FUNCTIONAL TEST.

184 days TR 3.11.2 Perform CHANNEL CALIBRATION.

24 months TR 3.11.3 Perform LOGIC SYSTEM FUNCTIONAL TEST and simulated automatic operation.

24 months Primary Containment Isolation Instrumentation 3.11 Brunswick Unit 2 3.11-3 Revision No. 51 Table 3.11-1 (page 1 of 1)

Primary Containment Isolation Instrumentation FUNCTION REQUIRED CHANNELS PER TRIP SYSTEM ALLOWABLE VALUE 1. Main Steam Line Tunnel Temperature-High (except for Main Steam Isolation

Valve Pit instruments) 2. Turbine Building Area Temperature-High 2 (a) 4 (b) 197°F 197°F (a) A channel is OPERABLE if 2 of 3 instruments in the channel are OPERABLE.

(b) A channel is OPERABLE if 2 of 4 instruments in the channel are OPERABLE.

CREV System Instrumentation 3.12 Brunswick Unit 2 3.12-1 Revision No. 23 3.12 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM INSTRUMENTATION TRMS 3.12 The CREV System instrumentation for each Function in Table 3.12-1 shall be OPERABLE. APPLICABILITY: According to Table 3.12-1.

COMPENSATORY MEASURES

NOTE -----------------------------------------------------------

Separate Condition entry is allowed for each Function.

CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One or both Chlorine Isolation Functions with one

chlorine detector inoperable

in one or both associated

trip subsystems. A.1 Restore detector(s) to OPERABLE status.

7 days B. Required Compensatory Measure and associated

Completion Time of

Condition A not met. B.1 Place the CREV System in the chlorine protection

mode of operation.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months C. One or both Chlorine Isolation Functions with two

chlorine detectors

inoperable in one or both

associated trip subsystems. C.1 Place the CREV System in the chlorine protection

mode of operation.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (continued)

CREV System Instrumentation 3.12 Brunswick Unit 2 3.12-2 Revision No. 57 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME D. One Control Building Intake Air Duct Detector InoperableD.1 Restore detector(s) to OPERABLE status.

7 days E. Required Compensatory Measure and associated

Completion Time of

Condition D not met. E.1 Place CREV System in the radiation/smoke protection

mode of operation.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months F. Both Control Building Intake Air Duct Detectors

Inoperable F.1 Place the CREV System in the radiation/smoke

protection mode of

operation.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months CREV System Instrumentation 3.12 Brunswick Unit 2 3.12-3 Revision No. 23 TEST REQUIREMENTS

NOTE -----------------------------------------------------------

Refer to Table 3.12-1 to determine which TRs apply for each CREV System Instrumentation

Function.

TEST FREQUENCY TR 3.12.1 Perform CHANNEL FUNCTIONAL TEST.

31 days TR 3.12.2 Perform CHANNEL FUNCTIONAL TEST.

184 days TR 3.12.3 Perform CHANNEL CALIBRATION.

12 months

CREV System Instrumentation 3.12 Brunswick Unit 2 3.12-4 Revision No. 57 Table 3.12-1 (page 1 of 1)

CREV System Instrumentation FUNCTION

APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED DETECTORS PER TRIP SYSTEM TEST REQUIREMENTS

ALLOWABLE VALUE

1. Chlorine Isolation

a. Control Building Air Intake (Local)

b. Chlorine Tank Car Area (Remote)

(a)

4(b) 4(b)

TR 3.12.1

TR 3.12.3 TR 3.12.1

TR 3.12.3

5 ppm 5 ppm

2. Control Room Envelope Smoke Protection

a. Control Building Intake Air Duct Smoke Detectors

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

1

TR 3.12.2

NA

(a) With chlorine tank car within the exclusion area.

(b) Four OPERABLE detectors per Trip System, consisting of two detectors per trip subsystem.

(c) During movement of irradiated fuel assemblies in secondary containment.

RCS Chemistry 3.13 Brunswick Unit 2 3.13-1 Revision No. 23 3.13 REACTOR COOLANT SYSTEM (RCS) CHEMISTRY TRMS 3.13 The chemistry of the RCS shall be maintained within the limits of Table 3.13-1. APPLICABILITY: According to Table 3.13-1.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. Conductivity greater than the limit of Table 3.13-1 but

< 10mhos/cm at 25

°C in MODE 1, 2, or 3.

OR Chloride concentration greater than the limit of

Table 3.13-1 but < 0.5 ppm

in MODE 1, 2, or 3. A.1 Verify by administrative means that operation

under this condition shall

not exceed 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per

year. AND A.2 ---------------NOTE-------------

TRMS 3.0.4 is not

applicable.

-- Restore chemistry parameter(s) to within

limit(s).

Immediately

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months B. Required Compensatory Measure A.1 and associated

Completion Time not met. B.1 Submit a Special Report to the NRC outlining the

cause of the

non-compliance, plans for

restoring the parameter to

within limit, and the impact

of the non-compliance on

RCS integrity.

14 days (continued)

RCS Chemistry 3.13 Brunswick Unit 2 3.13-2 Revision No. 23 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME C. Required Compensatory Measure A.2 and associated

Completion Time not met.

OR Conductivity 10mhos/cm @ 25°C in MODE 1, 2, or 3.

OR Chloride concentration 0.5 ppm in MODE 1, 2, or 3. C.1 Be in MODE 3.

AND C.2 Be in MODE 4.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months D. Conductivity greater than the limit of Table 3.13-1 in

MODE 4 or 5.

OR Chloride concentration greater than the limit of

Table 3.13-1 in MODE 4

or 5. D.1 Restore chemistry parameter to within limit.

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months

RCS Chemistry 3.13 Brunswick Unit 2 3.13-3 Revision No. 23 TEST REQUIREMENTS TEST FREQUENCY TR 3.13.1 ---------------------------------NOTE-------------------------------

Not required to be met if all continuous recording

conductivity monitors are inoperable and TR 3.13.2 is

satisfied.

Record RCS conductivity.

Continuously TR 3.13.2 ---------------------------------NOTE-------------------------------

Not required to be met if TR 3.13.1 is satisfied.

Analyze an RCS sample for conductivity.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TR 3.13.3 Analyze an RCS sample for conductivity.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months TR 3.13.4 Analyze an RCS sample for chloride concentration. 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

RCS Chemistry 3.13 Brunswick Unit 2 3.13-4 Revision No. 23 Table 3.13-1 (page 1 of 1)

RCS Chemistry Limits CHEMISTRY PARAMETER

APPLICABLE MODES OR OTHER SPECIFIED CONDITION LIMIT

1. Chlorides 1 2,3,4,5 < 0.5 ppm

< 0.2 ppm

2. Conductivity 1,2 3,4,5 < 2.0 mhos/cm @ 25

°C < 10.0 mhos/cm @ 25

°C Structural Integrity 3.14 Brunswick Unit 2 3.14-1 Revision No. 65 3.14 STRUCTURAL INTEGRITY TRMS 3.14 The structural integrity of the ASME Code Class 1, 2, 3, MC, and CC components shall be maintained.

APPLICABILITY: MODES 1, 2, 3, 4, and 5.

COMPENSATORY MEASURES

NOTE -----------------------------------------------------------------

Separate Condition entry is allowed for each component.

CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. -------------NOTE------------

Required Action A.1 shall be

completed if this Condition is

entered.

Unevaluated indication or

failed inspection is found in

an ASME Code Class 1, 2, 3

MC, or CC component(s), or

structural support

component(s). A.1 Evaluate the impact of the indication or failed

inspection on

OPERABILITY and

structural integrity of the affected systems, structures, or components.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. Structural integrity of any of ASME Code Class 1

component(s) not

maintained. B.1 Declare the associated system, structure, or

component inoperable.

AND B.2 Initiate action to isolate the affected component(s).

AND B.3 Restore the structural integrity of affected

component(s) to within

limits. Immediately

Immediately

Prior to entering

MODES 1, 2, or 3 (continued)

Structural Integrity 3.14 Brunswick Unit 2 3.14-2 Revision No. 65 COMPENSATORY MEASURES (continued) CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME C. Structural integrity of any of ASME Code Class 2 or

Class 3 component(s) not

maintained. C.1.1 Initiate action to isolate the affected component(s).

OR C.1.2 Declare the affected component(s)

inoperable/nonfunctional.

AND C.2 Initiate action to restore structural integrity of

affected component(s) to

within limits.

AND C.3 Restore the structural integrity of affected

component(s) to within

limits. Immediately

Immediately

Prior to entering

MODES 1, 2, or 3 D. Structural integrity of any of ASME Code Class MC or

Class CC component(s) not

maintained. D.1 Declare the affected component(s)

inoperable/nonfunctional.

AND D.2 Initiate action to restore structural integrity of

affected component(s) to

within limits.

AND D.3 Restore the structural integrity of affected

component(s) to within

limits. Immediately

Immediately

Prior to entering

MODES 1, 2, or 3 E. Condition A, B, C, or D or associated Completion Time

not met. E.1 Declare the associated systems, structures, or

components

inoperable/nonfunctional.

Immediately

Structural Integrity 3.14 Brunswick Unit 2 3.14-3 Revision No. 65 TEST REQUIREMENTS TEST FREQUENCY TR 3.14.1 Verify the structural integrity of ASME Code Class 1, 2, 3, MC, and CC components.

In accordance with

the Inservice

Inspection

Program Brunswick Unit 2 3.15-1 Revision No. 23 3.15 Not used.

Service Water System OPERABILITY-Shutdown 3.16 Brunswick Unit 2 3.16-1 Revision No. 58 3.16 SERVICE WATER SYSTEM OPERABILITY-SHUTDOWN TRMS 3.16 The Service Water System shall be OPERABLE with: a. Three OPERABLE site Nuclear Service Water (NSW) pumps and

b. Two OPERABLE Service Water (SW) pumps (any combination of NSW or Conventional Service Water (CSW) pumps) powered from

separate emergency buses and capable of supplying the nuclear

service water header. APPLICABILITY: MODES 4 and 5.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One required NSW pump inoperable due to inoperable

Unit 2 nuclear service water

header. --------------------NOTE-------------------

TRMS 3.0.4 is not applicable.

A.1 Verify by administrative means that two Unit 1

NSW pumps are

OPERABLE.

AND A.2 Administratively control nuclear service water

header valves to ensure

cooling water to the

required diesel generators.

AND A.3 Verify two Unit 2 SW pumps are OPERABLE on

the conventional service

water header.

AND

Immediately

Immediately (continued)

Service Water System OPERABILITY-Shutdown 3.16 Brunswick Unit 2 3.16-2 Revision No. 58 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. (continued) A.4 Administratively control valves to isolate

OPERABLE CSW pumps

and required loads from

the inoperable nuclear

header. AND A.5 Restore required NSW pump. Immediately

14 days B. One required NSW pump inoperable for reasons other

than Condition A. B.1 Restore required NSW pump. 7 days C. Required Compensatory Measure and associated

Completion Time of

Condition A or B not met.

OR Two or more required NSW pumps inoperable. C.1 Declare required diesel generators inoperable.

Immediately D. One required SW pump inoperable. D.1 Restore required SW pump. 7 days E. Required Compensatory Measure and associated

Completion Time of

Condition D not met.

OR Two required SW pumps inoperable. E.1 Declare required supported equipment

inoperable.

Immediately

Service Water System OPERABILITY-Shutdown 3.16 Brunswick Unit 2 3.16-3 Revision No. 33 TEST REQUIREMENTS TEST FREQUENCY TR 3.16.1 ---------------------------------NOTE-----------------------------

Isolation of flow to individual components does not

render the Service Water System inoperable.

Verify each Service Water System manual, power operated, and automatic valve in the flow paths servicing safety related systems or components, that is

not locked, sealed, or otherwise secured in position, is

in the correct position.

31 days TR 3.16.2 --------------------------------NOTES--------------------------- 1. A single test at the specified Frequency will satisfy this test for both units. 2. Isolation of flow to individual components does not render the Service Water System

inoperable.

Verify automatic transfer of each diesel generator cooling water supply from the normal service water

supply to the alternate service water supply on low

diesel generator jacket cooling water supply pressure.

92 days TR 3.16.3 ---------------------------------NOTE-----------------------------

Isolation of flow to individual components does not

render the Service Water System inoperable.

Verify each required Service Water System automatic component actuates on an actual or simulated

initiation signal.

24 months Service Water System-Shutdown Operations 3.17 Brunswick Unit 2 3.17-1 Revision No. 23 TEST REQUIREMENTS (continued) 3.17 SERVICE WATER SYSTEM-SHUTDOWN OPERATIONS TRMS 3.17 The conventional service water header may be removed from operation by stopping the service water pumps to permit isolating and draining the

nuclear service water header for maintenance provided:

a. The conventional service water header is lined up to supply cooling to required ECCS loads; b. The draining/maintenance on the nuclear service water header will not affect the Conventional Service Water System or the lineup described

in TRMS 3.17.a above; c. Average Reactor Coolant System (RCS) coolant temperature is 100°F at the start of the evolution and the heatup rate is 10°F per hour; and d. Two dedicated, qualified members of the unit operational staff are assigned to manually initiate the conventional service water pumps in

response to: 1. Any event which requires ECCS actuation, or

2. RCS coolant temperature > 180

°F, or 3. A loss of offsite power. APPLICABILITY: MODES 4 and 5 with the nuclear service water header inoperable.

Service Water System-Shutdown Operations 3.17 Brunswick Unit 2 3.17-2 Revision No. 23 COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. Requirements of TRMS not met. A.1 Initiate action to restore conventional service water

header to operation.

OR A.2 Initiate action to restore nuclear service water

header to OPERABLE

status. Immediately

Immediately

TEST REQUIREMENTS TEST FREQUENCY TR 3.17.1 Verify the conventional service water header is lined up to supply cooling water for ECCS by verifying that

each valve servicing safety related equipment that is

not locked in the proper position is administratively

controlled in the proper position.

Prior to securing

all service water

pumps TR 3.17.2 Verify two way communications between the control room and the service water building.

Prior to securing

all service water

pumps AND 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter (continued)

Service Water System-Shutdown Operations 3.17 Brunswick Unit 2 3.17-3 Revision No. 23 TEST REQUIREMENTS (continued)

TEST FREQUENCY TR 3.17.3 Verify RCS coolant temperature is 180°F. 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months CREV System-Smoke Protection Mode 3.18 Brunswick Unit 2 3.18-1 Revision No. 23 3.18 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM-SMOKE PROTECTION MODE TRMS 3.18 The smoke protection mode of the CREV System shall be OPERABLE with two OPERABLE control room emergency filtration subsystems. APPLICABILITY: MODES 1, 2, 3, 4, and 5, During movement of irradiated fuel assemblies in the secondary containment.

COMPENSATORY MEASURES

NOTE -----------------------------------------------------------

Required Compensatory Measures to initiate condition reports need not be completed when

control room emergency filtration subsystem inoperability is due solely to planned maintenance

or surveillance testing.

CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One control room emergency filtration

subsystem inoperable. A.1 Restore control room emergency filtration

subsystem to OPERABLE

status. OR A.2.1 Prepare a plan to return the control room

emergency filtration

subsystem to OPERABLE

status and assign a

responsible individual to

ensure the restoration plan

is carried out.

AND A.2.2 Initiate a condition report.

7 days

7 days (continued)

CREV System-Smoke Protection Mode 3.18 Brunswick Unit 2 3.18-2 Revision No. 23 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME B. Two control room emergency filtration

subsystems inoperable. B.1 Prepare a plan to return the control room

emergency filtration

subsystems to

OPERABLE status and

assign a responsible

individual to ensure the

restoration plan is carried

out. AND B.2 Initiate a condition report.

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months TEST REQUIREMENTS TEST FREQUENCY TR 3.18.1 Verify the CREV System automatically diverts its inlet flow through the HEPA filters and charcoal adsorber

banks of the Control Room Emergency Filtration

System on an actual or simulated smoke detection

signal. 24 months CREV System-Chlorine Protection Mode 3.19 Brunswick Unit 2 3.19-1 Revision No. 23 3.19 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM-CHLORINE PROTECTION MODE TRMS 3.19 The chlorine protection mode of the CREV System shall be OPERABLE.

APPLICABILITY: When the chlorine tank car is located within the exclusion area.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. Chlorine protection mode of the CREV System

inoperable for reasons other

than inoperable chlorine

isolation instrumentation. A.1 Remove the chlorine tank car from the exclusion

area. OR A.2.1 Prepare a plan to return the chlorine protection

mode of the CREV

System to OPERABLE

status and assign a

responsible individual to

ensure the restoration plan

is carried out.

AND A.2.2 ---------------NOTE-------------

Condition report need not

be generated when

inoperability is due solely

to planned maintenance or

surveillance testing.

-- Initiate a condition report.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months CREV System-Chlorine Protection Mode 3.19 Brunswick Unit 2 3.19-2 Revision No. 23 TEST REQUIREMENTS TEST FREQUENCY TR 3.19.1 Verify the CREV Syst em automatically isolates on an actual or simulated chlorine detection signal and the

Control Room Emergency Filtration System cannot be

started by an actual or simulated smoke or radiation

detection signal.

24 months Flood Protection 3.20 Brunswick Unit 2 3.20-1 Revision No. 23 3.20 FLOOD PROTECTION TRMS 3.20 Intake canal water level shall be 17'6" Mean Sea Level USGS datum. APPLICABILITY: At all times.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. Intake canal water not within limit. A.1 Initiate applicable emergency procedure to

mitigate consequences of

flooding vital equipment.

AND A.2. Be in MODE 3.

AND A.3 Be in MODE 4.

Immediately

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months TEST REQUIREMENTS TEST FREQUENCY TR 3.20.1 ---------------------------------NOTE-------------------------------

Not required to be performed when intake canal water

level is < 15'0" mean sea level USGS datum.

Verify intake canal water level is 17'6" mean sea level USGS datum.

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Snubbers 3.21 Brunswick Unit 2 3.21-1 Revision No. 40 3.21 SNUBBERS TRMS 3.21 All hydraulic and mechanical snubbers shall be OPERABLE.

APPLICABILITY: When associated systems are required to be OPERABLE.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. ---------------NOTE--------------

Required Compensatory

Measure A.1 shall be

completed if this Condition is

entered.

One or more snubbers inoperable that are

associated with only one

train or subsystem of a

multiple train or subsystem

supported system or are

associated with a single

train or subsystem

supported system. A.1 Determine snubber failure mode and that supported

system is acceptable for

continued operation.

AND A.2 Restore snubber to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months B. ---------------NOTE--------------

Required Compensatory

Measure B.1 shall be

completed if this Condition is

entered.

One or more snubbers inoperable that are

associated with more than

one train or subsystem of a

multiple train or subsystem

supported system. B.1 Determine snubber failure mode and that supported

system is acceptable for

continued operation.

AND B.2 Restore snubber to OPERABLE status.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months C. Required Compensatory Measure and associated

Completion Time not met. C.1 Declare associated system(s) inoperable.

Immediately Snubbers 3.21 Brunswick Unit 2 3.21-2 Revision No. 66 TEST REQUIREMENTS TEST FREQUENCY TR 3.21.1 Perform snubber testing in accordance with the Snubber Program Plan.

In accordance with

AD-EG-BNP-1618, "Snubber Program

Plan."

Sealed Source Contamination 3.22 Brunswick Unit 2 3.22-1 Revision No. 23 3.22 SEALED SOURCE CONTAMINATION TRMS 3.22 Each sealed source containing radioactive material in excess of 100Ci of beta and/or gamma emitting material or in excess of 5Ci of alpha emitting material shall have < 0.005Ci of removable contamination. APPLICABILITY: At all times.

COMPENSATORY MEASURES

NOTE -----------------------------------------------------------

Separate Condition entry is allowed for each sealed source.

CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One or more sealed sources with removable

contamination 0.005Ci. A.1 Withdraw the sealed source from use.

AND A.2.1 Initiate action to decontaminate and repair

the sealed source.

OR A.2.2 Initiate action to dispose of the sealed source in

accordance with NRC

regulations.

AND A.3 Submit a Special Report to the NRC. Immediately

Immediately

12 months Sealed Source Contamination 3.22 Brunswick Unit 2 3.22-2 Revision No. 23 TEST REQUIREMENTS

NOTES ----------------------------------------------------------

1. Tests for leakage and/or contamination shall be performed by the licensee or other persons specifically authorized by the NRC or an Agreement State. 2. The test method shall have a detection sensitivity of 0.005Ci per test sample. ------------------------------------------------------------------------------------------------------------------------------- TEST FREQUENCY TR 3.22.1 --------------------------------NOTES------------------------------ 1. Startup sources and fission detectors previously subjected to core flux are excluded. 2. Sealed sources and fission detector sources that are stored and not being used are excluded.

Perform testing for leakage and/or contamination for each sealed source containing radioactive material

with a half-life > 30 days and in any form other than

gas, excluding hydrogen 3.

184 days TR 3.22.2 ---------------------------------NOTE-------------------------------

Not required to be performed if performed within the

previous 184 days.

Perform testing for leakage for each sealed source and fission detector source that is stored and not in

use.

Prior to use or

transfer to another

licensee TR 3.22.3 Perform testing of sealed sources transferred without a certificate indicating the last test date.

Prior to use (continued)

Sealed Source Contamination 3.22 Brunswick Unit 2 3.22-3 Revision No. 23 TEST REQUIREMENTS (continued)

TEST FREQUENCY TR 3.22.4 ---------------------------------NOTE-------------------------------

Not required to be performed for sealed startup

sources or fission detectors that are continuously

enclosed within a shielded mechanism.

Perform leak testing of each sealed startup source and fission detector.

Once within

31 days prior to

being subjected to

core flux

AND Once within

31 days prior to

being installed in

the core following

any repair or

maintenance Decay Time 3.23 Brunswick Unit 2 3.23-1 Revision No. 23 3.23 DECAY TIME TRMS 3.23 The reactor shall be subcritical for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . APPLICABILITY: During movement of irradiated fuel in the reactor pressure vessel.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. Reactor subcritical

< 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . A.1 Suspend movement of irradiated fuel in the

reactor pressure vessel.

Immediately

TEST REQUIREMENTS TEST FREQUENCY TR 3.23.1 Determine the reactor has been subcritical for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verification of the date and time of subcriticality.

Prior to movement

of irradiated fuel in

the reactor pressure vessel Communications 3.24 Brunswick Unit 2 3.24-1 Revision No. 23 3.24 COMMUNICATIONS TRMS 3.24 Direct communications shall be maintained between the control room and refueling platform personnel. APPLICABILITY: During CORE ALTERATIONS, except normal control rod movement.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. Direct communications between control room and

refueling platform personnel

not maintained. A.1 Suspend CORE ALTERATIONS except for

normal control rod

movement.

Immediately

TEST REQUIREMENTS TEST FREQUENCY TR 3.24.1 Verify the availability of direct communications between the control room and refueling platform

personnel.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Crane and Hoist OPERABILITY 3.25 Brunswick Unit 2 3.25-1 Revision No. 23 3.25 CRANE AND HOIST OPERABILITY TRMS 3.25 All cranes and hoists used for handling fuel assemblies and control rods within the reactor pressure vessel (RPV) shall be OPERABLE. APPLICABILITY: During movement of fuel assemblies or control rods within the RPV using cranes or hoists.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. Requirements of TRMS not met. A.1 Suspend use of any inoperable crane and hoist

from operations involving

movement of fuel

assemblies or control rods

in the RPV after placing

the load in a safe location.

Immediately

Crane and Hoist OPERABILITY 3.25 Brunswick Unit 2 3.25-2 Revision No. 23 TEST REQUIREMENTS TEST FREQUENCY TR 3.25.1 Demonstrate operation of the overload cutoff of each crane or hoist to be used for movement of fuel

assemblies or control rods within the RPV:

a. When the load is 1600 lbs for the mast fuel gripper; and b. When the load is 1050 lbs for all other cranes and hoists.

Once within

7 days prior to

start of movement

of fuel assemblies

or control rods

within the RPV

using the

associated crane

or hoist, if not

performed within

the previous 30

days. TR 3.25.2 Demonstrate operation of the loaded interlock of each crane or hoist to be used for movement of fuel

assemblies or control rods within the RPV:

a. When the load is 750 lbs for the mast fuel gripper; and b. When the load is 350 lbs for all other cranes and hoists.

Once within

7 days prior to

start of movement

of fuel assemblies

or control rods

within the RPV

using the

associated crane

or hoist, if not

performed within

the previous 30

days. (continued)

Crane and Hoist OPERABILITY 3.25 Brunswick Unit 2 3.25-3 Revision No. 23 TEST REQUIREMENTS (continued)

TEST FREQUENCY TR 3.25.3 Demonstrate operation of the slack cable cutoff of the mast fuel gripper when the load is < 50 +/- 25 lbs.

Once within

7 days prior to

start of movement

of fuel assemblies

or control rods

within the RPV

using the mast fuel

gripper, if not

performed within

the previous 30

days. TR 3.25.4 Perform a load test of 1000 lbs of each crane or hoist to be used for movement of fuel assemblies or

control rods within the RPV.

Once within

7 days prior to

start of movement

of fuel assemblies

or control rods

within the RPV

using the

associated crane

or hoist, if not

performed within

the previous 30

days. (continued)

Crane and Hoist OPERABILITY 3.25 Brunswick Unit 2 3.25-4 Revision No. 23 TEST REQUIREMENTS (continued)

TEST FREQUENCY TR 3.25.5 Demonstrate operation of the uptravel stop of each crane or hoist (other than the mast fuel gripper) to be

used for movement of fuel assemblies or control rods

within the RPV when uptravel would bring the top of

active fuel to 7 ft below the normal spent fuel pool

water level.

Once within

7 days prior to

start of movement

of fuel assemblies

or control rods

within the RPV

using the

associated crane

or hoist, if not

performed within

the previous 30

days.

Crane Travel-Spent Fuel Storage Pool 3.26 Brunswick Unit 2 3.26-1 Revision No. 23 3.26 CRANE TRAVEL-SPENT FUEL STORAGE POOL TRMS 3.26 Loads > 1600 lbs shall be prohibited from travel over fuel assemblies in the spent fuel pool storage racks. APPLICABILITY: When fuel assemblies are in the spent fuel pool storage racks.

COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY ACTION COMPLETION TIME A. Requirements of TRMS not met. A.1 Place the load in a safe condition.

Immediately

TEST REQUIREMENTS TEST FREQUENCY TR 3.26.1 Verify loads, other than fuel assemblies, are 1600 lbs. Prior to movement

of loads over fuel assemblies in the

spent fuel pool

storage racks Brunswick Unit 2 4.0-1 Revision No. 23 4.0 Not used.

Programs and Manuals

5.0 Brunswick

Unit 2 5.0-1 Revision No. 45

5.0 PROGRAMS

AND MANUALS

5.5.1 Offsite

Dose Calculation Manual Technical Specification 5.5.1, "Offsite Dose Calculation Manual," is

implemented by the Brunswick Steam Electric Plant Off-Site Dose Calculation

Manual. 5.5.2 Primary Coolant Sources Outside Containment Technical Specification 5.5.2, "Primary Coolant Sources Outside

Containment," requires controls be provided to minimize leakage from those

portions of systems outside containment that could contain highly radioactive

fluids during a serious transient or accident to levels as low as practicable.

The program is implemented by the following procedures:

0PT-07.2.4A, 0PT-07.2.4B, 0PT-08.2.2C, 0PT-08.2.2B, 0PT-09.2, 0PT-10.1.1, and

0PT-14.6.

5.5.3 Deleted.

(continued)

Programs and Manuals

5.0 Brunswick

Unit 2 5.0-2 Revision No. 41

5.0 PROGRAMS

AND MANUALS (continued)

5.5.4 Radioactive

Effluent Controls Program Technical Specification 5.5.4, "Radioactive Effluent Controls Program,"

requires controls be established to conform with 10 CFR 50.36a for control of

radioactive effluents and for maintaining doses to members of the public from

radioactive effluents as low as reasonably achievable. This program is

implemented through Section 7.0 of the Brunswick Steam Electric Plant Off-

Site Dose Calculation Manual. 5.5.5 Component Cyclic or Transient Limit Program Technical Specification 5.5.5, "Component Cyclic or Transient Limit," requires

controls be provided to track the UFSAR, Table 5.3.3-2 cyclic and transient

occurrences to ensure that components are maintained within design limits.

The program is implemented by the following procedure:

0ENP-44. 5.5.6 Inservice Testing Program Technical Specification 5.5.6, "Inservice Testing Program," requires controls

be established for inservice testing of ASME Code Class 1, 2, and 3, components. This program is implemented by the following:

0ENP-17 and the applicable procedures that implement ASME OM Code

requirements.

5.5.7 Ventilation

Filter Testing Program (VFTP)

Technical Specification 5.5.7, "Ventilation Filter Testing Program (VFTP),"

requires testing of the Engineered Safety Feature filter ventilation systems for

the following Technical Specification systems:

Control Room Emergency Ventilation System and Standby Gas Treatment

System. (continued)

Programs and Manuals

5.0 Brunswick

Unit 2 5.0-3 Revision No. 45

5.0 PROGRAMS

AND MANUALS

5.5.7 Ventilation

Filter Testing Program (VFTP)

(continued)

The program is implemented by the following procedures:

2PT-15.1.1A, 2PT-15.1.1B, 2PT-15.1.2A, 2PT-15.1.2B, 0PT-17.0, and

0PT-21.1 In addition, laboratory analysis required by Technical Specification 5.5.7.c

must be completed within 31 days after removal of a representative carbon sample. 5.5.8 Explosive Gas and Storage Tank Radioactivity Monitoring Program Technical Specification 5.5.8, "Explosive Gas and Storage Tank Radioactivity

Monitoring Program," requires controls be provided for potentially explosive gas mixtures contained in the Main Condenser Offgas Treatment System and

the quantity of radioactivity contained in the unprotected outdoor storage

tanks. The program is implemented by ODCMS 7.3.6, "Liquid Holdup

Tanks," ODCMS 7.3.12, "Explosive Gas Mixtures," and procedures

0E&RC-1000 and 0E&RC-1222. 5.5.9 Diesel Fuel Oil Testing Program Technical Specification 5.5.9, "Diesel Fuel Oil Testing Program," requires

testing requirements be provided for new fuel oil and stored fuel oil and

includes sampling requirements and acceptance criteria. The program is

implemented by the following procedures:

0E&RC-1010, 0E&RC-1142, 0E&RC-1141, 0E&RC-1138, and

0E&RC-1020.

(continued)

Programs and Manuals

5.0 Brunswick

Unit 2 5.0-4 Revision No. 45

5.0 PROGRAMS

AND MANUALS (continued)

5.5.10 Technical Specification Bases Control Program Technical Specification 5.5.10, "Technical Specification Bases Control

Program," requires means be provided for processing changes to the Bases

of the Technical Specifications. The program is implemented by the following

procedure:

0AP-019. 5.5.11 Safety Function Determination Program Technical Specification 5.5.11, "Safety Function Determination Program,"

requires means be provided to ensure a loss of function is detected and

appropriate actions taken. The program is implemented by Appendix F of the

Technical Requirements Manual. 5.5.12 Primary Containment Leakage Rate Testing Program Technical Specification 5.5.12, "Primary Containment Leakage Rate Testing

Program," requires implementation of leakage rate testing of the primary

containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B as modified by approved exem ptions. The program is implemented by the following:

0PT-20.3, 0PT-20.3b, 0PT-20.3c, 0PT-20.5, 0PT-20.5.1, 0ENP-16.4, and

0ENP-16.8.

(continued)

Programs and Manuals

5.0 Brunswick

Unit 2 5.0-5 Revision No. 62

5.0 PROGRAMS

AND MANUALS (continued)

5.5.13 Control Room Envelope Habitability Program Technical Specification 5.5.13, "Control Room Envelope Habitability

Program," requires controls be established and testing performed to ensure

habitability of the control room envelope is maintained following a radiological

event, hazardous chemical release, or a smoke challenge. The program is

implemented by the following:

0ENP-54 0MST-CREV22

0OI-01.01

0PT-23.1 0PT-23.1.1

0PT-23.1.2

0PT-23.1.3

0PT-46.5 0PT-34.2.2.1

0PT-46.4 0PT-26.0 5.5.14 Configuration Risk Management Program The Configuration Risk Management Program (CRMP) provides a

proceduralized risk-informed assessment to manage the risk associated with

equipment inoperability. The program applies to Technical Specification

structures, systems, or components for which a risk-informed allowed outage

time has been granted (i.e., Technical Specification 3.8.1, Condition B). The

program shall include the following elements:

a. Provisions for the control and implementation of a Level 1 at-power internal events PRA-informed methodology. The assessment shall be

capable of evaluating the applicable plant configuration. (0AP-025) b. Provisions for performing an assessment prior to entering the Limiting Condition for Operation (LCO) Action for preplanned activities.

(0AP-025) c. Provisions for performing an assessment after entering the LCO Action for unplanned entry into the LCO Action. (0AP-025)

(continued)

Programs and Manuals

5.0 Brunswick

Unit 2 5.0-6 Revision No. 45

5.0 PROGRAMS

AND MANUALS

5.5.14 Configuration Risk Management Program (continued) d. Provision for assessing the need for additional actions after the discovery of additional equipment out of service conditions while in the

LCO Action. (0AP-025) e. Provisions for considering other applicable risk significant contributors such as Level 2 issues and external events, qualitatively or

quantitatively. (0AP-025, ADM-NGGC-0101, 0AI-068, and 0PEP-02.6) 5.5.15 Inservice Inspection Program This program provides controls for inservice inspection of ASME Code

Class 1, 2, and 3 components and their supports, and Class MC (i.e., metal

containment) and CC (i.e., concrete containment) components. This program

is implemented by the following:

0ENP-16 and the applicable procedures that implement ASME Section XI

requirements.

TRMS Applicability B 3.0 Brunswick Unit 2 B 3.0-1 Revision No. 23 B 3.0 TECHNICAL REQUIREMENTS MANUAL SPECIFICATION (TRMS) APPLICABILITY

BASES TRMSs TRMS 3.0.1 through TRMS 3.0.5 establish the general requirements applicable to all Specifications and apply at all times, unless otherwise

stated. TRMS 3.0.1 TRMS 3.0.1 establishes the Applicability statement within each individual TRMS as the requirement for when the TRMS is required to be met (i.e.,

when the unit is in the MODES or other specified conditions of the

Applicability statement of each TRMS).

TRMS 3.0.2 TRMS 3.0.2 establishes that upon discovery of a failure to meet a TRMS, the associated COMPENSATORY MEASURES shall be met. The

Completion Time of each Required Compensatory Measure for a

COMPENSATORY MEASURES Condition is applicable from the point in

time that a COMPENSATORY MEASURES Condition is entered. The

Required Compensatory Measures establish those remedial measures

that must be taken within specified Completion Times when the

requirements of a TRMS are not met. This TRMS establishes that:

a. Completion of the Required Compensatory Measures within the specified Completion Times constitutes compliance with a TRMS;

and b. Completion of the Required Compensatory Measures is not required when a TRMS is met within the specified Completion

Time, unless otherwise specified.

There are two basic types of Required Compensatory Measures. The

first type of Required Compensatory Measure specifies a time limit in

which the TRMS must be met. This time limit is the Completion Time to

restore an inoperable system or component to OPERABLE status or to

restore variables to within specified limits. If this type of Required

Compensatory Measure is not completed within the specified Completion

Time, a shutdown may be required to place the unit in a MODE or

condition in which the TRMS is not applicable. (Whether stated as a

Required Compensatory (continued)

TRMS Applicability B 3.0 Brunswick Unit 2 B 3.0-2 Revision No. 26

BASES TRMS 3.0.2 Measure or not, correction of the entered Condition is a compensatory (continued) measure that may always be considered upon entering COMPENSATORY MEASURES.) The second type of Required

Compensatory Measure specifies the remedial measures that permit

continued operation of the unit that is not further restricted by the

Completion Time. In this case, compliance with the Required

Compensatory Measures provides an acceptable level of safety for

continued operation.

Completing the Required Compensatory Measures is not required when a

TRMS is met or is no longer applicable, unless otherwise stated in the

individual TRMSs.

The nature of some Required Compensatory Measures of some

Conditions necessitates that, once the Condition is entered, the Required

Compensatory Measures must be completed even though the associated

Condition no longer exists. The individual TRMS's COMPENSATORY

MEASURES specify the Required Compensatory Measures where this is

the case. An example of this is in TRMS 3.21, "Snubbers."

The Completion Times of the Required Compensatory Measures are also

applicable when a system or com ponent is removed from service

intentionally. The reasons for intentionally relying on the

COMPENSATORY MEASURES include, but are not limited to, performance of Tests, preventive maintenance, corrective maintenance, or investigation of operational problems. Entering COMPENSATORY

MEASURES for these reasons must be done in a manner that does not

compromise safety. Intentional entry into COMPENSATORY

MEASURES should not be made for operational convenience.

Alternatives that would not result in redundant equipment being

inoperable should be used instead. Doing so limits the time both

subsystems/divisions of a safety function are inoperable. Individual

TRMSs may specify a time limit for performing a TR when equipment is

removed from service or bypassed for testing. In this case, the

Completion Times of the Required Compensatory Measures are

applicable when this time limit expires, if the equipment remains removed

from service or bypassed.

When a change in MODE or other specified condition is required to

comply with Required Compensatory Measures, the unit may enter a

MODE or other specified condition in which another TRMS becomes

applicable. In this case, the (continued)

TRMS Applicability B 3.0 Brunswick Unit 2 B 3.0-3 Revision No. 23 BASES TRMS 3.0.2 Completion Times of the associated Required Compensatory (continued) Measures would apply from the point in time that the new TRMS becomes applicable and the COMPENSATORY MEASURES

Condition(s) are entered.

TRMS 3.0.3 Not used.

TRMS 3.0.4 TRMS 3.0.4 establishes limitations on changes in MODES or other specified conditions in the Applicability when a TRMS is not met. It

precludes placing the unit in a MODE or other specified condition stated

in that Applicability (e.g., Applicability desired to be entered) when the

following exist:

a. Unit conditions are such that the requirements of the TRMS would not be met in the Applicability desired to be entered; and b. Continued noncompliance with the TRMS requirements, if the Applicability were entered, would result in the unit being required

to exit the Applicability desired to be entered to comply with the

Required Compensatory Measures.

Compliance with Required Compensatory Measures that permit

continued operation of the unit for an unlimited period of time in a MODE

or other specified condition provides an acceptable level of safety for

continued operation. This is without regard to the status of the unit before

or after the MODE change. Therefore, in such cases, entry into a MODE

or other specified condition in the Applicability may be made in

accordance with the provisions of the Required Compensatory Measures.

The provisions of this Specification should not be interpreted as

endorsing the failure to exercise the good practice of restoring systems or

components to OPERABLE status before unit startup.

The provisions of TRMS 3.0.4 shall not prevent changes in MODES or

other specified conditions in the Applicability that are required to comply

with COMPENSATORY MEASURES. In addition, the provisions of

TRMS 3.0.4 shall not prevent changes in MODES or other specified

conditions in the Applicability that result from any unit shutdown.

(continued)

TRMS Applicability B 3.0 Brunswick Unit 2 B 3.0-4 Revision No. 23 BASES TRMS 3.0.4 Exceptions to TRMS 3.0.4 are stated in the individual Tests.

(continued) Exceptions may apply to all the COMPENSATORY MEASURES or to a specific Required Compensatory Measure of a TRMS.

Tests do not have to be performed on the associated inoperable

equipment (or on variables outside the specified limits), as permitted by

TR 3.0.1. Therefore, changing MODES or other specified conditions

while in a COMPENSATORY MEASURES Condition, either in

compliance with TRMS 3.0.4 or where an exception to TRMS 3.0.4 is

stated, is not a violation of TR 3.0.1 or TR 3.0.4 for those Tests that do

not have to be performed due to the associated inoperable equipment.

However, TRs must be met to ensure OPERABILITY prior to declaring

the associated equipment OPERABLE (or variable within limits) and

restoring compliance with the affected TRMS.

TRMS 3.0.5 TRMS 3.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with COMPENSATORY MEASURES. The

sole purpose of this TRMS is to provide an exception to TRMS 3.0.2 (e.g.,

to not comply with the applicable Required Compensatory Measure(s)) to

allow the performance of TRs to demonstrate:

a. The OPERABILITY of the equipment being returned to service; or

b. The OPERABILITY of other equipment.

The administrative controls ensure the time the equipment is returned to

service in conflict with the requirements of the COMPENSATORY

MEASURES is limited to the time absolutely necessary to perform the

allowed TRs. This TRMS does not provide time to perform any other

preventive or corrective maintenance.

An example of demonstrating the OPERABILITY of the equipment being

returned to service is taking an inoperable channel or trip system out of

the tripped condition after it has been tripped to comply with Required

Compensatory Measures since it must be untripped to perform the TRs.

An example of demonstrating the OPERABILITY of other equipment is

taking an inoperable channel or trip system out of the tripped condition to

prevent the trip function from (continued)

TRMS Applicability B 3.0 Brunswick Unit 2 B 3.0-5 Revision No. 23 BASES TRMS 3.0.5 occurring during the performance of a TR on another channel in the (continued) other trip system. A simila r example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of

the tripped condition to permit the logic to function and indicate the

appropriate response during the performance of a TR on another channel

in the same trip system.

TR Applicability B 3.0 Brunswick Unit 2 B 3.0-6 Revision No. 23 B 3.0 TEST REQUIREMENT (TR) APPLICABILITY

BASES TRs TR 3.0.1 through TR 3.0.4 establish the general requirements applicable to all TRMSs and apply at all times, unless otherwise stated.

TR 3.0.1 TR 3.0.1 establishes the requirement that TRs must be met during the MODES or other specified conditions in the Applicability for which the

requirements of the TRMS apply, unless otherwise specified in the

individual TRs. This TRMS is to ensure that Tests are performed to verify

the OPERABILITY of systems and components, and that variables are

within specified limits. Failure to meet a Test within the specified

Frequency, in accordance with TR 3.0.2, constitutes a failure to meet a

TRMS.

Systems and components are assumed to be OPERABLE when the

associated TRs have been met. Nothing in this TRMS, however, is to be

construed as implying that systems or components are OPERABLE

when:

a. The systems or components are known to be inoperable, although still meeting the TRs; or b. The requirements of the Test(s) are known to be not met between required Test performances.

Tests do not have to be performed when the unit is in a MODE or other

specified condition for which the requirements of the associated TRMS

are not applicable, unless otherwise specified.

Tests, including Tests invoked by Required Compensatory Measures, do

not have to be performed on inoperable equipment because the

COMPENSATORY MEASURES define the remedial measures that apply.

Tests have to be met and performed in accordance with TR 3.0.2, prior to

returning equipment to OPERABLE status.

(continued)

TR Applicability B 3.0 Brunswick Unit 2 B 3.0-7 Revision No. 23 BASES TR 3.0.1 Upon completion of maintenance, appropriate post maintenance testing is (continued) required to declare equipment OPERABLE. This includes ensuring applicable Tests are not failed and their most recent performance is in

accordance with TR 3.0.2. Post maintenance testing may not be possible

in the current MODE or other specified conditions in the Applicability due

to the necessary unit parameters not having been established. In these

situations, the equipment may be considered OPERABLE provided

testing has been satisfactorily completed to the extent possible and the

equipment is not otherwise believed to be incapable of performing its

function. This will allow operation to proceed to a MODE or other

specified condition where other necessary post maintenance tests can be

completed.

TR 3.0.2 TR 3.0.2 establishes the requirements for meeting the specified Frequency for Tests and any Required Compensatory Measure with a

Completion Time that requires the periodic performance of the Required

Compensatory Measure on a "once per..." interval.

TR 3.0.2 permits a 25% extension of the interval specified in the

Frequency. This extension facilitates Test scheduling and considers plant

operating conditions that may not be suitable for conducting the Test (e.g., transient conditions or other ongoing Test or maintenance

activities).

The 25% extension does not significantly degrade the reliability that

results from performing the Test at its specified Frequency. This is based

on the recognition that the most probable result of any particular Test

being performed is the verification of conformance with the TRs.

As stated in TR 3.0.2, the 25% extension also does not apply to the initial

portion of a periodic Completion Time that requires performance on a "once per..." basis. The 25% extension applies to each performance after

the initial performance. The initial performance of the Required

Compensatory Measure, whether it is a particular Test or some other

remedial action, is considered a single compensatory measure with a

single Completion Time. One reason for not allowing the 25% extension

to this Completion (continued)

TR Applicability B 3.0 Brunswick Unit 2 B 3.0-8 Revision No. 23 BASES TR 3.0.2 Time is that such a compensatory measure may verify that no loss of (continued) function has occurred by checking the status of redundant or diverse components or accomplishes the function of the inoperable equipment in

an alternative manner.

The provisions of TR 3.0.2 are not intended to be used repeatedly merely

as an operational convenience to extend Test intervals (other than those

consistent with refueling intervals) or periodic Completion Time intervals

beyond those specified.

TR 3.0.3 TR 3.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a Test

has not been completed within the specified Frequency. A delay period

of up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or up to the limit of the specified Frequency, whichever

is less, applies from the point in time that it is discovered that the Test has

not been performed in accordance with TR 3.0.2, and not at the time that

the specified Frequency was not met.

This delay period provides adequate time to complete Tests that have

been missed. This delay period permits the completion of a Test before

complying with Required Compensatory Measures or other remedial

measures that might preclude completion of the Test.

The basis for this delay period includes consideration of unit conditions, adequate planning, availability of personnel, the time required to perform

the Test, the safety significance of the delay in completing the required

Test, and the recognition that the most probable result of any particular

Test being performed is the verification of conformance with the

requirements.

When a Test with a Frequency based not on time intervals, but upon

specified unit conditions or operational situations, is discovered not to

have been performed when specified, TR 3.0.3 allows the full delay

period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to perform the Test.

TR 3.0.3 also provides a time limit for completion of Tests that become

applicable as a consequence of MODE changes imposed by Required

Compensatory Measures.

(continued)

TR Applicability B 3.0 Brunswick Unit 2 B 3.0-9 Revision No. 23 BASES TR 3.0.3 Failure to comply with specified Frequencies for TRs is expected to be an (continued) infrequent occurrence. Use of the delay period established by TR 3.0.3 is a flexibility which is not intended to be used as an operational

convenience to extend Test intervals.

If a Test is not completed within the allowed delay period, then the

equipment is considered inoperable or the variable is considered outside

the specified limits and the Completion Times of the Required

Compensatory Measures for the applicable TRMS Conditions begin

immediately upon expiration of the delay period. If a Test is failed within

the delay period, then the equipment is inoperable, or the variable is

outside the specified limits and the Completion Times of the Required

Compensatory Measures for the applicable TRMS Conditions begin

immediately upon the failure of the Test.

Completion of the Test within the delay period allowed by this TRMS, or

within the Completion Time of the COMPENSATORY MEASURES, restores compliance with TR 3.0.1.

TR 3.0.4 TR 3.0.4 establishes the requirement that all applicable TRs must be met before entry into a MODE or other specified condition in the Applicability.

This TRMS ensures that system and component OPERABILITY

requirements and variable limits are met before entry into MODES or

other specified conditions in the Applicability for which these systems and

components ensure safe operation of the unit.

However, in certain circumstances failing to meet a TR will not result in

TR 3.0.4 restricting a MODE change or other specified condition change.

When a system, subsystem, division, component, device, or variable is

inoperable or outside its specified limits, the associated TR(s) are not

required to be performed, per TR 3.0.1, which states that Tests do not

have to be performed on inoperable equipment. When equipment is

inoperable, TR 3.0.4 does not apply to the associated TR(s) since the

requirement for the TR(s) to be performed is removed. Therefore, failing

to perform the Test(s) within the specified Frequency does not result in a (continued)

TR Applicability B 3.0 Brunswick Unit 2 B 3.0-10 Revision No. 23 BASES TR 3.0.4 TR 3.0.4 restriction to changing MODES or other specified conditions of (continued) the Applicability. However, since the TRMS is not met in this instance, TRMS 3.0.4 will govern any restrictions that may (or may not) apply to

MODE or other specified condition changes.

The provisions of TR 3.0.4 shall not prevent changes in MODES or other

specified conditions in the Applicability that are required to comply with

COMPENSATORY MEASURES. In addition, the provisions of TR 3.0.4

shall not prevent changes in MODES or other specified conditions in the

Applicability that result from any unit shutdown.

The precise requirements for performance of TRs are specified such that

exceptions to TR 3.0.4 are not necessary. The specific time frames and

conditions necessary for meeting the TRs are specified in the Frequency, in the Test, or both. This allows performance of Tests when the

prerequisite condition(s) specified in a Test procedure require entry into

the MODE or other specified condition in the Applicability of the

associated TRMS prior to the performance or completion of a Test. A

Test that could not be performed until after entering the TRMS

Applicability would have its Frequency specified such that it is not "due" until the specific conditions needed are met. Alternately, the Test may be

stated in the form of a Note as not required (to be met or performed) until

a particular event, condition, or time has been reached. Further

discussion of the specific formats of TRs' annotation is found in TRMS

Section 1.4, Frequency.

Control Rod Drive Housing Support B 3.1 Brunswick Unit 2 B 3.1-1 Revision No. 23 B 3.1 CONTROL ROD DRIVE HOUSING SUPPORT

BASES The control rod housing support restricts the outward movement of a control rod to less than

3 inches in the event of a housing failure. The amount of rod reactivity which could be added by

this small amount of rod withdrawal is less than a normal withdrawal increment and will not contribute to any damage to the primary cool ant system. The support is not required when there is no pressure to act as a driving force to rapidly eject a drive housing.

Brunswick Unit 2 B 3.2-1 Revision No. 23 B 3.2 Not used.

Control Rod Block Instrumentation B 3.3 Brunswick Unit 2 B 3.3-1 Revision No. 23 B 3.3 CONTROL ROD BLOCK INSTRUMENTATION

BASES The Control Rod Block Functions are provided with the trip logic arranged so that a trip in any

one of the inputs will result in a rod block.

Specified test intervals and allowed out-of-service times were established based on the

reliability analyses documented in GE reports NEDC-30851P-A, Supplement 1, "Technical

Specification Improvement Analysis for BWR Control Rod Block Instrumentation,"

October 1988, NEDC-32410P-A, "Nuclear Measurement Analysis and Control Power Range

Neutron Monitor (NUMAC-PRNM) Retrofit Plus Option III Stability Trip Function," October 1995, and NEDC-32410P-A, Supplement 1, "Nuclear Measurement Analysis and Control Power

Range Neutron Monitor (NUMAC PRNM) Plus Option III Stability Trip Function,"

November 1997.

CHANNEL CALIBRATIONS of the Average Power Range Monitors Functions 1.a and 1.d are

electronic.

Accident Monitoring Instrumentation B 3.4 Brunswick Unit 2 B 3.4-1 Revision No. 60 B 3.4 ACCIDENT MONITORING INSTRUMENTATION

BASES The OPERABILITY of the post-accident monitoring instrumentation ensures that sufficient

information is available on selected plant param eters to monitor and assess important variables following an accident. This capability is consistent with the recommendations of Regulatory

Guide 1.97, "Instrumentation for Light Water-Cooled Nuclear Power Plants to Assess Plant

Conditions During and Following an Accident," December 1975, and NUREG-0578, "TMI-2

Lessons Learned Task Force Status Report and Short-Term Recommendations."

To support removal to the Drywell and Suppression Chamber H 2 and O 2 Analyzer from the Technical Specifications, the H 2 portion of the analyzer will be maintained as Regulatory Guide 1.97, Category 3, instrumentation. The O 2 portion of the analyzer will be maintained as Regulatory Guide 1.97, Category 2, instrumentation. However, consistent with the rulemaking

to revise 10 CFR 50.44 (i.e., the final rule published in 68 FR 54123) neither the H 2 portion or the O 2 portion of the analyzer need to be qualified in accordance with 10 CFR 50.49. Rather, as committed to in Reference 1 and approved in Reference 2, the Drywell and Suppression

Chamber H 2 and O 2 Analyzer will be capable of diagnosing beyond design-basis accidents.

The H 2 and O 2 portions of each overall Drywell and Suppression Chamber H 2 and O 2 Analyzer are primarily separate from one another such that there are many failure modes that would only result in either the H 2 or O 2 portion of the system being inoperable and not affect the operability of the other portion of the overall analyzer. Each portion has a dedicated analyzer such that

each overall Drywell and Suppression Chamber H 2 and O 2 Analyzer has internal to it an H 2 analyzer and an O 2 analyzer. TRM Table 3.4-2 lists the Analyzers as applicable instruments; each of these analyzers provides an output to both a front panel display on the analyzer and to

a recorder. Either of these indications may be used to satisfy the monitoring criteria should the

other experience a failure, assuming accuracy is maintained.

One channel of Turbine Building or Stack Ventilation Monitoring consists of all three ranges (low, mid, and high) of the monitoring system.

REFERENCES

1. Letter from Cornelius J. Gannon to the U. S. Nuclear Regulatory Commission (Serial:

BSEP 04-0098), "Request for License Amendments - Deletion of Hydrogen and Oxygen

Analyzer Requirements Consolidated Li ne Item Improvement Process (TSTF-447, Revision 1)," dated July 26, 2004. 2. Letter from U.S. Nuclear Regulator Commission to Mr. C. J. Gannon, "Issuance of Amendments RE: Elimination of Require ments for Hydrogen and Oxygen Monitors Using The Consolidated Line Item Improvement Process (TAC Nos. MC3866 and

MC3867)," dated February 2, 2005.

Chloride Intrusion Monitors B 3.5 Brunswick Unit 2 B 3.5-1 Revision No. 23 B 3.5 CHLORIDE INTRUSION MONITORS

BASES The chloride intrusion monitors provide adequate warning of any leakage in the condenser or

hotwell so that actions can be taken to mitigate the consequences of such intrusion in the

reactor coolant system. With only a minimum number of instruments available, increased

sampling frequency provides adequate information for the same purpose. Chloride intrusion

can be detected if any of the Functions in Table 3.5-1 have their required channels OPERABLE.

Bus Power Monitors B 3.6 Brunswick Unit 2 B 3.6-1 Revision No. 31 B 3.6 BUS POWER MONITORS

BASES The Emergency Core Cooling System (ECCS) and Reactor Core Isolation Cooling (RCIC)

System Bus Power Monitors are provided to monito r the availability of power to logic system.

The bus power monitors are required to be O PERABLE when the instrumentation they support is required to be OPERABLE (e.g., bus power monitors associated with High Pressure Coolant

Injection (HPCI) System and RCIC System inst rumentation are required to be OPERABLE in MODE 1 and MODES 2 and 3 with reactor steam dome pressure > 150 psig to support the

HPCI and RCIC functions and are also required to be OPERABLE in MODES 1, 2, and 3 to

support the primary containment isolation functions associated with HPCI and RCIC

instrumentation). The RHR, Core Spray System, Low Pressure Coolant Injection (Residual

Heat Removal System), HPCI and RCIC System Bus Power Monitors each consist of one

instrument channel per bus. This instrumentation provides a monitoring/alarm function only.

The ECCS and RCIC System Bus Power Monitors will be tested at regularly scheduled

intervals.

The TRMS is modified by a Note to indicate that the annunciator function may be removed from

operation for performance of troubleshooting for up to 30 minutes provided no work is being

performed on the associated power supplies. Upon completion of the troubleshooting, or

expiration of the 30 minute allowance, the annunciator must be returned to operation or the

applicable Condition entered and Required Compensatory Measures taken. Appropriate

compensatory actions should be determined and implemented during the loss of annunciator

function. Since the loss of detection capability is of short duration, no work is allowed on the

associated power supplies, and appropriate compensatory actions are determined and

implemented, there is a minimal increase in the probability of an undetected loss of ECCS

power during the 30 minute troubleshooting allowance.

ADS Inhibit Switch B 3.7 Brunswick Unit 2 B 3.7-1 Revision No. 23 B 3.7 AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) INHIBIT SWITCH

BASES ADS Inhibit Switches are provided to permit the operator to prevent automatic actuation of the

ADS. Both switches must be actuated to prevent automatic blowdown. Automatic

depressurization may not be appropriate if reactor vessel level is recovering or during ATWS

events. During ATWS events, depressurization would lead to power increases from cold water

injection, void collapse, and boron dilution. In MODE 1 and in MODES 2 and 3 with reactor

steam dome pressure > 150 psig, the ADS Inhibit Switches must be in the automatic position to

ensure that ADS automatic actuation capability is maintained.

Suppression Chamber Water Temperature Instrumentation B 3.8 Brunswick Unit 2 B 3.8-1 Revision No. 31 B 3.8 SUPPRESSION CHAMBER WATER TEMPERATURE INSTRUMENTATION

BASES The suppression chamber water temperature moni toring system performs a dual function. It provides for accident monitoring as recommended by Regulatory Guide 1.97. This system is also designed to meet the acceptance criteria of NUREG-0661, Appendix A in monitoring

average suppression chamber water temperature during normal operating conditions.

The TRMS is modified by a Note to indicate that the annunciator function may be removed from

operation for performance of troubleshooting for up to 30 minutes provided the associated

function maintains monitoring capability. Upon completion of the troubleshooting, or expiration

of the 30 minute allowance, the annunciator must be returned to operation or the applicable

Condition entered and Required Compensatory Measures taken. Appropriate compensatory

actions should be determined and implemented during the loss of annunciator function. This

Note is based on the availability of the associated monitor and appropriate compensatory

actions to identify changes in suppression pool temperature. The monitor availability and

compensatory actions ensure that the 30 minute troubleshooting allowance does not

significantly reduce the probability of identifying changing conditions to allow appropriate

response.

Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-1 Revision No. 47 B 3.9 SEISMIC MONITORING INSTRUMENTATION

BASES BACKGROUND Seismic Monitoring Instrumentati on is required to promptly determine the response to nuclear power plant features important to safety in the event

of an earthquake. This capability is required to allow for a comparison of

the measured response to that used in the design basis of the plant.

Comparison of this data is needed to determine whether the plant can

continue to be operated safely as required by 10 CFR 100, Appendix A (Ref. 2).

Reference 2 requires that two earthquake levels be considered in the

design of safety related structur es, systems and components (SSCs).

Consequently, the Seismic Monitoring Instrumentation is designed to

monitor for vibratory ground motions exceeding either of these levels.

One of these levels, the Operating Basis Earthquake (OBE), is that

earthquake which could reasonably be expected to occur at the site

during the operating life of the plant. SSCs necessary for continued plant

operation without undue risk to the health and safety of the public are

designed to remain functional following an OBE. The other earthquake

level, the Safe Shutdown Earthquake (SSE), is that earthquake which is

based upon the maximum (i.e., most severe) earthquake potential for the

area in which the plant is sited. SSCs necessary to assure the integrity of

the reactor pressure boundary, the capability to shutdown the reactor (and maintain it in a shutdown condition), and the capability to prevent or

mitigate the consequences of accidents which could result in potential

offsite exposures are designed to remain functional following an SSE.

The Seismic Monitoring Instrumentation consists of passive peak shock

recorders, triaxial accelerometers, and a central recording panel. The

central recorder panel is located in the Main Control Room and has a

central recorder for seismic data acquisition and storage, a personal

computer, monitor, a printer for display of recorded data, an annunciator

instrument that provides local indicator lights and control room indication, and a 25 minute uninterruptible power supply. Lights on the panel identify

system triggering and indicate if the OBE has been exceeded based on

an analysis of the data collected in the basement of the Reactor Building (elevation -17 feet).

The earthquake data is collected in three orthogonal directions which

coincide with the major axes of the analytical model used in the seismic

analysis of the plant structures. The central recorder is connected to the

triaxial accelerometers.

(continued)

Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-2 Revision No. 47 BASES BACKGROUND When a very low "g" level threshold (0.01 g) has been exceeded at the (continued) reactor building accelerometer (elevation -17 foot), the system alerts the operator by actuating an event indication annunciator in the main control

room and initiates the recording functions of all the accelerometers until

termination of the event.

There are two triaxial accelerometers which input to the central recorder, each of which measures the absolute acceleration as a function of time in

three orthogonal directions. These accelerometers are located in the

reactor building (elevation -17 feet) and near the top of the containment

structure (elevation +89 feet).

During a ground motion event, where the acceleration exceeds the

seismic threshold, seismic data is stored in the central recorder which can

be later viewed and printed by means of the personal computer, monitor, and printer located at the panel. The recorded seismic data is then used

to facilitate the analysis of structural loads during the seismic event.

Passive monitoring is provided by three triaxial peak shock recorders

which record the absolute peak acceleration in three orthogonal directions

coinciding with the major axes of the analytical model of the structure.

These peak shock recorders are located in the equipment drain tank area

of reactor building basement (elevation -17 feet), the reactor building

RHR heat exchanger support (elevation +20 feet), and the reactor

building refueling area (elevation +117 feet).

APPLICABLE The function of the Seismic Monitoring Instrumentation is to monitor DESIGN BASES seismic activity above a low "g" level, and to record seismic data for comparison to design bases spectra. The Brunswick Plant was originally

constructed with seismic monitoring instrumentation which corresponded

with the recommendations of NRC Safety Guide 12. Although the

Brunswick Plant's licensing basis remains Safety Guide 12, the current

instrumentation is designed to meet the requirements of 10 CFR 100, Appendix A (Ref. 2) and is consistent with specific portions of the

recommendations of Regulatory Guide 1.12, "Instrumentation for

Earthquakes" (Ref. 3).

For Brunswick Plant, the site ground response spectra are based on

earthquakes with peak horizontal ground accelerations of 0.08 g and

0.16 g, for an OBE and an SSE respectively. The vertical ground

acceleration is assumed to be two-thirds of the respective horizontal

acceleration. SSCs designated Seismic Category I are designed to

remain functional following an SSE.

(continued)

Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-3 Revision No. 47 BASES APPLICABLE When an earthquake occurs, it may not be known immediately how DESIGN BASES severe the effects of the earthquake are on plant equipment. The triaxial (continued) accelerometers provide time-history data on the seismic input to containment. The passive triaxial peak shock recorders record peak

event acceleration information that can be used to supplement the data

gathered by the triaxial accelerometers. Response spectra are generated

from the time-history data at the control station in the main control room

for comparison to design basis data.

The Seismic Monitoring Instrumentation only provides information

regarding seismic activity during a seismic event and is not considered in

any design basis accident or transient nor does it provide any function to

mitigate an accident or its consequences.

TRMS Seismic Monitoring Instrumentation is required to promptly determine the magnitude of a seismic event and evaluate the response of those

features important to safety. The Seismic Monitoring Instrumentation

listed in Table 3.9-1, including the associated main control room alarm, must be OPERABLE to ensure that the capability of detecting and

comparing the observed spectra response of a seismic event to that used

in the design basis for the plant is maintained.

APPLICABILITY The potential for a seismic event exists at all times. For example, an

earthquake could occur while moving irradiated fuel in the secondary

containment with the core fully offloaded. Therefore, this TRMS is

applicable even when fuel is not loaded in the core.

COMPENSATORY A Note has been provided to modify the COMPENSATORY MEASURES MEASURES related to seismic monitoring instruments. Section 1.3, Completion Times, specifies that once a Condition has been entered, subsequent

divisions, subsystems, components, or variables expressed in the

Condition discovered to be inoperable or not within limits will not result in

separate entry into the Condition. Section 1.3 also specifies that

Required Compensatory Measures of the Condition continue to apply for

each additional failure, with Completion Times based on initial entry into

the Condition. However, the Required Compensatory Measures for

inoperable seismic monitoring instrumentation provide appropriate

compensatory measures for separate inoperable instruments. As such, a

Note has been provided that allows separate Condition entry for each

inoperable seismic monitoring instrument.

(continued)

Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-4 Revision No. 47 BASES COMPENSATORY A.1 MEASURES (continued) With one or more seismic monitoring instruments inoperable, the ability to monitor vibratory ground motion and determine its effects on safety

related SSCs is degraded. Because of the diversity of sensor locations

available to provide monitoring signals, an allowable out of service time of

31 days is acceptable to permit restoration of any inoperable instrument

to OPERABLE status.

B.1 If the seismic monitoring instrument is not restored to OPERABLE status, plant operation may continue provided a Special Report outlining the

cause of the inoperability and the plans for restoring the instrument to

OPERABLE status is prepared and submitted to the NRC within 14 days.

The 14 day Completion Time provides an appropriate period of time to

develop the recovery plan and is consistent with the original licensing

basis reporting requirements for the seismic monitoring instrumentation.

C.1, C.2, and C.3 If a seismic event having a vibratory ground motion of 0.08 g or greater

occurs at the site, actuated instruments must be restored to a ready

status to permit monitoring of any subsequent ground motion.

Additionally, the data collected from the instruments must be reviewed

against the dynamic stress assumptions in the plant design basis.

Some seismic instruments (i.e., the passive triaxial peak shock

recorders), once actuated, are not capable of recording a subsequent

event, rendering them inoperable until they have been reset or replaced (i.e., replacement of the recording plates). Since seismic events are typically followed by several aftershocks, it is necessary to return

actuated instruments to an OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (Required

Compensatory Measure C.1) to assure that the severity of subsequent aftershocks can be evaluated. Seismic monitoring instrument calibration

may also be affected by the sudden ground motion of an earthquake. An

instrument's calibration may have shifted outside of allowable limits, depending on the severity of the seismic event. Therefore, Required

Compensatory Measure C.2 requires that a CHANNEL CALIBRATION

per TR 3.9.3 be performed on each actuated instrument within 10 days

following the initiating event (e.g., the initiating seismic event and

associated aftershocks) to verify that the affected instruments are still

properly calibrated.

(continued)

Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-5 Revision No. 47 BASES COMPENSATORY C.1, C.2, and C.3 (continued)

MEASURES (continued) In order to validate the analytical model and to determine the magnitude of the stresses that were applied to safety related SSCs during the event, the data from the seismic monitoring instruments must be retrieved and

analyzed. The information derived from this analysis must be

incorporated into a Special Report per Required Compensatory

Measure C.3. The Special Report shall describe the magnitude and

frequency spectrum of the event and describe the effect of the event on

safety related SSCs at the station. The data analysis and Special Report

must be completed within 14 days of the initiating event.

Condition C is modified by a Note requiring Required Compensatory

Measures C.2 and C.3 to be completed whenever the Condition is

entered. The Note emphasizes the need to perform the evaluation of the

effects of the seismic event. Restoration of instrument OPERABILITY

alone per Required Compensatory Measure C.1 is insufficient because

higher than analyzed stresses may have occurred and may have affected

safety-related SSCs. Additionally, the Note ensures that the calibration of

actuated seismic instrumentation has not been affected by the event.

TEST As noted at the beginning of the TRs, the TRs for each Seismic REQUIREMENTS Monitoring Instrumentation Func tion are located in the TRs column of Table 3.9-1.

TR 3.9.1 Performance of the CHANNEL CHECK once every 31 days ensures that

a gross failure of instrumentation has not occurred. A CHANNEL CHECK

is normally a comparison of the parameter indicated on one instrument to

a similar parameter on other instruments. It is based on the assumption

that instruments monitoring the same parameter should read

approximately the same value. Significant deviations between the

instruments could be an indication of excessive instrument drift or

something even more serious. A CHANNEL CHECK will detect gross

instrument failure; thus, it is key to verifying the instrumentation continues

to operate properly between each CHANNEL CALIBRATION. This

CHANNEL CHECK is fulfilled by the absence of a system health warning

indication.

Agreement criteria are determined by the plant staff, based on a

combination of the instrument uncertainties, including indication and

readability. If an instrument is outside the criteria, it may be an indication

that the instrument has drifted outside its limit.

(continued)

Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-6 Revision No. 47 BASES TEST TR 3.9.1 (continued)

REQUIREMENTS (continued) The Frequency is based on operating experience that demonstrates instrument failure is rare and is consistent with the recommendations of

Reference 3. The CHANNEL CHECK supplements less formal, but more

frequent, checks of instruments during normal operational use of the

displays associated with the instruments required by the TRMS.

TR 3.9.2 A CHANNEL FUNCTIONAL TEST is performed on each required

instrument to ensure that the instrument channel will perform the intended

function. A successful test of the required contact(s) of an instrument

channel relay may be performed by the verification of the change of state

of a single contact of the relay. This clarifies what is an acceptable

CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because

all of the other required contacts of the relay are verified by other

Technical Specifications and non-Technical Specifications tests at least

once per refueling interval with applicable extensions. Any setpoint

adjustment shall be consistent with the assumptions of the current plant

specific setpoint methodology.

The Frequency of 184 days is consistent with the recommendations of

Reference 3.

TR 3.9.3 CHANNEL CALIBRATION is a complete check of the instrument loop and

the sensor. This test verifies the instrument responds to the measured

parameter within the necessary range and accuracy. CHANNEL

CALIBRATION leaves the instrument adjusted to account for instrument

drifts between successive calibrations, consistent with the plant specific

setpoint methodology.

The Frequency of 24 months is consistent with the recommendations of

Reference 3.

REFERENCES 1. UFSAR Section 3.7.4. 2. 10 CFR 100, Appendix A.

3. Regulatory Guide 1.12, "Instrumentation for Earthquakes."

Intake Canal High Water Level Instrumentation B 3.10 Brunswick Unit 2 B 3.10-1 Revision No. 31

B 3.10 INTAKE CANAL HIGH WATER LEVEL INSTRUMENTATION

BASES To ensure that operators are alerted to a rising water level in the intake canal, a level indicator

is provided with a sensor installed in the Class I service water intake structure and a recording

indicator in the control room. The level indicator will provide an alarm in the control room when

water in the intake canal reaches elevation 14.5 ft.

The TRMS is modified by a Note to indicate that the annunciator function may be removed from

operation for performance of troubleshooting for up to 30 minutes provided a method to monitor

water level is maintained. Upon completion of the troubleshooting, or expiration of the 30

minute allowance, the annunciator must be returned to operation or the applicable Condition

entered and Required Compensatory Measures taken. Appropriate compensatory actions

should be determined and implemented during the loss of annunciator function. This Note is

based upon appropriate compensatory actions being taken to identify changes in the intake

canal level during the 30 minute troubleshooting allowance.

Primary Containment Isolation Instrumentation B 3.11 Brunswick Unit 2 B 3.11-1 Revision No. 23 B 3.11 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION

BASES This specification ensures the effectiveness of the instrumentation by prescribing the trip settings for isolation of the reactor systems. When necessary, one channel may be inoperable

for brief intervals to conduct required testing. The setpoints are established at a level away

from the normal operating range to prevent inadver tent actuation of the systems involved.

Specified test intervals and allowed out-of-service times were established based on the

reliability analysis documented in GE report NEDC-31677P-A, "Technical Specification

Improvement Analysis for BWR Isolation Actuati on Instrumentation," July 1990, as modified by 0G90-579-32A, Letter to Millard L. Wohl (NRC) from W. P Sullivan and J. F. Klapproth (GE),

"Implementation Enhancements to Technical Specification Changes Given in Isolation Actuation

Instrumentation Analysis," June 25, 1990 and supplemented by GE letter report

GENE-A31-00001-02, "assessment of Brunswick Nuclear Plant Isolation Actuation

Instrumentation Against NEDC-31677P-A Bounding Analyses," August 1994.

The Main Steam Line Tunnel Temperature-High (except for Main Steam Isolation Valve Pit

instruments) Function and the Turbine Building Area Temperature-High Function are each

capable of isolating valves in Group 1 except for valves B32-F019 and B32-F020.

CREV System Instrumentation B 3.12 Brunswick Unit 2 B 3.12-1 Revision No. 57 B 3.12 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM INSTRUMENTATION BASES BACKGROUND One of the principal design objectives of the Control Building Heating, Ventilation and Air

Conditioning (CBHVAC) System is to permit continuous occupancy of the control room

emergency zone under normal operating conditions and under the postulated design basis

events throughout the life of the plant. The Control Building HVAC System must function to

provide protection to the operators for three type events: a radiation event, up to and including

a Design Basis Accident (e.g., Main Steam Line Break [MSLB] Accident, Refueling Accident, Control Rod Drop Accident, or Loss of Coolant Accident [LOCA]), a toxic gas event (complete

rupture of the 55 ton chlorine tank car located near the service water building, or a slow leak

lasting for an extended period of time), and an ex ternal smoke event. These events form the basis for the design of the Control Room Emer gency Ventilation (CREV) System function of the CBHVAC System. The radiation protection f unction of the CREV System is addressed in

Technical Specifications.

During an external smoke event, the CBHVAC Syst em is required to automatically isolate and enter the radiation/smoke protection mode on a smoke detection signal from one of the two

Control Building Intake air duct smoke detectors. Upon receipt of a smoke detection signal, the

CBHVAC System is automatically realigned to the emergency mode of operation. The normal

fresh air inlet closes, and, at approximately the same time, the emergency air filtration units

begin operation, recirculating control room air and providing filtered makeup air to minimize

smoke build-up and provide positive pre ssure in the control room envelope.

In the event of a chlorine release, the CBHVAC System enters a full recirculation mode (chlorine protection mode), with no outdoor air intake. The emergency filtration trains do not start, since

they do not effectively remove chlorine and may be damaged by the presence of chlorine.

Protection for chlorine gas events "overrides" any concurrent, ongoing, and any subsequent

radiation or smoke initiation signals. The override design offers protection to operations

personnel in the control room by providing protection against potentially fatal chlorine gas

releases. This protection is required at any time the chlorine tank car is within the exclusion

area.

The CREV System is designed to meet the criteria of General Design Criterion (GDC) 19 (Reference 1). In addition, the system is designed using the guidance of Regulatory

Guide 1.95, Revision 1 (Reference 2). Commitments have also been made to design chlorine

detection and isolation logic to single failure criteria, with approved exceptions (Reference 3, Section 3.6).

(continued)

CREV System Instrumentation B 3.12 Brunswick Unit 2 B 3.12-2 Revision No. 23 BASES (continued)

TRMS OPERABILITY of the CREV System instrumentat ion ensures that the control room operators will be protected from hazards external to the control room, consistent with the assumptions in

the various analyses, through the prompt detection and initiation of the necessary protective

actions of the system.

APPLICABILITY The instrumentation associated with the chlorine protection mode of the CREV System is

required to be OPERABLE to automatically detect and initiate the internal recirculation mode of

operation any time the chlorine tank car is within the exclusion area.

The instrumentation associated with the external smoke protection function of the CREV

System is required to be OPERABLE to automatic ally detect and initiate the radiation/smoke protection mode of operation during the same conditions as the radiation protection function.

This ensures that habitability of the control room is maintained during times when a radiological

release could potentially occur.

COMPENSATORY MEASURES Chlorine Protection

The chlorine detection/isolation instrumentation is organized into two trip systems, with one trip

system (remote) located near the chlorine tank car and the other located in the control building

intake plenum (local). Each trip system contains two trip subsystems, with two detectors (one from each division) in each trip subsystem. Both trip subsystems in each trip system are

required to be OPERABLE any time the chlorine tank car is within the exclusion area to ensure

adequate protection for the control room under postulated toxic gas events.

The chlorine detectors in each trip system are arranged in a one-out-of-two taken-twice

configuration. One detector from each of the trip subsystems in a trip system must actuate to

initiate the automatic detection/isolation function. The loss of a single chlorine detector means

that the CREV System reliability is reduced because a single failure in the remaining

OPERABLE trip subsystem detector could result in reduced or lost system capability. The 7 day

out of service time is based on the low probability of a design basis chlorine gas event and a

single active failure occurring during this time period, and the capability of the remaining

detectors to provide the required isolation capabilities. The out of service time is consistent with

the out of service time allowed for loss of redundancy at the system level.

(continued)

CREV System Instrumentation B 3.12 Brunswick Unit 2 B 3.12-3 Revision No. 57 BASES COMPENSATORY MEASURES (continued)

The loss of both detectors in any trip subsystem means that the automatic protection function of

the chlorine detection/isolation system is lost.

Placing the CBHVAC System in the chlorine protection mode, through the use of control switches (as opposed to injection of a chlorine

injection signal) to close the appropriate dampers, ensures that the control room envelope is

protected, while at the same time allowing a valid radiation or smoke signal to initiate

appropriate protective actions. Operation in this mode is not limited in duration provided that

either trip system remains functional to ensure that the override function of the chlorine

protection mode is not lost.

Smoke Protection

Automatic detection/isolation of the control room envelope in response to an external smoke

event is dependent on the response of one of two Control Building Intake air duct smoke

detectors.

With both of the Control Building Intake air duct smoke detectors inoperable, the automatic

detection/isolation function of the external smoke protection system is lost. Placing the

CBHVAC System in the radiation/smoke protec tion mode is a suitable compensatory action to ensure that the automatic external smoke protection function is not lost.

TEST REQUIREMENTS Chlorine Protection

The CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the

entire channel will perform the intended function. The Control Building HVAC DBD (Reference 3) defines the specific actions to be satisfied by the chlorine isolation

instrumentation. The monthly frequency of the CHANNEL FUNCTIONAL TEST is consistent

with the testing frequencies performed by other utilities with this type of instrumentation.

(continued)

CREV System Instrumentation B 3.12 Brunswick Unit 2 B 3.12-4 Revision No. 23 BASES TEST REQUIREMENTS (continued)

The CHANNEL CALIBRATION of the trip units provides a check of the instrument loop and the

sensor when the sensor is replaced. The test verifies the calibration of the existing sensor prior

to removal and performs an installation calibration of the new sensor, including a complete

CHANNEL CALIBRATION with the new sensor installed, to verify the channel responds to the

measured parameter within the necessary range and accuracy. The CHANNEL CALIBRATION leaves the channel adjusted to ensure consistenc y with the system assumptions (Reference 3).

The chlorine detectors use an amperometric sensor consisting of a platinum cathode and silver

anode joined by an electrolytic salt bridge, all enclosed in a permeable membrane. This design

eliminates the majority of the maintenance required on previous detectors. The detectors have been in service at other facilities and have provided reliable service. The annual replacement

and calibration are based on a manufacturer recommendation. The adequacy of the

replacement interval has been confirmed through discussions with other utilities.

Smoke Protection

The CHANNEL FUNCTIONAL TEST for the Smoke protection instrumentation is consistent with

the testing performed in accordance with the existing fire detection instrumentation

requirements.

REFERENCES

1. 10 CFR 50, Appendix A, General Design Criterion 19, Control Room.

2. Regulatory Guide 1.95, Revision 1, Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release. 3. BNP Design Basis Document (DBD)-37, Control Building Heating, Ventilation, and Air Conditioning System.

RCS Chemistry B 3.13 Brunswick Unit 2 B 3.13-1 Revision No. 23 B 3.13 REACTOR COOLANT SYSTEM (RCS) CHEMISTRY

BASES The reactor water chemistry limits are established to prevent damage to the reactor materials in

contact with the coolant. Chloride limits are specified to prevent stress corrosion cracking of the

stainless steel. The effect of chloride is not as great when the oxygen concentration in the

coolant is low; thus, the higher limit on chlorides is permitted during full power operation. During

shutdown and refueling operations, the temperature necessary for stress corrosion to occur is

not present.

Conductivity measurements are required on a cont inuous basis since changes in this parameter are an indication of abnormal conditions. When the conductivity is within limits, the pH, chlorides, and other impurities affecting conductivity must also be within their acceptable limits.

With the conductivity outside the limits, additional samples must be examined to ensure that the

chlorides are not exceeding the limits.

The Test Requirements provide adequate assurance t hat concentrations in excess of the limits will be detected in sufficient time to take corrective action.

In order to reduce personnel radiation exposure, chemical decontamination of portions of the

Reactor Coolant System may be performed during shutdown. During the chemical

decontamination process, the injection of chemical solvents may cause the Reactor Coolant

System conductivity and chloride measurements to increase above the limits. The solvents that are selected for use in performing the chemical decontamination process are selected and

evaluated to ensure their chemical reactivity will not adversely impact components or the

structural integrity of the Reactor Coolant System. Because decontamination activities are performed at temperatures and pressures significantly less than normal operating temperatures, the chemical reactivity of these solvents will not increase the likelihood of stress corrosion

occurring nor affect those stress corrosion cracks that may already be present.

Structural Integrity 3.14 Brunswick Unit 2 B 3.14-1 Revision No. 65 B 3.14 STRUCTURAL INTEGRITY

BASES BACKGROUND The inservice inspection and testing programs for ASME Code Class 1, 2, 3, MC, and CC components ensure that the structural integrity and

operational readiness of these components will be maintained at an

acceptable level throughout the life of the plant. These programs are in accordance with Section XI of the ASME Boiler and Pressure Vessel

Code and applicable Addenda as required by 10 CFR Part 50.55a(g)

(Ref. 1) except where specific written relief has been granted by the

Commission pursuant to 10 CFR Part 50.55a(g)(6)(i).

TRMS For plant systems and components to be OPERABLE, structural integrity of these systems and components must be maintained in conformance with American Society of Mechanical Engineers (ASME) Code Section XI (Ref. 2), for those parts of a system that are subject to ASME Section XI

Code requirements.

This requirement applies to all ASME Section XI Code Class 1, 2, and 3

piping and components. In addition to piping and components, structural

support components such as pipe hangers, support steel, base plates, welds, bolts, etc. are considered part of the scope of this TRMS. Non-Section XI-Code-classed components are not part of the scope of this

TRMS.

Snubbers are not considered part of the scope of this TRMS. Snubbers

are addressed in TRMS 3.21.

For components with degraded material properties or relevant conditions as defined in ASME Section XI, the criteria for structural integrity are contained or referenced in Section XI. Alternative evaluation criteria may

be used to determine structural integrity, when approved by the NRC.

NRC expectations for structural integrity and operability of components

are described in NRC Inspection Manual 0326, Appendix C (Ref. 3). The

table below, which is found in Appendix C of NRC Inspection Manual

Chapter 0326, summarizes the NRC accepted methods available for

evaluating structural integrity of flaws in components including supports, classified as ASME Code Class 1, Class 2, and Class 3 components.

(continued)

Structural Integrity 3.14 Brunswick Unit 2 B 3.14-2 Revision No. 65 BASES TRMS (continued)

Pipe Class/

Energy ASME Code Section XI/

Construction Code NRC Approved Alternative e.g., RG approved Code Case Code Case N-513 (1) GL 90-05 Class 1/HE (2) X X Class 2/HE X X Class 2/ME (3) X X X Class 3/HE X X X Class 3/ME X X X X (1) Refer to NRC Regulatory Guide 1.147 for the latest revision acceptable to the NRC, and any conditions placed upon the code case. (2) HE - High Energy - Maximum oper ating temperature greater than 200°F or maximum operating pressure greater than 275 psig. (3) ME - Moderate Energy - Maximum operating temperature equal to or less than 200°F or maximum operating pressure equal to or less than

275 psig.

APPLICABILITY The components monitored by the Inservice Inspection Program have functions required for shutting down the reactor, maintaining the

shutdown condition, and mitigating the consequences of an accident.

Therefore, their structural integrity is required anytime there is fuel in the

reactor (i.e., MODES 1, 2, 3, 4, and 5). This requirement applies to all ASME Section XI Code Class 1, 2 ,and 3 piping and components, and to all ASME Section XI MC and CC components. This requirement does not

apply to piping and components that were designed and built to ASME

Section III Code or ANSI B31.1 requirements, that are not subject to ASME Section XI Code Class 1, 2, or 3 inservice inspection requirements (i.e., non-Code-Class components).

COMPENSATORY A Note has been provided to m odify the Compensatory Measures related MEASURES to structural integrity. Section 1.3, Completion Times, specifies once a Condition has been entered, subsequent divisions, subsystems, components or variables expressed in the Condition, discovered to be

inoperable or not within limits, will not result in separate entry into the (continued)

Structural Integrity 3.14 Brunswick Unit 2 B 3.14-3 Revision No. 65 BASES COMPENSATORY Condition. Section 1.3 also specifies Technical Requirements Manual MEASURES Required Compensatory Measures of the Condition continue to apply for (continued) each additional failure, with Completion Times based on initial entry into the Condition. However, the Technical Specification Required Actions and

TRM Required Compensatory Measures for systems provide appropriate compensatory measures for separate structural integrity conditions. As

such, a Note has been provided that allows separate Condition entry for

each structural integrity condition.

A.1 Upon initial discovery, supplemental NDE may be required to fully

characterize the degraded condition. Preliminary judgments regarding

structural integrity may be expressed considering the available

information and the expectation that a final determination of structural

integrity will result once all characterization, evaluation, and

documentation are complete.

During the time frame of these investigations, no Technical Requirements

Manual Specification is considered not met. The condition should be

immediately entered in the Corrective Action Program.

Condition A is modified by a Note, which requires that a structural

integrity evaluation must be completed.

If the indication is found to impact the structural integrity or

OPERABILITY/functionality of the component, system, or structure, or if

the evaluation of the indication has not been completed within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , then an unevaluated indication is considered to exist (i.e., an condition

which fails to meet the acceptance criteria of the ASME or applicable

code, the requirements of an NRC-accepted ASME Code Case, or an

NRC-approved alternative). In these circumstances, the TRMS shall be

declared "not met" and Condition B, C, or D is entered.

If the evaluation determines that the indication does not impact the

component, system, or structure OPERABILITY or structural integrity, the

indication becomes an evaluated indication and the TRMS is considered

met. The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time is deemed appropriate for providing a

reasonable amount of time to perform the necessary evaluations.

(continued)

Structural Integrity 3.14 Brunswick Unit 2 B 3.14-4 Revision No. 65 BASES COMPENSATORY A.1 (continued)

MEASURES There is no indeterminate state of operability. If, at any time, information

becomes available that negates a previous determination regarding

structural integrity, then the Technical Requirements Manual Specification

for structural integrity is considered not met and the appropriate Condition

shall be entered based on the Code Class of the affected component, system, or structure.

B.1, B.2, and B.3 When ASME Class 1 components do not meet ASME Code or

construction code acceptance standards, the requirements of an NRC

endorsed ASME Code Case, or an NRC approved alternative, then an

immediate operability determination cannot conclude a reasonable

expectation of operability exists and the affected component shall either

be isolated or the associated system, structure, or component shall be

declared inoperable and the associated TS Action statement or TRM

Required Compensatory Measure entered.

Satisfaction of Code acceptance standards is the minimum necessary for

operability of Class 1 pressure boundary components because of the

importance of the safety function being provided.

TS LCO 3.4.4, RCS Operational Leakage, does not permit any reactor

coolant pressure boundary leakage. Upon discovery of leakage from a

Class 1 pressure boundary component (pipe wall, valve body, pump

casing, etc.), the component must be immediately declared inoperable.

C.1.1, C.1.2, C.2, and C.3 When ASME Class 2 or Class 3 components do not meet ASME Code or

construction code acceptance standards, the requirements of an NRC

endorsed ASME Code Case, or an NRC approved alternative, then a

determination must be made of whether the nonconforming condition

results in a TS/TRM-required SCC or a TS/TRM-required support SSC

being inoperable. In order to determine the component is

OPERABLE/functional under an immediate operability determination, the

degradation mechanism must be readily apparent. To be readily

apparent, the degradation mechanism must be discernable from visual (continued)

Structural Integrity 3.14 Brunswick Unit 2 B 3.14-5 Revision No. 65 BASES COMPENSATORY C.1.1, C.1.2, C.2, and C.3 (continued)

MEASURES examination (such as external corrosion or wear), or there must be

substantial operating experience with the identified degradation

mechanism in the affected system. In addition, detailed non-destructive

examination data may be necessary to determine that a component is

OPERABLE/functional under an immediate operability determination.

If flaw examination and characterization, and engineering analysis, cannot be completed within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , the component should be declared

inoperable as specified in Required Compensatory Measure C and the

appropriate TS Action statement or TRM Required Compensatory

Measure entered. There is no indeterminate state of operability. NRC

regulations (Ref. 1) require that the structural integrity of ASME Code

Class 1, 2, and 3 components be maintained in accordance with the

ASME Code or construction code acceptance standards. If a structural

integrity concern is discovered in a Class 2 or Class 3 component while

conducting an inservice inspection, maintenance activity, or during facility

operation, corrective measures must be taken to restore structural

integrity before continuing or resuming operation in MODES 1, 2, or 3.

The affected component must be restored to ASME Code or construction

code acceptance standards by the end of the next refueling outage.

D.1, D.2, and D.3 When ASME Class MC or Class CC components do not meet acceptance

standards, the requirements of an NRC endorsed ASME Code Case, or

an NRC approved alternative, then a determination of whether the

degraded or nonconforming condition results in a TS/TRM-required SSC

or a TS/TRM-required support SCC being inoperable/non-functional must

be made.

Structural support components are required to be OPERABLE/functional

to support operability of related support functions. Examples of structural

degradation are concrete cracking and spalling, excessive deflection or

deformation of the steel containment liner, or missing/damaged pressure

boundary bolts. If the Code Class MC or Class CC structure is degraded, the structure's capability of performing its specified function shall be

assessed. As long as the identified degradation does not result in

exceeding acceptance limits specified in applicable design codes and

standards referenced in the design basis documents, the affected

structure is either OPERABLE or functional.

(continued)

Structural Integrity B 3.14 Brunswick Unit 2 B 3.14-6 Revision No. 65 BASES COMPENSATORY D.1, D.2, and D.3 (continued)

MEASURES NRC regulations (Ref. 1) require that the structural integrity of ASME

Code Class MC and CC components be maintained in accordance with

the ASME Code or construction code acceptance standards. If a

structural integrity concern is discovered in a Class MC or CC component

while conducting an inservice inspection, maintenance activity, or during

facility operation, corrective measures must be taken to restore structural

integrity before continuing or resuming operation in MODES 1, 2, or 3.

The affected component must be restored to ASME Code or construction

code acceptance standards by the end of the next refueling outage.

E.1 If the evaluation of operability/functionality cannot be completed within the

required Completion Time, the component shall be declared

inoperable/nonfunctional and the appropriate TS LCOs and TRMS

entered. TEST TR 3.14 REQUIREMENTS The structural integrity of ASME Section XI Code Class 1, 2, 3, MC, and

CC components is ensured by the successful completion of the Inservice

Inspection Program and by visual inspections of components for evidence

of deterioration or breach of integrity. This ensures that the structural

integrity of these components will be maintained in accordance with the

provisions of the Program.

The Frequencies for the TR is defined in the Inservice Inspection

Program. The testing and frequency for components in the Inservice

Inspection Program are consistent with the requirements of References 1

and 2. (continued)

Structural Integrity B 3.14 Brunswick Unit 2 B 3.14-7 Revision No. 65 BASES (continued)

REFERENCES 1. 10 CFR 50.55a(g), Inservice Inspection Requirements. 2. ASME Code,Section XI, 2001 Edition with 2003 Addenda

3. NRC Inspection Manual Chapter 0326, Operability Determinations and Functionality Assessments for Conditions Adverse to Quality

and Safety. 4. NRC Generic Letter 90-05, Guidance for Performing Temporary Non-code Repairs of ASME Code Class 1, 2, and 3 Piping. 5. NRC Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1. 6. UFSAR Section 3.2, Classification of Structures, Systems, and Components. 7. 0BNP-TR-001, Inservice Inspection Technical Report

8. AD-OP-ALL-0105, Operability Determinations and Functionality Assessments.

Brunswick Unit 2 B 3.15-1 Revision No. 23 B 3.15 Not used.

Service Water System OPERABILITY-Shutdown B 3.16 Brunswick Unit 2 B 3.16-1 Revision No. 58 B 3.16 SERVICE WATER SYSTEM OPERABILITY-SHUTDOWN

BASES For Mode 4 and 5 conditions, the Service Water System is designed to provide cooling water for

the removal of heat from equipment such as the emergency diesel generators, the Reactor

Building Closed Cooling Water (RBCCW) System and the Residual Heat Removal Service

Water (RHRSW) System. The Service Water Syst em provides cooling water for the service water pump motors. During the initial stage (0 - 10 minutes) of an event (DBA on the opposite

unit, loss of shutdown cooling, a loss of coolant inventory, etc.) potentially combined with a Loss

of Offsite Power (LOOP), the Service Water System must automatically provide cooling water to the emergency diesel generators. Following the first 10 minute period, shutdown cooling loads

must be supplied. The Service Water System also provides flow to the Turbine Building Closed

Cooling Water System, the Chlorination System, lube water to the Circulating Water Pumps, and fill to the Circulating Water System.

The Service Water System design allows either (or both) unit's nuclear header to supply diesel

generator cooling water when required. The phrase "site nuclear service water pump" refers to

any nuclear service water pump on either unit. Other pump designations refer to the specific

unit under discussion. The four nuclear service water pumps on site, two per unit, are each on

a separate emergency bus so that a single failure could prevent only one nuclear service water

pump from operating.

The OPERABILITY requirements are structured to ensure that the Service Water System is capable of automatically supplying sufficient cooling water for the diesel generators assuming

no operator action for the first 10 minutes following an event, and that at least one service water

pump for the shutdown unit is available to supply the shutdown cooling loads after the first ten

minutes following an event. The event includes consideration of a LOOP and/or a single active

failure. For the specific alignments associated with header maintenance, plant procedures

document required administrative controls and valve operability requirements needed to ensure that these objectives are met.

The four nuclear service water pumps are pow ered from separate emergency buses. The three conventional service water pumps on each unit are on separate emergency buses. For each

unit, two of the conventional pumps are on the same emergency buses as the two unit nuclear

service water pumps. The loss of one nuclear pump and one conventional pump on the unit

due to a single failure of one emergency bus has been accounted for in the OPERABILITY

requirements. However, conventional service water pump OPERABILITY will be more strictly defined in cases where only one nuclear pump and one conventional pump are available for

operation. Therefore, with one unit nuclear service water pump and one conventional service

water pump available, the conventional servic e water pump must be powered from a separate emergency bus to be considered OPERABLE.

(continued)

Service Water System OPERABILITY-Shutdown B 3.16 Brunswick Unit 2 B 3.16-2 Revision No. 58 BASES (continued)

In MODES 4 and 5, a conventional pump may be considered OPERABLE when only the

applicable header discharge valve is OPERABLE. This allows maintenance on the conventional

and nuclear headers without reducing Service Water System OPERABILITY. However, a

conventional pump aligned to the nuclear header is not considered to meet the requirements for

an OPERABLE nuclear pump since it is not automatically powered and restarted on the diesel

generators following an accident signal.

In MODES 4 and 5, with a DBA in the opposite unit, two nuclear service water pumps from one

or both units are capable of supplying sufficient flow to cool all four emergency diesel

generators under worst-case scenarios while also supplying flow to other potential flow paths (vital header loads, cross-header leakage, and pump strainer backwash flow). To prohibit any

single failure from preventing the supply of service water to the diesel generators during the first

10 minutes following a DBA, at least three nuclear service water pumps per site are required

while in MODE 4 or 5.

In MODES 4 and 5, one unit service water pump, nuclear or conventional, is capable of

supplying additional required safety-related and shutdown equipment. To prohibit any single

failure from preventing the supply of service water after the first 10 minutes following an event, at least two OPERABLE unit service water pumps, nuclear or conventional, are required while in

MODES 4 or 5. When only one header is available, an event with failure of one division of

emergency power can result in the need for manual actions in the reactor building to reposition

valves as the decay heat removal function is being restored.

The allowed out-of service times and Compensatory Measures established are conservative.

Although the probability and consequences of an event are reduced in MODES 4 and 5, the

Compensatory Measures for the nuclear service water pumps for a unit in MODE 4 or 5 are

based on the assumption that the other unit is in MODE 1, 2, or 3. Specific Compensatory

Measures have not been established for both units in MODES 4 or 5 since the

COMPENSATORY MEASURES for one unit in MODE 4 or 5 are more conservative.

In MODES 4 and 5, a LOCA is not considered credible and core decay heat loads are reduced.

As such, availability of service water for vital header loads is not needed. However, in

MODES 4 and 5, the availability of service water is required to support cooling for decay heat

removal systems. Therefore, the OPERABILITY requirements for the unit service water pumps apply for nuclear or conventional pumps. With one OPERABLE unit service water pump, the

applicable decay heat removal systems remain OPERABLE. However, to minimize the

possibility of loss of these systems due to loss of the single pump, the out of service time for one OPERABLE unit service water pump is set at 7 days. For no OPERABLE unit service

water pumps, the applicable decay heat removal systems must be declared inoperable.

(continued)

Service Water System OPERABILITY-Shutdown B 3.16 Brunswick Unit 2 B 3.16-3 Revision No. 58 BASES (continued)

In MODES 4 and 5, Condition A allows one unit to operate with the nuclear service water

header inoperable for up to 14 days provided that: a) two nuclear service water pumps are OPERABLE on the other unit, b) both units' nuclear service water header valves are administratively controlled as required to ensure cooling water to the diesel generators, c) the Service Water System conventional header is OPERABLE with two unit conventional service water pumps OPERABLE, and d) administrative controls are established to isolate OPERABLE conventional service water pumps and required loads from the inoperable nuclear header.

Considering any additional single failure, this requirement ensures at least one OPERABLE

nuclear service water pump to supply the diesel generators during the first 10 minutes after an

event and one OPERABLE conventional service water pump to supply the unit shutdown

cooling loads. By requiring administrative control of applicable valves, the Required Compensatory Measure minimizes the risk of inadvertent valve action that could reduce cooling

water flow to the diesel generators or result in flow diversion that could affect CSW flow to

essential loads.

Service Water System-Shutdown Operations B 3.17 Brunswick Unit 2 B 3.17-1 Revision No. 23 B 3.17 SERVICE WATER SYSTEM-SHUTDOWN OPERATIONS

BASES This Specification permits securing the Serv ice Water System conventional header when the nuclear header is out of service and is required to permit flange installation in Service Water

System header cross-connect piping.

CREV System-Smoke Protection Mode B 3.18 Brunswick Unit 2 B 3.18-1 Revision No. 23 B 3.18 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM-SMOKE PROTECTION MODE BASES BACKGROUND One of the principal design objectives of the Control Building Heating, Ventilation and Air

Conditioning (CBHVAC) System is to permit continuous occupancy of the control room

emergency zone under normal operating conditions and under the postulated design basis

events throughout the life of the plant. The Control Building HVAC System must function to

provide protection to the operators for three type events: a radiation event, up to and including

a Design Basis Accident (e.g., Main Steam Line Break [MSLB] Accident, Refueling Accident, Control Rod Drop Accident, or Loss of Coolant accident [LOCA]), a toxic gas event (complete

rupture of the 55 ton chlorine tank car located near the service water building, or a slow leak

lasting for an extended period of time), and an ex ternal smoke event. These events form the basis for the design of the Control Room Emer gency Ventilation (CREV) System function of the CBHVAC System. The radiation protection func tion of CREV System is addressed in Technical

Specifications.

The CREV System is designed to meet General De sign Criterion (GDC) 19 (Reference 1). In

addition, the system is designed using the guidance of Regulatory Guide 1.95, Revision 1 (Reference 2).

TRMS OPERABILITY of the CREV System ensures that the control room will remain habitable for

operations personnel during and following all credible hazard event scenarios external to the

control room, consistent with the assumptions in the various analyses. Two redundant

subsystems of the CREV System are required to be OPERABLE to ensure that at least one is

available, assuming a single failure disables the other subsystem. The CREV System is

considered OPERABLE when the individual components necessary to control operator

exposure are OPERABLE in both subsystems. For the smoke protection mode, a subsystem is considered OPERABLE when its associated: 1. Fan is OPERABLE,

2. HEPA filter and charcoal adsorbers are not excessively restricting flow and are capable of performing their filtration functions, and 3. Ductwork and dampers are OPERABLE, and when air circulation exists (as required in Reference 3, Section 3.1).

(continued)

CREV System-Smoke Protection Mode B 3.18 Brunswick Unit 2 B 3.18-2 Revision No. 23 BASES TRMS (continued) Two additional OPERABILITY requirements apply to all modes of CREV System operation. The

CBHVAC Control Air System must be OPERABLE to support damper operation. In addition, the control room envelope must be maintained, including the integrity of the walls, floors, ceilings, ductwork, and access doors. The control room envelope includes the electronic equipment rooms, the central control room area, computer rooms, kitchen, restrooms, and the supply and

return ductwork up to and including the isolation dampers.

The following components, including their associated logic trains, actuation devices, and power

supplies, are non-redundant. Their OPERABILITY affects both trains of the CREV System.

These components are: control room (washr oom) exhaust isolation damper, control room normal make-up damper, and the control room emergency recirculation damper. In addition, the control room is not equipped with redundant outdoor air intakes (References 4 and 5).

The radiation/smoke protection mode of operation provides protection to the control room operators in the event of an external smoke event.

During an external smoke event, the CBHVAC Syst em is required to automatically isolate and enter the radiation/smoke protection mode on a smoke detection signal from the Control Room Envelope Smoke Protection Zone Function. Upon receipt of a smoke detection signal, the

CBHVAC System is automatically realigned to the emergency mode of operation. The normal

fresh air inlet closes, and, at approximately the same time, the emergency air filtration units

begin operation, recirculating control room air and providing filtered makeup air to minimize

smoke build-up and provide positive pre ssure in the control room envelope.

APPLICABILITY The applicabilities ensure that system is capable of performing the required smoke protection function when the potential for external hazards exist.

COMPENSATORY MEASURES With one emergency filtration subsystem i noperable, the inoperable subsystem must be restored to OPERABLE status within 7 days. With the unit in this condition, the remaining

subsystem is adequate to perform control room smoke protection. The loss of a single

emergency filtration unit means that the CREV System reliability is reduced because a single

failure in the OPERABLE subsystem could result in reduced or lost system capability. The

7 day out of service time is based on the low probability of an external smoke event and a single

failure in the OPERABLE subsystem occurring during this time period, and the capability of the

remaining subsystem to provide the required capabilities.

(continued)

CREV System-Smoke Protection Mode B 3.18 Brunswick Unit 2 B 3.18-3 Revision No. 23 BASES COMPENSATORY MEASURES (continued)

If the inoperable subsystem cannot be restored to OPERABLE status within the required 7 days, Required Compensatory Measures must be taken to return the subsystem to OPERABLE status and initiate a Condition Report.

The loss of both emergency filtration subsystems means that the smoke protection function is

lost. In this Condition, Required Compensatory Measures must be taken to return the

subsystems to OPERABLE status and initiate a Condition Report.

The Required Compensatory Measures are modified by a Note which eliminates the

requirement to initiate a Condition Report when equipment inoperability is due solely to planned

maintenance or performance of surveillance. The intent of initiation of a Condition Report is to

ensure that proper corrective actions are taken to restore inoperable equipment. When

equipment is inoperable due to planned maintenance or performance of surveillance testing, such corrective actions are not required. If, however, unexpected failures are identified during

performance of the maintenance or surveillance testing, a Condition Report shall be initiated.

TEST REQUIREMENTS The Test Requirement demonstrates functional capab ility of the system by verifying automatic emergency system initiation upon receipt of a smoke detection signal.

REFERENCES

1. 10 CFR 50, Appendix A, General Design Criterion 19, Control Room.

2. Regulatory Guide 1.95, Revision 1, Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chemical Release. 3. DBD-37, Design Basis Document for Control Building Heating, Ventilation, and Air Conditioning System. 4. NUS-3697, Revision 2, February 1983, Control Room Habitability Analysis.

5. NLU-83-673, TMI Action Item III.D.3.4-Control Room Habitability, NRC Safety Evaluation dated October 18, 1983.

CREV System-Chlorine Protection Mode B 3.19 Brunswick Unit 2 B 3.19-1 Revision No. 23 B 3.19 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM-CHLORINE PROTECTION MODE BASES BACKGROUND One of the principal design objectives of the Control Building Heating, Ventilation and Air

Conditioning (CBHVAC) System is to permit continuous occupancy of the control room

emergency zone under normal operating conditions and under the postulated design basis

events throughout the life of the plant. The Control Building HVAC System must function to

provide protection to the operators for three type events: a radiation event, up to and including

a Design Basis Accident (e.g., Main Steam Line Break [MSLB] Accident, Refueling Accident, Control Rod Drop Accident, or Loss of Coolant Accident [LOCA]), a toxic gas event (complete

rupture of the 55 ton chlorine tank car located near the service water building, or a slow leak

lasting for an extended period of time), and an ex ternal smoke event. These events form the basis for the design of the Control Room Emer gency Ventilation (CREV) System function of the CBHVAC System. The radiation protection func tion of CREV System is addressed in Technical

Specifications.

The CREV System is designed to meet General De sign Criterion (GDC) 19 (Reference 1). In

addition, the system is designed using the guidance of Regulatory Guide 1.95, Revision 1 (Reference 2). Commitments have also been made to design the chlorine detection and

isolation logic to single failure criteria, with approved exceptions (Reference 3, Section 3.6).

TRMS OPERABILITY of the CREV System ensures that the control room will remain habitable for

operations personnel during and following all credible hazard event scenarios external to the

control room, consistent with the assumptions in the various analyses. Two redundant

subsystems of the CREV System are required to be OPERABLE to ensure that at least one is

available, assuming a single failure disables the other subsystem. The CREV System is

considered OPERABLE when the individual components necessary to control operator

exposure are OPERABLE in both subsystems. For the chlorine protection mode, a subsystem

is considered OPERABLE when: 1. The isolation dampers are OPERABLE, and

2. The logic components necessary to achieve automatic isolation are functional, as described in Reference 3, Section 3.1.

(continued)

CREV System-Chlorine Protection Mode B 3.19 Brunswick Unit 2 B 3.19-2 Revision No. 23 BASES (continued)

TRMS (continued) Two additional OPERABILITY requirements apply to all modes of CREV System operation. The

CBHVAC Control Air System must be OPERABLE to support damper operation. In addition, the control room envelope must be maintained, including the integrity of the walls, floors, ceilings, ductwork, and access doors. The control room envelope includes the electronic equipment rooms, the central control room area, computer rooms, kitchen, restrooms, and the supply and

return ductwork up to and including the isolation dampers.

The following components, including their associated logic trains, actuation devices, and power

supplies, are non-redundant. Their OPERABILITY affects both trains of the CREV System.

These components are: control room (washr oom) exhaust isolation damper, control room normal make-up damper, and the control room emergency recirculation damper. In addition, the control room is not equipped with redundant outdoor air intakes (References 4 and 5).

In the event of a chlorine release, the CBHVAC System enters a full recirculation mode (chlorine protection mode), with no outdoor air intake. The emergency filtration trains do not start, since

they do not effectively remove chlorine and may be damaged by the presence of chlorine.

Protection for chlorine gas events "overrides" any concurrent, ongoing, or subsequent radiation

or smoke initiation signals. The override design offers protection to operations personnel in the

control room by providing protection against potentially fatal chlorine gas releases. This

protection is required any time the chlorine tank car is within the exclusion area.

APPLICABILITY OPERABILITY of the chlorine protection mode of the CREV System is required any time the chlorine tank car is within the exclusion area. Analyses demonstrate that movement of the tank

car outside the exclusion area sufficiently reduces the threat of control room operator

incapacitation from a release of this chemical.

COMPENSATORY MEASURES With the chlorine protection mode inoperable for reasons other than inoperable chlorine

isolation instrumentation, the chlorine tank car must be removed from the exclusion area within

the next eight hours to ensure adequate protection for the operators. Chlorine gas protection is

not required with the tank car outside of the exclusion area. Eight hours is considered adequate

time to perform the necessary system alignments and to allow plant personnel to remove the

chlorine tank car from the site in an orderly manner.

(continued)

CREV System-Chlorine Protection Mode B 3.19 Brunswick Unit 2 B 3.19-3 Revision No. 23 BASES COMPENSATORY MEASURES (continued)

With the plant physically unable to remove the chlorine tank car from the site, Required

Compensatory Measures must be taken to return the chlorine protection mode to OPERABLE

status and initiate a Condition Report.

Compensatory Measure A.2.2 is modified by a Note which eliminates the requirement to initiate a Condition Report when equipment inoperability is due solely to planned maintenance or

performance of surveillance. The intent of initiation of a Condition Report is to ensure that

proper corrective actions are taken to restore inoperable equipment. When equipment is

inoperable due to planned maintenance or performance of surveillance testing, such corrective

actions are not required. If, however, unexpected failures are identified during performance of

the maintenance or surveillance testing, a Condition Report shall be initiated.

TEST REQUIREMENTS The Test Requirement demonstrates functional capabilit y of the system by verifying the override function of the chlorine protection function. Testing of the chlorine override function ensures

OPERABILITY of the chlorine protection mode of the CREV System by demonstrating the capability of the system to prevent the emergency filtration units from initiating during a chlorine

event.

REFERENCES

1. 10 CFR 50, Appendix A, General Design Criterion 19, Control Room.

2. Regulatory Guide 1.95, Revision 1, Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chemical Release. 3. DBD-37, Design Basis Document for Control Building Heating, Ventilation, and Air Conditioning System. 4. NUS-3697, Revision 2, February 1983, Control Room Habitability Analysis.

5. NLU-83-673, TMI Action Item III.D.3.4-Control Room Habitability, NRC Safety Evaluation dated October 18, 1983.

Flood Protection B 3.20 Brunswick Unit 2 B 3.20-1 Revision No. 23 B 3.20 FLOOD PROTECTION

BASES The limitation on flood protection ensures that facility protective actions will be taken and operation will be terminated in the event of flood conditions. The limit of elevation 17'6" Mean

Sea Level is based on the maximum elevation at which facility flood control measures provide protection to safety-related structures, systems, components, and equipment.

Snubbers B 3.21 Brunswick Unit 2 B 3.21-1 Revision No. 66 B 3.21 SNUBBERS

BASES All snubbers are required OPERABLE to ensure that the structural integrity of the Reactor

Coolant System and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure

of the systems which they are installed, w ould have no adverse effect on any safety-related system.

A list of all required individual snubbers necessary for structural integrity, with detailed

information of snubber location and size and of system affected, shall be available at the plant

in accordance with Section 50.71(c) of 10 CFR Part 50. The accessibility of each snubber shall

be based upon the existing radiation levels and the expected time to perform a visual inspection

in each snubber location as well as other factors associated with accessibility during plant

operations (e.g., temperature, atmosphere, locations, etc.), and the recommendations of

Regulatory Guides 8.8 and 8.10. The addition or deletion of any hydraulic or mechanical

snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.

Amendments 241 and 269 (Reference 1) to Renewed Facility Operating Licenses DPR-71

and DPR-62 for Units 1 and 2, respectively, approved the addition of Technical Specification

Limiting Condition for Operation (LCO) 3.0.8 for snubbers. LCO 3.0.8 establishes conditions

under which systems are considered to remain capable of performing their intended safety

function when associated snubbers are not capable of providing their associated support

function(s). LCO 3.0.8 states that the supported system is not considered to be inoperable

solely due to one or more snubbers not capable of performing their associated support

function(s).

Compensatory Measure A applies when one or more snubbers are not capable of providing

their associated support function(s) to a single train or subsystem of a multiple train or

subsystem supported system or to a single tr ain or subsystem supported system. TRMS, Compensatory Measure A.1 requires an engineering evaluation to be performed on the

attached component to determine if the component is acceptable for continued operation. The

Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is based on the original licensing basis for snubbers and is

considered acceptable based on the amount of time required to perform the required

engineering evaluation.

Compensatory Measure A.2 allows 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months to restore the snubber(s) before declaring the

supported system inoperable. The 72 hour8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Completion Time is reasonable based on the low

probability of a seismic event concurrent with an event that would require operation of the

supported system occurring while the snubber(s) are not capable of performing their associated

support function and due to the availability of the redundant train of the supported system.

(continued)

Snubbers B 3.21 Brunswick Unit 2 B 3.21-2 Revision No. 66 BASES (continued)

Compensatory Measure B applies when one or more snubbers are not capable of providing

their associated support function(s) to more than one train or subsystem of a multiple train or

subsystem supported system. Compensatory Measure B.1 requires an engineering evaluation to be performed on the attached component to determine if the component is acceptable for

continued operation. The Completion Time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months is based on the original licensing basis

for snubbers and is considered acceptable based on the amount of time required to perform the

required engineering evaluation.

Compensatory Measure B.2 allows 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to restore the snubber(s) before declaring the

supported system inoperable. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Completion Time is reasonable based on the low

probability of a seismic event concurrent with an event that would require operation of the

supported system occurring while the snubber(s) are not capable of performing their associated

support function.

REFERENCES

1. Letter from Stewart N. Bailey (USNRC) to James Scarola (CP&L) dated February 15, 2007, Issuance of Amendment to Adopt TSTF-372 (TAC Nos. MD1371 and MD1372).

Sealed Source Contamination B 3.22 Brunswick Unit 2 B 3.22-1 Revision No. 23 B 3.22 SEALED SOURCE CONTAMINATION

BASES The limitation on removable contamination for sources requiring leak testing, including alpha

emitters, is based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from by-product, source, and special nuclear material sources will not exceed allowable

intake values. Sealed sources are classified into three groups according to their damage to a

source in that group. Those sources which are frequently handled are required to be tested

more often than those which are not. Sealed sources that are continuously enclosed within a

shielded mechanism, i.e., sealed sources with radiation monitoring or boron measuring devices, are considered to be stored and need not be tested unless they are removed from the shielding

mechanism. Fission detectors associated with Local Power Range Monitors are considered to

be stored and continuously enclosed within a shielded mechanism when the fission detector is

enclosed in the associated detector housing tube provided the detector housing tube is not

breached.

Decay Time B 3.23 Brunswick Unit 2 B 3.23-1 Revision No. 23 B 3.23 DECAY TIME

BASES The minimum requirement for reactor subcriticality prior to fuel movement ensures that sufficient

time has elapsed to allow the radioactive decay of the short lived fission products. This decay

time is consistent with the assumptions used in the accident analyses.

Communications B 3.24 Brunswick Unit 2 B 3.24-1 Revision No. 23 B 3.24 COMMUNICATIONS

BASES The requirement for communications capability ensures that refueling station personnel can be

promptly informed of significant changes in the facility status or core reactivity condition during

movement of fuel within the reactor pressure vessel.

Crane and Hoist Operability B 3.25 Brunswick Unit 2 B 3.25-1 Revision No. 23 B 3.25 CRANE AND HOIST OPERABILITY

BASES The OPERABILITY requirements of the cranes and hoists used for movement of fuel

assemblies ensures that: 1) each has sufficient load capacity to lift a fuel element, and 2) the

core internals and pressure vessel are protected from excessive lifting force in the event they

are inadvertently engaged during lifting operations.

The fuel grapple hoist overload cutoff demonstration load of 1600 pounds is based on the

submerged fuel bundle loads of 650 pounds, the highest unloaded hoist cable-supported load of

approximately 660 pounds, and a tolerance for fuel bundle friction and load spikes of

290 pounds.

The fuel grapple hoist loaded interlock demonstration load of 750 pounds is based on the

highest unloaded hoist cable-supported load of approximately 660 pounds plus a tolerance for

load spikes of 90 pounds as sections are raised and lowered.

Crane Travel-Spent Fuel Storage Pool B 3.26 Brunswick Unit 2 B 3.26-1 Revision No. 23 B 3.26 CRANE TRAVEL-SPENT FUEL STORAGE POOL

BASES The restriction on movement of loads in excess of the weight specified provides some

assurance that with the failure of the lifting device the fuel pool would not be damaged to such a

degree that the irradiated fuel would be subjected to a loss-of-coolant.

Brunswick Unit 2 Revision No. 23 APPENDIX A RELOCATED ITEMS MATRIX

TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-1) Revision No. 23

ITS CTS Description General Location Specific Location 2.0 LA.2 6.7.1.b, 6.7.1.c, and

6.7.1.d Safety Limit Violations and the notification of the Vice

President-Brunswick Nuclear Plant along with submittal of

a report. UFSAR Section 13.5.1 3.0 LA.1 3.0.4 Discussion of intent of CTS 3.0.4 phrase "Exceptions to this Specification are stated in individual Specifications." Bases B 3.0: LCO 3.0.4 3.1.1 LA.1 4.1.1.a Detail of the method for performing the surveillance. Bases B 3.1.1: SR 3.1.1.1 3.1.2 LA.1 3.1.2 Action a Perform an analysis to determine and explain the cause of the reactivity difference. Bases B 3.1.2: Action A.1 3.1.3 LA.1 3.1.3.1 Actions a.1.b Details for method of disarming stuck control rods. Bases B 3.1.3: Actions A.1, A.2, A.3, and A.4 3.1.3 LA.1 3.1.3.1 Actions b.1.c

and b.2.a.

3.1.3.6 Action a.2 Details for method of disarming non-stuck control rods. Bases B 3.1.3: Actions C.1 and C.2 3.1.3 LA.2 4.1.3.6 Details of method of performing the control rod coupling integrity checks. Bases B 3.1.3: SR 3.1.3.5 3.1.3 LA.3 3.1.3.7 Action a Methods for determining the position of a control rod and

details of which control rod position switches are required. Bases B 3.1.3: SR 3.1.3.1 3.1.3 LA.4 3.1.3.6 Action a.2 Method of coupling a control rod. Bases B 3.1.3: Actions C.1 and

C.2 3.1.3 LA.5 4.1.1.b Unit 2 Detail of method of performing SDM. Bases B 3.1.3: Actions A.1, A.2, A.3, and A.4 3.1.4 LA.1 4.1.3.2, 4.1.3.3, and

4.1.3.4 Details of the method for performing control rod scram

time testing. Bases B 3.1.4: SR 3.1.4.1, SR 3.1.4.2, and

SR 3.1.4.4 3.1.4 LA.2 4.1.3.2.c Details of what constituted a representative sample of control rods to be tested. Bases B 3.1.4: SR 3.1.4.2 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-2) Revision No. 23

ITS CTS Description General Location Specific Location 3.1.5 LA.1 4.1.3.5 Details of the method of verifying OPERABILITY of control rod scram accumulators (not in alarmed condition). Bases B 3.1.5: SR 3.1.5.1 3.1.5 LC.1 4.1.3.5.a and 4.1.3.5.b Control rod scram accumulators, leak detectors, and

pressure detectors testing. UFSAR Section 3.9.4.1.2.4 3.1.7 LA.1 3.1.5 Details of what constitutes an OPERABLE Standby Liquid Control (SLC) System. Bases B 3.1.7: Background and LCO 3.1.7 LA.2 4.1.5.b.3 Details of the method for performing test that verifies SLC boron concentration. Bases B 3.1.7: SR 3.1.7.5 3.1.7 LA.2 4.1.5.c.1 Details of the method for performing test that verifies SLC flow of system to reactor. Bases B 3.1.7: SR 3.1.7.7 3.1.7 LA.3 4.1.5.c.3 SLC System relief valve setting. UFSAR Section 9.3.4.4 3.1.7 LA.5 Figure 3.1.5-1 Statement that boron concentration range in

Figure 3.1.5-1 supports a boron concentration of 660

ppm. Bases B 3.1.7: Applicable Safety Analysis 3.1.8 LA.1 4.1.3.1.1 Note

Allowance for scram discharge volume vent and drain

valves to be closed intermittently under administrative

control during testing. Bases B 3.1.8: SR 3.1.8.1 None 3/4.1.3.8 LA.1 Requirement for CRD housing support to be in place. TRM TRMS 3.1 3.2.1 LA.1 3.2.1 The types of APLHGR limits, the methodology used to determine the limits, and the COLR location of the limits to

be used when hand calculations are required. Bases B 3.2.1: LCO 3.2.1 LA.2 3.2.1 Action Requirement to "initiate corrective action within 15 minutes and continue corrective action" to restore limit. Bases B 3.2.1: Action A.1 3.2.2 LA.1 3.2.2.1 Details that MPCR limits in the COLR are provided as a function of core flow, core power, and cycle average

exposure. Bases B 3.2.2: LCO 3.2.2 LA.2 3.2.2.1 Action Requirement to "initiate corrective action within 15 minutes and continue corrective action" to restore limit. Bases B 3.2.2: Action A.1 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-3) Revision No. 23

ITS CTS Description General Location Specific Location 3.2.2 LA.3 3.2.2.2 Details related to the determination of average control rod scram time (Tau) and the use of Tau in determining the

operating limits of MCPRs. UFSAR Section 4.4.1.5 3.3.1.1 LA.1 Table 2.2.1-1 Trip setpoints for associated instrumentation. TRM Appendix B: TRM Table 3.3.1.1-1 3.3.1.1 LA.2 Table 2.2.1-1

Note (a) Design details of IRM RPS instrumentation. Bases B 3.3.1.1: ASA/ LCO/ APP of Function 1.a 3.3.1.1 LA.2 Table 2.2.1-1

Notes (c) and (d) Design details of APRM RPS instrumentation. Bases B 3.3.1.1: ASA/ LCO/ APP of Functions 2.b and 2.c 3.3.1.1 LA.3 Table 2.2.1-1

Note (b) Note (b): APRM Neutron Flux - High, Startup Function is a

fixed point and is increased when the reactor mode switch

is placed in run position. UFSAR Section 7.6.1.1.4 3.3.1.1 LA.3 Table 2.2.1-1

Notes (e) and (f) Note (e): Main Steam Line Isolation Valve - Closure

Function is bypassed when not in the run mode.

Note (f): TSV - Closure and TCV Fast Closure Functions

are bypassed < 30% rated thermal power. UFSAR Section 7.2.1.1.4 3.3.1.1 LA.4 Table 2.2.1-1

Note (g) Vessel water levels are referenced to REFERENCE

LEVEL ZERO. Bases B 3.3.1.1: ASA/ LCO/ APP of Function 4 3.3.1.1 LA.5 3.3.1 Actions

and **

Notes Details relating to placing channels in trip. Bases B 3.3.1.1: Actions A.1 and A.2; B.1 and B.2 3.3.1.1 LA.6 4.3.1.2 Details of the method for performing surveillances. Bases B 3.3.1.1: SR 3.3.1.1.15 3.3.1.1 LA.6 Table 4.3.1-1

Note (e) Details of the method for performing surveillances. Bases B 3.3.1.1: SR 3.3.1.1.3 3.3.1.1 LA.6 Table 4.3.1-1

Note (g) Details of the method for performing surveillances. Bases B 3.3.1.1: SR 3.3.1.1.8 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-4) Revision No. 23

ITS CTS Description General Location Specific Location 3.3.1.1 LA.7 Table 3.3.1-1

Note (b) Requirements associated with the removal of shorting

links. UFSAR Section 7.6.1.1.1.2.d 3.3.1.1 LA.8 Table 3.3.1-1

Note (c) Number of LPRM inputs for APRM OPERABILITY. Bases B 3.3.1.1: ASA/LCO/APP of APRM. 3.3.1.1 LA.9 Table 4.3.1-1

Note (h) Details on how to perform calibration of position switches. Bases B 3.3.1.1: SR 3.3.1.1.13 3.3.1.2 LA.1 4.3.5.4.b Details of the method for performing the surveillance. Bases B 3.3.1.2: LCO 3.3.1.2 LA.2 3/4.9.2 Details relating to SRM OPERABILITY. Bases B 3.3.1.2: LCO; SR 3.3.1.2.4 3.3.1.2 LA.3 3.9.2.c Removal of RPS shorting links. UFSAR Section 7.6.1.1.1.2.d 3.3.2.1 LA.1 Table 3.3.4-2 Trip setpoints for associated instrumentation. TRM Appendix B: TRM Table 3.3.2.1-1 3.3.2.1 LA.2 Table 4.3.1-1

Note (a) Details of the methods for performing the RBM CHANNEL

CALIBRATION. Bases B 3.3.2.1: SR 3.3.2.1.7 3.3.2.1 LA.3 3.1.4.1 Action d.2 Details relating to actions when an individual control rod is

bypassed on the RWM. Bases B 3.3.2.1: Actions C.1, C.2.1.1, C.2.1.2, and

C.2.2 3.3.2.1 LA.4 4.1.4.1.1 Details of the methods for performing RWM CHANNEL FUNCTIONAL TEST. Bases B 3.3.2.1: SR 3.3.2.1.2 and SR 3.3.2.1.3 3.3.2.1 R.1 3/4.3.4.1 3/4.3.4.3

3/4.3.4.4

3/4.3.4.5 Control Rod Block Instrumentation for APRM, IRM, SRM, and SDV LCO's and Surveillance Requirements. TRM TRMS 3.3 and Appendix C: TRM Table 3.3-2 3.3.3.1 LA.1 Table 3.3.5.3-

1 ACTION 81 The use of alternate methods of post accident monitoring. Bases B 3.3.3.1: Action B.1 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-5) Revision No. 23

ITS CTS Description General Location Specific Location 3.3.3.1 LA.2 Table 4.3.5.3-

1 Note (a) Details of the method for performing the surveillance. Bases B 3.3.3.1: SR 3.3.3.1.2 and SR 3.3.3.1.3 3.3.3.1 LA.3 3.6.6.4 Details relating to system design. Bases B 3.3.3.1: LCO for Function 9 3.3.3.1 LA.4 4.6.6.4 Details of the method for performing the surveillance. Bases B 3.3.3.1: SR 3.3.3.1.2 and SR 3.3.3.1.3 3.3.3.1 R.1 3/4.3.5.3 Accident Monitoring Instrumentation; Suppression Chamber Atmosphere Temperature,Drywell Radiation (Airborne radiation monitors),Safety/Relief Valve Position

Indication,Turbine Building Ventilation Monitor, Offgas

Stack Ventilation Monitor LCO's and Surveillance

Requirements. TRM TRMS 3.4 3.3.3.2 LA.1 3/4.3.5.2 Details relating to system design and operation. Bases B 3.3.3.2: LCO and Table B 3.3.3.2-1 3.3.4.1 LA.1 3/4.3.6.1 Trip setpoints for associated instrumentation. TRM Appendix B: TRM Table 3.3.4.1-1 3.3.4.1 LA.2 Table 3.3.6.1-

2 Note (a)

Vessel water levels are referenced to REFERENCE

LEVEL ZERO. Bases B 3.3.4.1: ASA/ LCO/ APP of Function a 3.3.5.1 LA.1 3/4.3.3 Trip setpoints for associated instrumentation. TRM Appendix B: TRM Table 3.3.5.1-1 3.3.5.1 LA.2 4.3.3.2 Details of methods of performing the LOGIC SYSTEM FUNCTIONAL TESTS. Bases B 3.3.5.1: SR 3.3.5.1.5 3.3.5.1 LA.3 Table 3.3.3-1

Function 2.c Reactor Vessel Shroud Level Function is a permissive for drywell spray. Bases B 3.3.5.1: ASA/ LCO/ APP of Function 2.e 3.3.5.1 LA.3 Table 3.3.3-1

Functions 4.e

and 4.f CS and RHR Pump Discharge Pressure-High Functions

are permissives for ADS. Bases B 3.3.5.1: ASA/ LCO/ APP of Functions 4.d, 4.e, 5.d, and 5.e 3.3.5.1 LA.4 Table 3.3.3-1

Function 2.d.1 Details associated with equipment started by the LPCI

Reactor Steam Dome Pressure-Low Function. Bases B 3.3.5.1: ASA/ LCO/ APP of Functions 1.c and 2.c TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-6) Revision No. 23

ITS CTS Description General Location Specific Location 3.3.5.1 LA.5 Table 3.3.3-1

Note (c) Detail which describes what equipment receives the HPCI

pump suction swap over signals. Bases B 3.3.5.1: ASA/ LCO/ APP of Functions 3.d and 3.e 3.3.5.1 LA.6 Table 3.3.3-1

ACTION 30,

item b Requirement to place all inoperable channels that do not

cause the trip function to occur in the tripped condition. Bases B 3.3.5.1: Actions B.1, B.2, and B.3 3.3.5.1 LA.7 Table 3.3.3-2

Note (b) Note (b): Reactor vessel water levels are referenced to

REFERENCE LEVEL ZERO. Bases B 3.3.5.1: ASA/ LCO/ APP of Functions 1.a and 2.a, 2.e, 3.a, 3.c, 4.a and 5.a, and 4.c and 5.c 3.3.5.1 LA.7 Table 3.3.3-2

Note (c) Note (c): Suppression chamber water level zero is the

torus centerline minus 1 inch. Bases B 3.3.5.1: ASA/ LCO/ APP of Function 3.e 3.3.5.1 R.1 3/4.3.3.1.e 3/4.3.3.2.f

3/4.3.3.3.e

3/4.3.3.4.g ECCS Actuation Instrumentation LCO and Surveillances

associated with:

Core Spray Bus Power Monitor;

LPCI Bus Power Monitor;

HPCI Bus Power Monitor; and

ADS Bus Power Monitor. TRM TRMS 3.6 3.3.5.1 R.2 3/4.3.3.4.a ADS Inhibit Switch LCO and Surveillance Requirements. TRM TRMS 3.7 3.3.5.2 LA.1 3/4.3.7 Trip setpoints for associated instrumentation. TRM Appendix B: TRM Table 3.3.5.2-1 3.3.5.2 LA.2 4.3.7.2 Details relating to the methods for performing the LOGIC SYSTEM FUNCTIONAL TEST. Bases B 3.3.5.2: SR 3.3.5.2.5 3.3.5.2 LA.3 Table 3.3.7-1

Notes (b) and (c) RCIC System design and operational details. Bases B 3.3.5.2: Background 3.3.5.2 LA.3 Table 3.3.7-1

Note (d) RCIC System design and operational details. Bases B 3.3.5.2: ASA/ LCO/

APP of Function 3 3.3.5.2 LA.4 Table 3.3.7-2

Note (a) Reactor vessel water levels are referenced to

REFERENCE LEVEL ZERO. Bases B 3.3.5.2: ASA/ LCO/

APP of Functions 1 and 2 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-7) Revision No. 23

ITS CTS Description General Location Specific Location 3.3.6.1 LA.1 3/4.3.2 Trip setpoints for associated instrumentation. TRM Appendix B: TRM Table 3.3.6.1-1 3.3.6.1 LA.2 4.3.2.2 Details relating to the method for performing LOGIC SYSTEM FUNCTIONAL TEST. Bases B 3.3.6.1: SR 3.3.6.1.7 3.3.6.1 LA.3

Note to

3.3.2 Actions

Details of the method for performing Required Actions of

which trip system to trip. Bases B 3.3.6.1: Action A.1 3.3.6.1 LA.4 Table 3.3.2-1 Details relating to system design and operation. Bases B 3.3.6.1: ASA/LCO/APP of all Functions 3.3.6.1 LA.4 Table 3.3.2-1

Note (k) Details relating to system design and operation. Bases B 3.3.6.1: ASA/LCO/APP of Functions 3.e and 4.e 3.3.6.1 LA.5 Table 3.3.2-1

Function 1.e Requirement for bypassing the Condenser Vacuum-Low

Function when <500 psig. UFSAR Section 7.3.1.1.6.20 3.3.6.1 LA.7 Table 3.3.2-2

Note (a) Reactor vessel water levels are referenced to

REFERENCE LEVEL ZERO. Bases B 3.3.6.1: ASA/LCO/APP of Functions 1.a, 2.a, 5.g, and 6.b 3.3.6.1 R.1 3/4.3.2.4.a.5 3/4.3.2.4.b.5 HPCI and RCIC Bus Power Monitoring. TRM TRMS 3.6 3.3.6.1 R.2 3/4.3.2.1.d and 3/4.3.2.1.f Main Steam Line Tunnel and Turbine Bldg Area

Temperature Instrumentation for MSIV isolation function (except for MSIV pit). TRM TRMS 3.11 and Appendix C: TRM

Table 3.11-2 3.3.6.2 LA.1 3/4.3.2 Trip setpoints for associated instrumentation. TRM Appendix B: TRM Table 3.3.6.2-1 3.3.6.2 LA.2 4.3.2.2 Details relating to the method for performing the LOGIC SYSTEM FUNCTIONAL TEST. Bases B 3.3.6.2: SR 3.3.6.2.5 3.3.6.2 LA.3

Note to

3.3.2 Actions

Details of the method for performing Required Actions of

which trip system to trip. Bases B 3.3.6.2: Action A.1 3.3.6.2 LA.4 Table 3.3.2-1 Details relating to system design and operation. Bases B 3.3.6.2: Background TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-8) Revision No. 23

ITS CTS Description General Location Specific Location 3.3.6.2 LA.5 Table 3.3.2-2

Note (a) Reactor vessel water levels are referenced to

REFERENCE LEVEL ZERO. Bases B 3.3.6.2: ASA/LCO/APP of Function 1 3.3.7.1 LA.1 3/4.3.5.5 Trip setpoints for associated instrumentation. TRM Appendix B: TRM Table 3.3.7.1-1 3.3.7.1 R.1 3/4.3.5.5.1 3/4.3.5.5.3 CREV System Chlorine Protection Instrumentation and

Smoke Protection Mode Instrumentation requirements. TRM TRMS 3.12 and Appendix C: TRM

Table 3.12-2 3.3.7.2 LA.1 3.3.8 Details relating to instrumentation OPERABILITY. Bases B 3.3.7.2: LCO 3.3.8.1 LA.1 3/4.3.3 Trip setpoints for associated instrumentation. TRM Appendix B: TRM Table 3.3.8.1-1 3.3.8.1 LA.2 4.3.3.2 Details relating to the methods for performing the LOGIC SYSTEM FUNCTIONAL TEST. Bases B 3.3.8.1: SR 3.3.8.1.4 3.3.8.1 LA.3 Table 3.3.3-1

Table 3.3.3-2 Details relating to system design (i.e number of channels

provided, etc.). Bases B 3.3.8.1: Background 3.3.8.1 LA.4 Table 3.3.3-2 Bases for 120V loss of power instrumentation trip setpoints and Allowable Values. TRM Appendix B: TRM Table 3.3.8.1-1 None 3/4.3.5.1 R.1 Seismic Monitoring Instrumentation Technical Specification. TRM TRMS 3.9 None 3/4.3.5.6 R.1 Chlorine Intrusion Monitors Technical Specification. TRM TRMS 3.5 and Appendix C: TRM

Table 3.5-2 None 3/4.3.5.8 R.1 Radioactive Liquid Effluent Monitoring Instrumentation Technical Specification. ODCM ODCMS 7.3.1 None 3/4.3.5.9 LC.1 Requirements for the Main Condenser Off-Gas Treatment

System Explosive Gas Moni toring System (Function G). ODCM ODCMS 7.3.2 None 3/4.3.5.9 R.1 Radioactive Gaseous Effluent Monitoring Instrumentation Technical Specification. ODCM ODCMS 7.3.2 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-9) Revision No. 27

ITS CTS Description General Location Specific Location 3.4.2 LA.1 4.4.1.2.2 Requirements that each jet pump be operable prior to entering OPERATIONAL CONDITION 2 and at least once

per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter with THERMAL POWER less

than or equal to 25% of RTP. UFSAR Deleted in Section 3.9.5.4 per LDCR 04FSAR-038. 3.4.3 LA.1

footnote to

3.4.2 Details

relating to lift setting pressures of the safety/relief valves. Bases B 3.4.3: SR 3.4.3.1 3.4.4 LA.1 4.4.3.2 Details of the methods for performing the Reactor Coolant System leakage surveillance. Bases B 3.4.4: SR 3.4.4.1 3.4.6 LA.1 Table 4.4.5-1 Item 5 Requirements for isotopic analysis for xenon and krypton. UFSAR Section 11.1.2 3.4.9 LA.1 3.4.6.1.c Limitations on the maximum RCS temperature change in any one hour period during inservice leak and hydrostatic

testing operations above the heatup and cooldown limit curves. Bases B 3.4.9: Actions C.1 and C.2 3.4.9 LA.2 4.4.6.1.3 Requirements for reactor material irradiation surveillance specimen location, removal and examination. UFSAR Section 5.3.1.6 3.4.9 LA.2 Table 4.4.6.1.3-1 Requirements for reactor material irradiation surveillance

specimen location, removal and examination. UFSAR Table 5-8 3.4.9 LA.3 3.4.1.3.c and 3.4.1.3 Action Operational limits during single recirculation loop

operation. UFSAR Section 5.4.1.2.2 3.4.9 LA.4 3.4.6.1 Action Details of method for determining RCS is acceptable for continued operation. Bases B 3.4.9: Actions A.1 and A.2; C.1 and C.2 3.4.9 LA.5 3.4.1.3.a Details of method for performing the recirculation pump startup temperature differential verification (specific RCS

location to monitor temperature). Bases B 3.4.9: SR 3.4.9.4 and SR 3.4.9.5 None 3/4.4.4 R.1 Reactor Coolant System Chemistry Technical Specification. TRM TRMS 3.13 None 3/4.4.8 R.1 Reactor Coolant System Structural Integrity Technical Specification. TRM TRMS 3.14 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-10) Revision No. 23

ITS CTS Description General Location Specific Location 3.5.1 LA.1 3.5.1, 3.5.3.1 and 3.5.3.2 Details relating to system OPERABILITY. Bases B 3.5.1: Background 3.5.1 LA.2 4.5.1.c.1, 4.5.3.1.d,

and 4.5.3.2.c Details of methods for performing Surveillances. Bases B 3.5.1: SR 3.5.1.9 3.5.1 LA.2 4.5.2.a Details of methods for performing Surveillances. Bases B 3.5.1: SR 3.5.1.10 3.5.1 LA.2 4.5.2.b Details of methods for performing Surveillances. Bases B 3.5.1: SR 3.5.1.11 3.5.1 LA.2 4.5.3.1.c.1 and 4.5.3.2.d Details of methods for performing Surveillances. Bases B 3.5.1: SR 3.5.1.6, SR 3.5.1.7, and

SR 3.5.1.8 3.5.1 LA.3 4.5.1.c.3 Verification of automatic transfer of HPCI suction valves. Bases B 3.5.1: SR 3.5.1.9 3.5.1 LA.4 4.5.1.c.2 Lower value of the HPCI turbine steam pressure range. Bases B 3.5.1: SR 3.5.1.6, SR 3.5.1.7, and

SR 3.5.1.8 3.5.1 LC.1 4.5.3.1.c.2 Core Spray Header Delta Pressure Alarm Instrumentation Surveillance Requirements. UFSAR Section 7.3.3.1.3.7 3.5.2 LA.1 3.5.3.1, 3.5.3.2, and

3.5.4 Details

relating to system OPERABILITY. Bases B 3.5.2: LCO 3.5.2 LA.2 4.5.3.1.c.1, 4.5.3.1.d.

4.5.3.2.b, and

4.5.3.2.c Details relating to methods for performing surveillances. Bases B 3.5.2: SR 3.5.2.3, SR 3.5.2.5, SR 3.5.2.6, and SR 3.5.2.7 3.5.3 LA.1 3.7.4 Details relating to system OPERABILITY. Bases B 3.5.3: Background 3.5.3 LA.2 4.7.4.a.1 Details relating to methods for performing surveillances. Bases B 3.5.3: SR 3.5.3.1 3.5.3 LA.2 4.7.4.c.1 (including

Note +) Details relating to methods for performing surveillances. Bases B 3.5.3: SR 3.5.3.5 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-11) Revision No. 23

ITS CTS Description General Location Specific Location 3.5.3 LA.2 4.7.4.b and 4.7.4.c.2 Details relating to methods for performing surveillances. Bases B 3.5.3: SR 3.5.3.3 and SR 3.5.3.4 3.5.3 LA.3 4.7.4.c.3 Verification of automatic transfer of the RCIC pump suction. Bases B 3.5.3: SR 3.5.3.5 3.6.1.1 LA.1 1.0 Details of Primary Containment Integrity definition. Bases B 3.6.1.1: Background 3.6.1.2 LA.1 3.6.1.3.a Details comprising OPERABILITY of the air lock. Bases B 3.6.1.2: LCO 3.6.1.3 LA.1 4.6.3.4 Details relating to methods for performing surveillances. Bases B 3.6.1.3: SR 3.6.1.3.7 3.6.1.3 LA.2 4.6.6.2.b.2 Details of the methods for performing surveillances. Bases B 3.6.1.3: SR 3.6.1.3.6 3.6.1.4 LA.1 4.6.1.6 Details of the methods for performing the drywell average air temperature surveillance. Bases B 3.6.1.4: SR 3.6.1.4.1 3.6.1.5 LA.1 3.6.4.2.b Details relating to the OPERABILITY of the Nitrogen Backup System. Bases B 3.6.1.5: Background 3.6.1.5 LA.2 4.6.4.2.1.a.1

and 4.6.4.2.1.a.2 Details of the method for performing surveillances. Bases B 3.6.1.5: SR 3.6.1.5.3 3.6.1.5 LA.2 4.6.4.2.1.b.1

and 4.6.4.2.1.b.2 Details of the method for performing surveillances. Bases B 3.6.1.5: SR 3.6.1.5.4 3.6.1.5 LA.2 4.6.4.2.2.c Details of the method for performing surveillances. Bases B 3.6.1.5: SR 3.6.1.5.6 3.6.1.5 LA.3 4.6.4.2.1.b.3 Details of visual inspection of reactor building-to-suppression chamber vacuum breakers. UFSAR Section 6.2.1.6.2 3.6.1.6 LA.2 4.6.4.1.b Details of the methods for performing surveillances. Bases B 3.6.1.6: SR 3.6.1.6.2 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-12) Revision No. 23

ITS CTS Description General Location Specific Location 3.6.1.6 LA.2 4.6.4.1.c Details of the methods for performing surveillances. Bases B 3.6.1.6: SR 3.6.1.6.1 3.6.2.3 LA.1 3.6.2.2 Details relating to system OPERABILITY. Bases B 3.6.2.3: Background and LCO 3.6.3.2 LA.1 3.6.6.2 Details relating to system OPERABILITY. Bases B 3.6.3.2: LCO 3.6.3.2 LA.2 4.6.6.2.b.1 Details of the methods for performing surveillances. Bases B 3.6.3.2: SR 3.6.3.2.3 3.6.4.1 LA.1 1.0 Details of Secondary Containment Integrity definition. Bases B 3.6.4.1: LCO B 3.6.4.2: LCO; Actions

A.1 and A.2; Action B.1

B 3.6.4.3: LCO 3.6.4.2 LA.1 4.6.5.1.a and

4.6.5.2.a Cycling of each automatic Secondary Containment

Isolation Damper. UFSAR Section 6.2.3.4 3.6.4.2 LA.2 4.6.5.2.c.1 Details of the performance of isolation time verification. Bases B 3.6.4.2: SR 3.6.4.2.1 3.6.4.3 LA.1 3.6.6.1 Details relating to system design. Bases B 3.6.4.3: Background 3.6.4.3 LA.2 4.6.6.1.a Details of the methods for performing standby gas treatment subsystem operating surveillance. Bases B 3.6.4.3: SR 3.6.4.3.1 3.6.4.3 LA.3 4.6.6.1.a Details of performance of standby gas treatment subsystem surveillance with heaters "on automatic

control." Bases B 3.6.4.3: SR 3.6.4.3.1 3.7.1 LA.1 3.7.1.1 Details relating to system OPERABILITY. Bases B 3.7.1: LCO 3.7.1 LA.2 4.7.1.1.b Requirements for testing RHRSW pump flow. UFSAR Section 9.2.1.4 3.7.2 LA.1 3.7.1.2 Details relating to system OPERABILITY. Bases B 3.7.2: LCO TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-13) Revision No. 23

ITS CTS Description General Location Specific Location 3.7.2 LA.2 3.7.1.2 Requirements and Actions relating to system OPERABILITY in non-operating MODES (i.e., MODES 4

and 5). Bases and TRM B 3.4.8: LCO;

B 3.9.7: LCO;

B 3.9.8: LCO;

TRMS 3.16 3.7.3 LA.1 3.7.2 Details relating to system OPERABILITY. Bases B 3.7.3: LCO 3.7.3 LA.2 4.7.2.a Details of the methods for performing surveillances. Bases B 3.7.3: SR 3.7.3.1 3.7.3 LA.2 4.7.2.d.2 Details of the methods for performing surveillances. Bases B 3.7.3: SR 3.7.3.4 3.7.3 R.1 3/4.7.2 CREV smoke protection mode requirements.

TRM TRMS 3.18 3.7.3 R.1 3/4.7.2 CREV chlorine protection mode requirements.

TRM TRMS 3.19 3.7.5 LA.1 3.11.2.7 and 4.11.2.7.2 Details defining the radioactivity involved, methods for

performing the surveillance, and methods for determining

when an increase has occurred. Bases B 3.7.5: SR 3.7.5.1 3.7.5 LA.2 4.11.2.7.1 Requirements to monitor the radioactivity rate of noble gases at the main condenser. ODCM ODCMS Table 7.3.2-1, Function 6 3.7.7 LA.1 3.9.9 Action Discussion of crane operation with loads. UFSAR Sections 9.1.4.1 and 9.1.4.2.3.2 3.7.7 LA.2 3.9.9 Action Details of the method for performing action to place equipment in a safe condition. Bases B 3.7.7: Action A.1 None 3/4.7.3 R.1 Flood Protection Technical Specification.

TRM TRMS 3.10 and TRMS 3.20 None 3/4.7.5 LA.1 Snubber Technical Specification.

TRM TRMS 3.21 None 3/4.7.6 R.1 Sealed Source Contamination Technical Specification. TRM TRMS 3.22 3.8.1 LA.1 4.8.1.1.2.d.1 Requirements to inspect DGs in accordance with procedures prepared in accordance with manufacturer's

recommendations. UFSAR Section 8.3.1.1.6.6 3.8.1 LA.2 4.8.1.1.2.a.4 Note

Details associated with manually starting the DG for

surveillances. Bases B 3.8.1: SR 3.8.1.2 and SR 3.8.1.7 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-14) Revision No. 25

ITS CTS Description General Location Specific Location 3.8.1 LA.3 4.8.1.1.2.d.6 Specific load value for the auto-connected loads. UFSAR Section 8.3.1.1.6.6 and Table 8-7 3.8.1 LA.4 3.8.1.1.a and 3.8.1.1.b Details relating to system design. Bases B 3.8.1: Background 3.8.4 LA.1 3.8.2.3.a and 3.8.2.3.b Details relating to system OPERABILITY. Bases B 3.8.4: Background and LCO 3.8.4 LA.3 4.8.2.3.2.d.1 Details of the DC loads and the licensed service duration for battery service test. UFSAR Section 8.3.2.1.4 3.8.4 LA.4 4.8.2.3.2.d.2 Details requiring battery charger to be demonstrated capable of recharging its associated battery after

completion of the battery service test. UFSAR Section 8.3.2.1.4 3.8.7 LA.1 3.8.2.1, 4.8.2.1,

3.8.2.3, 4.8.2.3.1, 3.8.2.4.1, and

4.8.2.4.1.1 Details relating to system design and OPERABILITY. Bases B 3.8.7: Background; LCO; Table B 3.8.7-1 3.8.7 LA.1 3.8.2.4.1

Note Details relating to system design and OPERABILITY. Bases B 3.8.7: Actions B.1, B.2, B.3, and B.4 3.8.7 LA.2 3.8.2.4.1 Actions b.1

and b.3 Details of the methods for performing verification of power

availability. Bases B 3.8.7: Actions B.1, B.2, B.3, and B.4 3.8.8 LA.1 3.8.2.2 and 3.8.2.4.2 Details relating to AC and DC electrical power distribution

system design and OPERABILITY. Bases B 3.8.7: Table B 3.8.7-1 3.9.5 LA.1 4.1.3.5.a Details of the method of verifying OPERABILITY of the control rod accumulators. Bases B 3.9.5: SR 3.9.5.1 and SR 3.9.5.2 3.9.5 LC.1 4.1.3.5.a and 4.1.3.5.b Control rod scram accumulators, leak detectors, and

pressure detectors testing. UFSAR Section 3.9.4.1.2.4 None 3/4.9.4 LA.1 Decay Time Technical Specification.

TRM TRMS 3.23 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-15) Revision No. 23

ITS CTS Description General Location Specific Location None 3/4.9.5 R.1 Communications Technical Specification.

TRM TRMS 3.24 None 3/4.9.6 R.1 Crane and Hoist OPERABILITY Technical Specification. TRM TRMS 3.25 None 3/4.9.7 R.1 Crane Travel - Spent Fuel Storage Pool Technical Specification. TRM TRMS 3.26 3.10.2 LA.1 Table 1.2 Note # Details of the method used to verify control rods remain

fully inserted (by verification using a second licensed

operator or other technically qualified member of the unit

technical staff.). Bases B 3.10.2: SR 3.10.2.1 and SR 3.10.2.2 3.10.4 LA.1 3/4.9.10.1.d Details of the recommended procedures for disarming control rods. Bases B 3.10.4: SR 3.10.4.1, SR 3.10.4.2, SR 3.10.4.3, and SR 3.10.4.4 3.10.5 LA.1 3/4.9.10.1.d Details of the recommended procedures for disarming control rods. Bases B 3.10.5: SR 3.10.5.1, SR 3.10.5.2, SR 3.10.5.3, SR 3.10.5.4, and

SR 3.10.5.5 None 3/4.10.5 LA.1 The requirements for OPERABILITY of the Plant Service Water system in non-operating MODES (i.e., MODES 4

and 5). Bases and TRM B 3.4.8: LCO;

B 3.9.7: LCO;

B 3.9.8: LCO;

TRMS 3.17 None 3/4.11.1.1 R.1 Liquid Effluents Concentration Technical Specification. ODCM ODCMS 7.3.3 None 3/4.11.1.2 R.1 Dose Liquid Effluents Technical Specification. ODCM ODCMS 7.3.4 None 3/4.11.1.3 R.1 Liquid Radwaste Treatment System Technical

Specification. ODCM ODCMS 7.3.5 None 3/4.11.2.1 R.1 Gaseous Effluents Technical Specification. ODCM ODCMS 7.3.7 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-16) Revision No. 25

ITS CTS Description General Location Specific Location None 3/4.11.2.2 R.1 Dose Noble Gases Technical Specification. ODCM ODCMS 7.3.8 None 3/4.11.2.3 R.1 Dose Iodine-131, Iodine-133, Tritium, and Radionuclides

in Particulate Form Technical Specification. ODCM ODCMS 7.3.9 None 3/4.11.2.4 R.1 Gaseous Radwaste Treatment System Technical

Specification. ODCM ODCMS 7.3.10 None 3/4.11.2.5 R.1 Ventilation Exhaust Treatment System Technical

Specification. ODCM ODCMS 7.3.11 None 3/4.11.2.8 R.1 Drywell Venting or Purging Technical Specification. ODCM ODCMS 7.3.13 None 3/4.11.3 R.1 Solid Radioactive Waste Technical Specification. UFSAR Section 12.5.3.8 None 3/4.11.4 R.1 Total Dose (40 CFR PART 190) Technical Specification. ODCM ODCMS 7.3.14 None 3/4.12.1 R.1 Radiological Environmental Monitoring Program Technical Specification. ODCM ODCMS 7.3.15 None 3/4.12.2 R.1 Land Use Census Technical Specification. ODCM ODCMS 7.3.16 None 3/4.12.3 R.1 Interlaboratory Comparison Program Technical Specification. ODCM ODCMS 7.3.17 4.0 LA.1 5.1.2 and

5.1.3 Details

of the low population zone and site boundary. UFSAR Section 2.1.1.3 4.0 LA.2 5.2 Configurations, design temperatures and pressures, and volumes of the Primary Containment. UFSAR Section 6.2.1 and Table 6-3 4.0 LA.2 5.4 Configurations, design temperatures and pressures, and volumes of the Reactor Coolant System. UFSAR Section 5.3.3.7 and Table 6-5 4.0 LA.3 5.3.1 Details of specific fuel types that can be inserted in the reactor core. UFSAR Section 4.2.2 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-17) Revision No. 25

ITS CTS Description General Location Specific Location 4.0 LA.5 5.5 Location of meteorological tower. UFSAR Section 2.2.1.3 and Figure 2-2 4.0 LA.6 5.1.6.3 Details of uncertainties included in k eff calculations associated with the fuel racks. UFSAR Section 9.1.2.3.2 4.0 LA.7 5.6.1.1 Corrected temperature for new fuel k-infinity values. UFSAR Section 9.1.1.3 4.0 LA.7 5.6.1.2.a and 5.6.1.2.b Corrected temperature for irradiated fuel k-infinity values. UFSAR Section 9.1.2.3.2 5.1 LA.1 6.1.1 and 6.5.2.7 Compliance details relating to plant specific position titles. UFSAR Section 13.1.2.2 5.2 LA.1 Table 6.2.2-1 Details of the minimum shift crew requirements. UFSAR Table 13-1 5.2 LA.2 6.2.2.d Details of operator license requirements. UFSAR Section 13.1.2.2 5.2 LA.3 6.2.2.g Details that require Core Alterations to be supervised by either a licensed Senior Reactor Operator or Senior

Reactor Operator Limited to Fuel Handling. UFSAR Section 13.1.2.2 5.2 LA.4 6.2.1.b, 6.2.1.c, 6.2.2.e, and

6.2.4.1 Compliance details relating to plant specific position titles. UFSAR Section 13.1.2.2 5.3 LA.1 6.3.1 Compliance details relating to plant specific position titles. UFSAR Section 13.1.2.2 5.4 LA.1 6.8.1.i Guidance of procedures to be used covering Quality Assurance for effluent and environmental monitoring.

QA Program

Description UFSAR Chapter 17, Appendix A, Section 1.1.1 5.4 LA.2 6.8.2 Details of procedure reviews and approvals for temporary changes. QA Program

Description UFSAR Chapter 17, Appendix A, Section 1.1.2 5.4 LA.3 6.8.1.h Requirements for Process Control Program implementation procedures.

QA Program

Description UFSAR Section 17.3.1.7 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-18) Revision No. 25

ITS CTS Description General Location Specific Location 5.5 LA.1 6.8.3.2 Details of In-Plant Radiation Monitoring Program. UFSAR Section 12.5.3.3 5.5 LA.2 5.7 Details of the components governed by Component Cyclic or Transient Limit Program. UFSAR Table 5-11 5.5 LA.3 4.0.5 Details of the Inservice Inspection Program associated with Generic Letter 88-01. UFSAR Section 5.2.3.4.2.4 5.5 LA.3 4.0.5 Details of the Inservice Inspection Program for Class 1 components.. UFSAR Section 5.2.4 5.5 LA.3 4.0.5 Details of the Inservice Inspection Program for Class 2 and 3 components. UFSAR Section 6.6 5.5 LA.4 4.0.5 Details of the Inservice Testing Program. UFSAR Section 3.9.6 5.5 LA.5 4.6.6.1.b.2, 4.6.6.1.c, 4.7.2.b.2,and

4.7.2.c Details of the methods for implementing testing of the

SGTS and CREV filter system laboratory analysis. TRM Section 5.5.7 5.5 LA.6 3/4.11.1.4 Details of the methods for implementing requirements for Liquid Holdup Tanks. ODCM ODCMS 7.3.6 5.5 LA.6 3/4.11.2.6 Details of the methods for implementing requirements for Explosive Gas Mixtures. ODCM ODCMS 7.3.12 5.5 LA.7 4.8.1.1.2.c References to ASTM Standards and acceptance criteria for diesel fuel oil. Bases B 3.8.3: SR 3.8.3.2 5.6 LA.1 6.9.1.1, 6.9.1.2, and

6.9.1.3 Details associated with Startup Report. UFSAR Section 13.4.2.1 5.6 LA.2 6.9.3.1.a Details associated with individual specifications addressing the Core Operating Limits Report. Bases B 3.2.1: ASA and LCO TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-19) Revision No. 23

ITS CTS Description General Location Specific Location 5.6 LA.2 6.9.3.1.b Details associated with individual specifications addressing the Core Operating Limits Report. Bases B 3.2.2: ASA and LCO 5.7 LA.1 6.12.2 Compliance details relating to plant specific titles. UFSAR Section 13.1.2.2 None 6.4 LA.1 Details contained on training and replacement training for the unit staff. UFSAR Section 13.2.2 None 6.5 LA.1 Details of procedures, modification, or Operating License/Technical Specification reviews and approvals for

changes. QA Program

Description UFSAR Chapter 17, Appendix A, Sections

1.1.3, 1.1.4, 1.2, 1.3, 1.4, and 1.5 None 6.5 LA.2 Details of review and audit activities.

QA Program Description UFSAR Chapter 17, Appendix A, Sections 1.6, 1.7, 1.8, and 1.9 None 6.6 LA.2 Details of reportable events reviews.

QA Program Description UFSAR Chapter 17, Appendix A, Section 2.0 None 6.10 LA.1 Details of record retention.

QA Program Description UFSAR Chapter 17, Appendix A, Section 3.0 None 6.11 LA.1 Details of the radiation protection program. UFSAR Section 12.5.3 None 6.14 LA.1 Details of the process control program. UFSAR Section 12.5.3.8

Brunswick Unit 2 Revision No. 23 APPENDIX B TECHNICAL SPECIFICATION (TS) INSTRUMENT LIST

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-1 Revision No. 23 APPENDIX B TECHNICAL SPECIFICATION (TS) INSTRUMENT LIST

PURPOSE This appendix provides instrument tables to aid in complying with the requirements of the

instrument TS (TS Section 3.3, "INSTRUMENTATION"), TS 3.4.4, "RCS Operational

LEAKAGE," and TS 3.4.5, "RCS Leakage Detection Instrumentation." This appendix does not

define OPERABILITY for individual channels. For OPERABILITY of instrument channels, refer

to the Bases of the associated TS, the Updated Final Safety Analysis Report, or the associated Design Basis Document.

Each table in the TS Instrument List corresponds to the associated instrumentation TS. For

example; TRM Table 3.3.1.1-1, "Reactor Protecti on System Instrumentation" corresponds to TS 3.3.1.1, "Reactor Protection System (RPS) Instrumentation." Each TS Instrument List Table

includes the applicable instrument number(s) associated with each TS instrument function and

the nominal trip setpoint associated with each TS instrument function, where applicable.

Each TS instrument function with a nominal trip setpoint value specified is considered to be

properly adjusted when the "as left" value of the instrumentation is in compliance with the "as-

left" tolerance specified in the surveillance test. Additionally, the "as-found" value must be in

compliance with the Allowable Value specified in the TS. A detailed description of the

methodology used to calculate each instrument nominal trip setpoint, including explicit

uncertainties, is provided in the associated setpoint calculation.

For Nominal Trip Setpoints that are specified in units of inches, the zero reference value is

defined in the associated TS Bases except where noted.

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-2 Revision No. 44 TRM Table 3.3.1.1-1 (page 1 of 2) Reactor Protection System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

NOMINAL TRIP SETPOINT

1. Intermediate Range Monitors

a. Neutron Flux-High

C51-IRM-A, B, C, D, E, F, G, H C72-K14A, B, C, D, E, F, G, H

117/125 divisions of full

scale

b. Inop C51-IRM-A, B, C, D, E, F, G, H C72-K14A, B, C, D, E, F, G, H

NA

2. Average Power Range Monitors

a. Neutron Flux-High (Setdown)

C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11

15% RTP

b. Simulated Thermal Power-High

C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11

0.55W + 61.1% RTP (a) and 115.8% RTP c. Neutron Flux-High

C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11

117.4% RTP

d. Inop C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11

NA

e. 2-Out-of-4 Voter

C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11

NA

f. OPRM Upscale C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11 NA(c) 3. Reactor Vessel Steam Dome Pressure-High

B21-PT-N023A, B, C, D B21-PTM-N023A-1, B-1, C-1, D-1 C72-K14A, B, C, D, E, F, G, H

1060 psig

4. Reactor Vessel Water Level-Low Level 1

B21-LT-N017A-1, B-1, C-1, D-1 B21-LTM-N017A-1, B-1, C-1, D-1 C72-K14A, B, C, D, E, F, G, H

166 inches

(continued)

(a) [0.55 (W - W) + 61.1% RTP] when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating." The setpoint value of W is defined in plant procedures.

(b) Nominal Trip Setpoint is referenced from valve full open position.

(c) See COLR for OPRM period based detection algorithm (PBDA) setpoint limits.

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-3 Revision No. 23 TRM Table 3.3.1.1-1 (page 2 of 2) Reactor Protection System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

NOMINAL TRIP SETPOINT 5. Main Steam Isolation Valve-Closure

B21-F022A, B, C, D B21-F028A, B, C, D C72-K14A, B, C, D, E, F, G, H

1.25 inches of stem travel (b) 6. Drywell Pressure-High

C72-PT-N002A, B, C, D C72-PTM-N002A-1, B-1, C-1, D-1 C72-K14A, B, C, D, E, F, G, H

1.7 psig

7. Scram Discharge Volume Water Level-High

C12-LSH-N013A, B, C, D C12-LSH-4516A, B, C, D C72-K14A, B, C, D, E, F, G, H

104 gallons

8. Turbine Stop Valve-Closure

MS-ZS-SVRP-1, 2, 3, 4 C72-K14A, B, C, D, E, F, G, H

0.625 inches of stem travel (b) 9. Turbine Control Valve Fast Closure, Control Oil Pressure-Low

EHC-PSL-1756, 1757, 1758, 1759 C72-K14A, B, C, D, E, F, G, H

600 psig

10. Reactor Mode Switch-Shutdown Position

C72-CS-S1

NA

11. Manual Scram

C72-PB-S3A, B

NA

(b) Nominal Trip Setpoint is referenced from valve full open position.

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-4 Revision No. 44 TRM Table 3.3.1.2-1 (page 1 of 1) Source Range Monitor Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

1. Source Range Monitor

C51-SRM-A, B, C, D

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-5 Revision No. 23 TRM Table 3.3.2.1-1 (page 1 of 1) Control Rod Block Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

NOMINAL TRIP SETPOINT

1. Rod Block Monitor

a. Low Power Range-Upscale

C51-RBMA-AR21 C51-RBMB-AR22

(a)

b. Intermediate Power Range-Upscale

C51-RBMA-AR21 C51-RBMB-AR22

(a)

c. High Power Range-Upscale

C51-RBMA-AR21 C51-RBMB-AR22

(a)

d. Inop C51-RBMA-AR21 C51-RBMB-AR22

NA

2. Rod Worth Minimizer

2-C12-CNV-5516 19.1% rated steam flow

3. Reactor Mode Switch-Shutdown Position

C72-CS-S1 NA (a) Nominal Trip Setpoints specified in the COLR.

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-6 Revision No. 23 TRM Table 3.3.2.2-1 (page 1 of 1) Feedwater and Main Turbine High Water Level Trip Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

NOMINAL TRIP SETPOINT

1. Feedwater Pumps

a. Reactor Vessel Water Level-High

C32-LT-N0O4A, B, C C32-LY-K602A - A1, B1, A4 C32-LY-K602C - A1, B1, A4 C32-LY-K602E - A1, B1, A4 C32-LC-R602A, B

206 inches

2. Main Turbine

a. Reactor Vessel Water Level-High

C32-LT-N0O4A, B, C C32-LY-K602A - A1, B1, A4 C32-LY-K602C - A1, B1, A4 C32-LY-K602E - A1, B1, A4 C32-LC-R602A, B

206 inches

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-7 Revision No. 39 TRM Table 3.3.3.1-1 (page 1 of 1) Post Accident Monitoring Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

1. Reactor Vessel Pressure

2. Reactor Vessel Water Level

a. -150 inches to +150 inches

b. 0 inches to +210 inches

c. +150 inches to +550 inches

3. Suppression Chamber Water Level

4. Suppression Chamber Water Temperature

5. Suppression Chamber Pressure

6. Drywell Pressure

7. Drywell Temperature

8. PCIV Position

9. (Not Used.)

10. Drywell Area Radiation

B21-PI-R605A, B

B21-LI-R610, B21-LR-R615

B21-LI-R604A, B

B21-LI-R605A, B

CAC-LI-2601-1, CAC-LR-2602

CAC-TR-4426-1A CAC-TR-4426-2A CAC-TY-4426-1, 2

CAC-PI-1257-2A, B

CAC-PI-4176, CAC-PR-1257-1

CAC-TR-4426-1A, B CAC-TR-4426-2A, B CAC-TY-4426-1, 2

See TRM Table 3.3.3.1-2, "Primary Containment Isolation Valve Position Indication."

D22-RI-4195 OR D22-RI-4196 OR D22-RR-4195 AND D22-RI-4197 OR D22-RI-4198 OR D22-RR-4197

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-8 Revision No. 23 TRM Table 3.3.3.1-2 (page 1 of 5) Primary Containment Isolation Valve Position Indication VALVE NUMBER VALVE DESCRIPTION LOCATION OF DISPLAY 2-B21-F016 MAIN STEAM LINE DRAIN INBOARD ISOLATION H12-P601 2-B21-F019 MAIN STEAM LINE DRAIN OUTBOARD ISOLATION H12-P601 2-B21-F022A INBOARD MSIV A H12-P601 2-B21-F022B INBOARD MSIV B H12-P601 2-B21-F022C INBOARD MSIV C H12-P601 2-B21-F022D INBOARD MSIV D H12-P601 2-B21-F028A OUTBOARD MSIV A H12-P601 2-B21-F028B OUTBOARD MSIV B H12-P601 2-B21-F028C OUTBOARD MSIV C H12-P601 2-B21-F028D OUTBOARD MSIV D H12-P601 2-B21-F032A FEEDWATER SUPPLY LINE A ISOLATION H12-P603 2-B21-F032B FEEDWATER SUPPLY LINE B ISOLATION H12-P603 2-B32-FO19 SAMPLE LINE INBOARD ISOLATION H12-P603 2-B32-F020 SAMPLE LINE OUTBOARD ISOLATION H12-P603 2-B32-V22 RECIRC PUMP 2A SEAL INJECTION H12-P603 2-B32-V30 RECIRC PUMP 2B SEAL INJECTION H12-P603 2-CAC-SV-1200B CAC-AT-1261 INBOARD SAMPLE INLET XU-2 2-CAC-SV-1205E CAC-AT-4409 PRIMARY CONTAINMENT INBOARD SAMPLE XU-2 2-CAC-SV-1209A CAC-AT-4409 PRIMARY CONTAINMENT INBOARD SAMPLE XU-2 2-CAC-SV-1209B CAC-AT-4409 PRIMARY CONTAINMENT INBOARD SAMPLE XU-2 2-CAC-SV-1211E CAC-AT-1262 INBOARD SAMPLE RETURN XU-2 2-CAC-SV-1211F CAC-AT-1262 INBOARD SAMPLE INLET XU-2 2-CAC-SV-1213A CAC-AT-4409 TORUS INBOARD SAMPLE XU-2 2-CAC-SV-1215E CAC-AT-4409 INBOARD SAMPLE RETURN XU-2 2-CAC-SV-1218A CAC-AT-4410 TORUS INBOARD SAMPLE XU-2 2-CAC-SV-1225B COMMON INBOARD SAMPLE RETURN XU-2 2-CAC-SV-1227A CAC-AT-4410 PRIMARY CONTAINMENT INBOARD SAMPLE XU-2 2-CAC-SV-1227B CAC-AT-4410 PRIMARY CONTAINMENT INBOARD SAMPLE XU-2 2-CAC-SV-1227C

CAC-AT-1260 INBOARD SAMPLE INLET XU-2 (continued)

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-9 Revision No. 23 TRM Table 3.3.3.1-2 (page 2 of 5) Primary Containment Isolation Valve Position Indication VALVE NUMBER VALVE DESCRIPTION LOCATION OF DISPLAY 2-CAC-SV-1227E CAC-AT-4410 PRIMARY CONTAINMENT INBOARD SAMPLE XU-2 2-CAC-SV-1231B CAC-AT-4410 INBOARD SAMPLE RETURN XU-2 2-CAC-SV-1260 CAC-AT-1260 OUTBOARD SAMPLE INLET XU-2 2-CAC-SV-1261 CAC-AT-1261 OUTBOARD SAMPLE INLET XU-2 2-CAC-SV-1262 CAC-AT-1262 OUTBOARD SAMPLE INLET XU-2 2-CAC-SV-3439 CAC-AT-1262 OUTBOARD SAMPLE RETURN XU-2 2-CAC-SV-3440 COMMON OUTBOARD SAMPLE RETURN XU-2 2-CAC-SV-4409-1 CAC-AT-4409 TORUS OUTBOARD SAMPLE XU-51 2-CAC-SV-4409-2 CAC-AT-4409 PRIMARY CONTAINMENT OUTBOARD SAMPLE XU-51 2-CAC-SV-4409-3 CAC-AT-4409 PRIMARY CONTAINMENT OUTBOARD SAMPLE XU-51 2-CAC-SV-4409-4 CAC-AT-4409 PRIMARY CONTAINMENT OUTBOARD SAMPLE XU-51 2-CAC-SV-4410-1 CAC-AT-4410 TORUS OUTBOARD SAMPLE XU-51 2-CAC-SV-4410-2 CAC-AT-4410 PRIMARY CONTAINMENT OUTBOARD SAMPLE XU-51 2-CAC-SV-4410-3 CAC-AT-4410 PRIMARY CONTAINMENT OUTBOARD SAMPLE XU-51 2-CAC-SV-4410-4 CAC-AT-4410 PRIMARY CONTAINMENT OUTBOARD SAMPLE XU-51

2-CAC-SV-4540 CAC-AT-4409 OUTBOARD SAMPLE RETURN XU-51 2-CAC-SV-4541 CAC-AT-4410 OUTBOARD SAMPLE RETURN XU-51 2-CAC-V4 INBOARD PRIMARY CONTAINMENT N2 INERTING INLET XU-51 2-CAC-V5 SUPPRESSION POOL N2 INLET XU-51 2-CAC-V6 DRYWELL N2 INLET XU-51 2-CAC-V7 INBOARD SUPPRESSION POOL PURGE EXHAUST XU-51 2-CAC-V8 OUTBOARD SUPPRESSION POOL PURGE EXHAUST XU-51 2-CAC-V9 INBOARD DRYWELL PURGE EXHAUST XU-51 2-CAC-V10 OUTBOARD DRYWELL PURGE EXHAUST XU-51 2-CAC-V15 PRIMARY CONTAINMENT PURGE AIR INLET XU-51 2-CAC-V16 REACTOR BUILDING TO SU PPRESSION CHAMBER VACUUM BREAKER XU-51 2-CAC-V17 REACTOR BUILDING TO SU PPRESSION CHAMBER VACUUM BREAKER XU-51 2-CAC-V22 SUPPRESSION POOL 2" EXHAUST XU-51 2-CAC-V23 DRYWELL 2" EXHAUST XU-51 2-CAC-V49 DRYWELL HEAD INBOARD PURGE EXHAUST XU-51 2-CAC-V50 DRYWELL HEAD OUTBOARD PURGE EXHAUST XU-51 2-CAC-V55 DRYWELL CAD N2 INJECTION SOLENOID XU-51 2-CAC-V56

DRYWELL CAD N2 INJECTION SOLENOID XU-51 (continued)

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-10 Revision No. 23 TRM Table 3.3.3.1-2 (page 3 of 5) Primary Containment Isolation Valve Position Indication VALVE NUMBER VALVE DESCRIPTION LOCATION OF DISPLAY 2-CAC-V160

SUPPRESSION POOL CAD N2 INJECTION INLET

XU-51 2-CAC-V161 DRYWELL CAD N2 INJECTION INLET XU-51 2-CAC-V162 SUPPRESSION POOL CAD N2 INJECTION INLET XU-51 2-CAC-V163 DRYWELL CAD N2 INJECTION INLET XU-51 2-CAC-V172 SUPPRESSION POOL PURGE EXHAUST SOLENOID XU-51 2-CAC-V216 HARDENED WETWELL VENT OUTBOARD ISOLATION XU-51 2-C51-J004A A TIP BALL VALVE AND SHEAR VALVE ASSEMBLY H12-P607 2-C51-J004B B TIP BALL VALVE AND SHEAR VALVE ASSEMBLY H12-P607 2-C51-J004C C TIP BALL VALVE AND SHEAR VALVE ASSEMBLY H12-P607 2-C51-J004D D TIP BALL VALVE AND SHEAR VALVE ASSEMBLY H12-P607 2-E11-F007A MINIMUM FLOW BYPASS VALVE A TO SUPPRESSION POOL H12-P601 2-E11-F007B MINIMUM FLOW BYPASS VALVE B TO SUPPRESSION POOL H12-P601 2-E11-F008 SHUTDOWN COOLING OUTBOARD SUCTION H12-P601 2-E11-F009 SHUTDOWN COOLING INBOARD SUCTION THROTTLE H12-P601 2-E11-F011A RHR HEAT EXCHANGER 2A DRAIN TO SUPPRESSION POOL H12-P601 2-E11-F011B RHR HEAT EXCHANGER 2B DRAIN TO SUPPRESSION POOL H12-P601 2-E11-F015A LPCI A INBOARD INJECTION H12-P601 2-E11-F015B LPCI B INBOARD INJECTION H12-P601 2-E11-F016A DRYWELL SPRAY A OUTBOARD ISOLATION H12-P601 2-E11-F016B DRYWELL SPRAY B OUTBOARD ISOLATION H12-P601 2-E11-F017A LPCI A OUTBOARD INJECTION H12-P601 2-E11-F017B LPCI B OUTBOARD INJECTION H12-P601 2-E11-F020A RHR PUMP 2A AND 2C TORUS SUCTION H12-P601 2-E11-F020B RHR PUMP 2B AND 2D TORUS SUCTION H12-P601 2-E11-F021A DRYWELL SPRAY A INBOARD ISOLATION H12-P601 2-E11-F021B DRYWELL SPRAY B INBOARD ISOLATION H12-P601 2-E11-F024A SUPPRESSION POOL COOLING A ISOLATION H12-P601 2-E11-F024B SUPPRESSION POOL COOLING B ISOLATION H12-P601 2-E11-F027A SUPPRESSION POOL SPRAY A ISOLATION H12-P601 2-E11-F027B SUPPRESSION POOL SPRAY B ISOLATION H12-P601 2-E11-F028A SUPPRESSION POOL SPRAY A ISOLATION H12-P601 2-E11-F028B SUPPRESSION POOL SPRAY B ISOLATION H12-P601 (continued)

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-11 Revision No. 23 TRM Table 3.3.3.1-2 (page 4 of 5) Primary Containment Isolation Valve Position Indication VALVE NUMBER VALVE DESCRIPTION LOCATION OF DISPLAY 2-E11-F103A

RHR HEAT EXCHANGER 2A OUTBOARD VENT

H12-P601 2-E11-F103B RHR HEAT EXCHANGER 2B OUTBOARD VENT H12-P601 2-E21-F001A SUPPRESSION POOL A SUCTION H12-P601 2-E21-FO01B SUPPRESSION POOL B SUCTION H12-P601 2-E21-FO04A CORE SPRAY PUMP 2A OUTBOARD INJECTION H12-P601 2-E21-FO04B CORE SPRAY PUMP 2B OUTBOARD INJECTION H12-P601 2-E21-FO05A CORE SPRAY PUMP 2A INBOARD INJECTION H12-P601 2-E21-FO05B CORE SPRAY PUMP 2B INBOARD INJECTION H12-P601 2-E21-FO15A CORE SPRAY FULL FLOW TEST BYPASS H12-P601 2-E21-FO15B CORE SPRAY FULL FLOW TEST BYPASS H12-P601 2-E21-FO31A CORE SPRAY MINIMUM FLOW BYPASS H12-P601 2-E21-FO31B CORE SPRAY MINIMUM FLOW BYPASS H12-P601 2-E41-F002 HPCI STEAM SUPPLY INBOARD ISOLATION H12-P601 2-E41-F003 HPCI STEAM SUPPLY OUTBOARD ISOLATION H12-P601 2-E41-F006 HPCI INJECTION H12-P601 2-E41-F012 HPCI MINIMUM FLOW BYPASS TO SUPPRESSION POOL H12-P601 2-E41-F042 HPCI SUPPRESSION POOL SUCTION H12-P601 2-E41-F075 HPCI TURBINE EXHAUST VACUUM BREAKER H12-P601 2-E41-F079 HPCI TURBINE EXHAUST VACUUM BREAKER H12-P601 2-E51-F007 RCIC STEAM SUPPLY INBOARD ISOLATION H12-P601 2-E51-F008

RCIC STEAM SUPPLY OUTBOARD ISOLATION H12-P601 (continued)

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-12 Revision No. 24 TRM Table 3.3.3.1-2 (page 5 of 5) Primary Containment Isolation Valve Position Indication VALVE NUMBER VALVE DESCRIPTION LOCATION OF DISPLAY 2-E51-F013

RCIC INJECTION

H12-P601 2-E51-F019 RCIC MINIMUM FLOW BYPASS TO SUPPRESSION POOL H12-P601 2-E51-F031 RCIC SUPPRESSION POOL SUCTION H12-P601 2-E51-F062 RCIC TURBINE EXHAUST VACUUM BREAKER H12-P601 2-E51-F066 RCIC TURBINE EXHAUST VACUUM BREAKER H12-P601 2-G16-F003 DRYWELL FLOOR DRAIN INBOARD ISOLATION H12-P601 2-G16-F004 DRYWELL FLOOR DRAIN OUTBOARD ISOLATION H12-P601 2-G16-F019 DRYWELL EQUIPMENT DRAIN INBOARD ISOLATION H12-P601 2-G16-F020 DRYWELL EQUIPMENT DRAIN OUTBOARD ISOLATION H12-P601 2-G31-F001 RWCU INLET INBOARD ISOLATION H12-P601 2-G31-F004 RWCU INLET OUTBOARD ISOLATION H12-P601 2-G31-F042 RWCU RETURN TO REACTOR H12-P603 2-RCC-SV-1222B RECIRC PUMP 2A COOLER OUTLET SAMPLE XU-2 2-RCC-SV-1222C RECIRC PUMP 2B COOLER OUTLET SAMPLE XU-2 2-RCC-V28 RBCCW DRYWELL DISCHARGE HEADER ISOLATION XU-2 2-RCC-V52 RBCCW DRYWELL SUPPLY HEADER ISOLATION XU-2 2-RNA-SV-5251 BACKUP NITROGEN SUPPLY TO DRYWELL ISOLATION VALVE - DIVISION II XU-51 2-RNA-SV-5253 BACKUP NITROGEN SUPPLY TO DRYWELL ISOLATION VALVE - DIVISION I XU-51 2-RNA-SV-5261 NON-INTERRUPTIBLE REACTOR INSTRUMENT AIR SOLENOID XU-51 2-RNA-SV-5262 NON-INTERRUPTIBLE REACTOR INSTRUMENT AIR SOLENOID XU-51 2-RXS-SV-4186 LIQUID SAMPLE RETURN INBOARD ISOLATION XU-75 2-RXS-SV-4187 LIQUID SAMPLE RETURN OUTBOARD ISOLATION XU-79 2-RXS-SV-4188 GAS SAMPLE RETURN INBOARD ISOLATION XU-75 2-RXS-SV-4189

GAS SAMPLE RETURN OUTBOARD ISOLATION XU-79 TRM TS Instrument List Appendix B

Brunswick Unit 2 B-13 Revision No. 23 TRM Table 3.3.3.2-1 (page 1 of 1) Remote Shutdown Monitoring Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

1. Reactor Vessel Pressure

2. Reactor Vessel Water Level

3. Suppression Chamber Water Level

4. Suppression Chamber Water Temperature

5. Drywell Pressure

6. Drywell Temperature

7. Residual Heat Removal System Flow

C32-PI-3332, C32-PT-3332

B21-LT-N017D-3, B21-LSH-N017D-3 B21-LI-3331, B21-LI-R604BX, B21-LT-3331, B21-LT-N026B

CAC-LI-3342, CAC-LT-3342

CAC-TR-778-6 or CAC-TR-778-7

CAC-PI-3341, CAC-PT-3341

CAC-TR-778-1 or CAC-TR-778-3 or CAC-TR-778-4

E11-FT-3338, E11-FI-3338, E11-FY-3338

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-14 Revision No. 23 TRM Table 3.3.4.1-1 (page 1 of 1) Anticipated Transient Without Scram Recirculation Pump Trip Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

NOMINAL TRIP SETPOINT

1. Reactor Vessel Water Level-Low Level 2

B21-LT-N024A-2, B-2 B21-LT-N025A-2, B-2 B21-LTM-N024A-2, B-2 B21-LTM-N025A-2, B-2

105 inches

2. Reactor Vessel Steam Dome Pressure-High

B21-PT-N045A, B, C, D B21-PTM-N045A, B, C, D

1137.8 psig

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-15 Revision No. 23 TRM Table 3.3.5.1-1 (page 1 of 2) Emergency Core Cooling System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

NOMINAL TRIP SETPOINT

1. Core Spray System

a. Reactor Vessel Water Level-Low Level 3

B21-LT-N031A, B, C, D B21-LTS-N031A-4, B-4, C-4, D-4

45 inches

b. Drywell Pressure-High

E11-PT-N011A, B, C, D E11-PTS-N011A-2, B-2, C-2, D-2

1.7 psig

c. Reactor Steam Dome Pressure-Low

B21-PT-N021A, B, C, D, B21-PTS-N021A-2, B-2, C-2, D-2

410 psig

d. Core Spray Pump Start-Time Delay Relay

E21-K16A, B STR/2A-1, STR/2A-2 STR/2B-1, STR/2B-2

15 seconds

2. Low Pressure Coolant Injection (LPCI) System

a. Reactor Vessel Water Level-Low Level 3

B21-LT-N031A, B, C, D B21-LTS-N031A-4, B-4, C-4, D-4

45 inches

b. Drywell Pressure-High

E11-PT-N011A, B, C, D E11-PTM-N011A-1, B-1, C-1, D-1

1.7 psig

c. Reactor Steam Dome Pressure-Low

B21-PT-N021A, B, C, D B21-PTS-N021A-2, B-2, C-2, D-2

410 psig

d. Reactor Steam Dome Pressure-Low (Recirculation Pump Discharge Valve Permissive)

B21-PT-N021A, B, C, D B21-PTM-N021A-1, B-1, C-1, D-1

310 psig

e. Reactor Vessel Shroud Level

B21-LT-N036, B21-LT-N037 B21-LTM-N036-1, B21-LTM-N037-1

-47.4 inches

f. RHR Pump Start-Time Delay Relay

STR/2A-1, STR/2A-2, STR/2B-1, STR/2B-2, STR/1A-3, STR/1A-4, STR/1B-3, STR/1B-4

10 seconds

3. High Pressure Coolant Injection (HPCI) System

a. Reactor Vessel Water Level-Low Level 2

B21-LT-N031A, B, C, D B21-LTS-N031A-2, B-2, C-2, D-2

105 inches

b. Drywell Pressure-High

E11-PT-N011A, B, C, D E11-PTS-N011A-2, B-2, C-2, D-2

1.7 psig

(continued)

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-16 Revision No. 23 TRM Table 3.3.5.1-1 (page 2 of 2) Emergency Core Cooling System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

NOMINAL TRIP SETPOINT

3. High Pressure Coolant Injection (HPCI) System (continued)

c. Reactor Vessel Water Level-High

B21-LT-N017 B-2, D-2 B21-LTM-N017 B-2, D-2

206 inches

d. Condensate Storage Tank Level-Low

E41-LS-N0O2, E41-LS-N003

23 feet 5 inches

e. Suppression Chamber Water Level-High

E41-LSH-N015A, B

-25 inches

4. Automatic Depressurization System (ADS) Trip System A

a. Reactor Vessel Water Level-Low Level 3

B21-LT-N031B, D B21-LTS-N031B-3, D-3

45 inches

b. ADS Timer

B21-TDPU-K5A

83 seconds

c. Reactor Vessel Water Level-Low Level 1

B21-LT-N042B B21-LTM-N042B-1

166 inches

d. Core Spray Pump Discharge Pressure-High

E21-PS-N008B E21-PS-N009B

115 psig

e. RHR (LPCI Mode) Pump Discharge Pressure-High

E11-PS-N016B, D E11-PS-N020B, D

115 psig

5. ADS Trip System B

a. Reactor Vessel Water Level-Low Level 3

B21-LT-N031A, C B21-LTS-N031A-3, C-3

45 inches

b. ADS Timer

B21-TDPU-K5B

83 seconds

c. Reactor Vessel Water Level-Low Level 1

B21-LT-N042A B21-LTM-N042A-1

166 inches

d. Core Spray Pump Discharge Pressure-High

E21-PS-N008A E21-PS-N009A

115 psig

e. RHR (LPCI Mode) Pump Discharge Pressure-High E11-PS-N016A, C E11-PS-N020A, C

115 psig

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-17 Revision No. 23 TRM Table 3.3.5.2-1 (page 1 of 1) Reactor Core Isolation Cooling System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

NOMINAL TRIP SETPOINT

1. Reactor Vessel Water Level-Low Level 2

B21-LT-N031A, B, C, D B21-LTM-N031A-1, B-1, C-1, D-1

105 inches

2. Reactor Vessel Water Level-High

B21-LT-N017A-2, C-2 B21-LTM-N017A-2, C-2

206 inches

3. Condensate Storage Tank Level-Low

E51-LSL-4463 E51-LSL-4464

23 feet 1 inch

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-18 Revision No. 28 TRM Table 3.3.6.1-1 (page 1 of 5) Primary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

NOMINAL TRIP SETPOINT

1. Main Steam Line Isolation

a. Reactor Vessel Water Level-Low Level 3

B21-LT-N024A-1, B-1 B21-LT-N025A-1, B-1 B21-LTS-N024A-1-2, B-1-2 B21-LTS-N025A-1-2, B-1-2

45 inches

b. Main Steam Line Pressure-Low

B21-PT-N015A, B, C, D B21-PTM-N015A-1, B-1, C-1, D-1

835 psig c. Main Steam Line Flow-High

B21-PDT-N006A, B, C, D B21-PDT-N007A, B, C, D B21-PDT-N008A, B, C, D B21-PDT-N009A, B, C, D B21-PDTM-N006A-1, B-1, C-1, D-1 B21-PDTM-N007A-1, B-1, C-1, D-1 B21-PDTM-N008A-1, B-1, C-1, D-1 B21-PDTM-N009A-1, B-1, C-1, D-1

137% rated steam flow

d. Condenser Vacuum-Low

B21-PT-N056A, B, C, D B21-PTM-N056A-1, B-1, C-1, D-1

10 inches Hg vacuum

e. Main Steam Isolation Valve Pit Temperature-High

B21-TS-N010A, B, C, D

190°F f. Main Steam Line Flow-High (Not in Run)

B21-PDTS-N006A-2 B21-PDTS-N007B-2 B21-PDTS-N008C-2 B21-PDTS-N009D-2

30% rated steam flow 2. Primary Containment Isolation

a. Reactor Vessel Water Level-Low Level 1

B21-LT-N017A-1, B-1, C-1, D-1 B21-LTM-N017A-1, B-1, C-1, D-1

166 inches

b. Drywell Pressure-High

C72-PT-N002A, B, C, D C72-PTM-N002A-1, B-1, C-1, D-1 E11-PT-N011A, B, C, D E11-PTS-N011A-2, B-2, C-2, D-2

1.7 psig

c. Main Stack Radiation-High

2-D12-RM-80S

(a)

d. Reactor Building Exhaust Radiation-High

D12-RM-K609A, B D12-RE-N010A, B

4 mR/hr (continued)

(a) Nominal Trip Setpoint established in accordance with the methodology in the Offsite Dose Calculation Manual.

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-19 Revision No. 23 TRM Table 3.3.6.1-1 (page 2 of 5) Primary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

NOMINAL TRIP SETPOINT

3. High Pressure Coolant Injection (HPCI) System Isolation

a. HPCI Steam Line Flow-High

E41-PDTM-N004-1, E41-PDTM-N005-1 E41-PDTS-N004-2, E41-PDTS-N005-2

220% rated steam flow

b. HPCI Steam Line Flow-High Time Delay Relay

E41-TDR-K33, E41-TDR-K43 5 seconds

c. HPCI Steam Supply Line Pressure-Low

E41-PSL-N001A, B, C, D

115 psig

d. HPCI Turbine Exhaust Diaphragm Pressure-High

E41-PSH-N012A, B, C, D

7 psig

e. Drywell Pressure-High

E11-PT-N011C, D E11-PTS-N011C-2, D-2

1.7 psig

f. HPCI Steam Line Area Temperature-High B21-XY-5948A Ch. A5-2: E41-TE-3488 B21-XY-5948B Ch. A5-2: E41-TE-3489

165°F g. HPCI Steam Line Tunnel Ambient Temperature-High

B21-XY-5948A Ch. A2-2: E41-TE-3314 Ch. A5-1: E51-TE-N025C B21-XY-5948B Ch. A5-1: E51-TE-N025D

165°F 190°F 190°F

h. HPCI Steam Line Tunnel Differential Temperature-High

B21-XY-5948A Ch. A6-1: E51-TE-N026C and E51-TE-N027C B21-XY-5948B Ch. A6-1: E51-TE-N026D and E51-TE-N027D

47°F

i. HPCI Equipment Area Temperature-High

B21-XY-5948A Ch. A3-2: E41-TE-3316 Ch. A4-2: E41-TE-3318 Ch. A1-1: E41-TE-N030A B21-XY-5948B Ch. A2-2: E41-TE-3315 Ch. A3-2: E41-TE-3317 Ch. A4-2: E41-TE-3354 Ch. A1-1: E41-TE-N030B

165°F (continued)

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-20 Revision No. 23 TRM Table 3.3.6.1-1 (page 3 of 5) Primary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

NOMINAL TRIP SETPOINT

4. Reactor Core Isolation Cooling (RCIC) System Isolation

a. RCIC Steam Line Flow-High

E51-PDTM-N017-1, E51-PDTM-N018-1 E51-PDTS-N017-2, E51-PDTS-N018-2

220% rated steam flow

b. RCIC Steam Line Flow-High Time Delay Relay

E51-TDR-K32, E51-TDR-K12

5 seconds

c. RCIC Steam Supply Line Pressure-Low

E51-PS-N019A, B, C, D

70

d. RCIC Turbine Exhaust Diaphragm Pressure-High

E51-PS-N012A, B, C, D

5 psig

e. Drywell Pressure-High

E11-PT-N011A, B E11-PTS-N011A-2, B-2

1.7 psig

f. RCIC Steam Line Area Temperature-High

B21-XY-5949A Ch. A6-4: E51-TE-3487 B21-XY-5949B Ch. A4-4: E51-TE-3320

165°F g. RCIC Steam Line Tunnel Ambient Temperature-High

B21-XY-5949A Ch. A3-4: E51-TE-3319 Ch. A3-3: E51-TE-N025A B21-XY-5949B Ch. A3-3: E51-TE-N025B

165°F 190°F 190°F

h. RCIC Steam Line Tunnel and Area Temperature-High Time Delay B21-XY-5949A Ch. A3-3: E51-TE-N025A Ch. A3-4: E51-TE-3319 Ch. A4-3: E51-TE-N026A and E51-TE-N027A Ch. A6-4: E51-TE-3487 B21-XY-5949B Ch. A3-3: E51-TE-N025B Ch. A4-3: E51-TE-N026B and E51-TE-N027B Ch. A4-4: E51-TE-3320

27 minutes

i. RCIC Steam Line Tunnel Differential Temperature-High

B21-XY-5949A Ch. A4-3: E51-TE-N026A and E51-TE-N027A B21-XY-5949B Ch. A4-3: E51-TE-N026B and E51-TE-N027B

47°F

(continued)

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-21 Revision No. 23 TRM Table 3.3.6.1-1 (page 4 of 5) Primary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

NOMINAL TRIP SETPOINT

4. RCIC System Isolation (continued)

j. RCIC Equipment Area Temperature-High

B21-XY-5949A Ch. A4-4: E51-TE-3321 Ch. A5-4: E51-TE-3323 Ch. A1-3: E51-TE-N023A B21-XY-5949B Ch. A5-4: E51-TE-3322 Ch. A6-3: E51-TE-3355 Ch. A1-3: E51-TE-N023B

165°F k. RCIC Equipment Area Differential Temperature-High

B21-XY-5949A Ch. A2-3: E51-TE-N021A and E51-TE-N022A B21-XY-5949B Ch. A2-3: E51-TE-N021B and E51-TE-N022B

47°F

5. Reactor Water Cleanup (RWCU) System Isolation

a. Differential Flow-High

B21-XY-5949B G31-FT-N012 G31-FT-N041 G31-FT-N036

43 gpm

b. Differential Flow-High Time Delay

B21-XY-5949B G31-FT-N012 G31-FT-N041 G31-FT-N036

28.5 minutes

c. Area Temperature-High

B21-XY-5949A Ch. A1-1: G31-TE-N016A Ch. A2-1: G31-TE-N016C Ch. A3-1: G31-TE-N016E B21-XY-5949B Ch. A1-1: G31-TE-N016B Ch. A2-1: G31-TE-N016D Ch. A3-1: G31-TE-N016F

140°F d. Area Ventilation Differential Temperature-High

B21-XY-5949A Ch. A4-1: G31-TE-N022A and G31-TE-N023A Ch. A5-1: G31-TE-N022C and G31-TE-N023C Ch. A6-1: G31-TE-N022E and G31-TE-N023E B21-XY-5949B Ch. A4-1: G31-TE-N022B and G31-TE-N023B Ch. A5-1: G31-TE-N022D and G31-TE-N023D Ch. A6-1: G31-TE-N022F and G31-TE-N023F

47°F

(continued)

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-22 Revision No. 48 TRM Table 3.3.6.1-1 (page 5 of 5) Primary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

NOMINAL TRIP SETPOINT

5. Reactor Water Cleanup (RWCU) System Isolation (continued)

e. Piping Outside RWCU Rooms Area Temperature-High

B21-XY-5949A Ch. A1-2: G31-TE-5931 B21-XY-5949B Ch. A1-2: G31-TE-5932

115°F f. SLC System Initiation

C41A-S1 NA

g. Reactor Vessel Water Level-Low Level 2

B21-LT-N024A-1, B-1 B21-LT-N025A-1, B-1 B21-LTM-N024A-1-1, B-1-1 B21-LTM-N025A-1-1, B-1-1

105 inches

6. RHR Shutdown Cooling System Isolation

a. Reactor Steam Dome Pressure-High

B32-PS-N018A-1, B

130.8 psig

b. Reactor Vessel Water Level- Low Level 1

7. Traversing In-Core Probe Isolation

a. Reactor Vessel Water Level-Low Level 1

b. Drywell Pressure-High

B21-LT-N017A-1, B-1, C-1, D-1 B21-LTM-N017A-1, B-1, C-1, D-1

B21-LT-N017A-1, B-1 B21-LTM-N017A-1, B-1

C72-PT-N002A, B C72-PTM-N002A-1, B-1 166 inches

166 inches

1.7 psig TRM TS Instrument List Appendix B

Brunswick Unit 2 B-23 Revision No. 23 TRM Table 3.3.6.2-1 (page 1 of 1) Secondary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

NOMINAL TRIP SETPOINT

1. Reactor Vessel Water Level-Low Level 2

B21-LT-N024A-1, B-1 B21-LT-N025A-1, B-1 B21-LTM-N024A-1-1, B-1-1 B21-LTM-N025A-1-1, B-1-1

105 inches

2. Drywell Pressure-High

C72-PT-N002A, B, C, D C72-PTM-N002A-1, B-1, C-1, D-1

1.7 psig

3. Reactor Building Exhaust Radiation-High

D12-RE-N010A, B D12-RM-K609A, B

4 mR/hr

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-24 Revision No. 34 TRM Table 3.3.7.1-1 (page 1 of 1) Control Room Emergency Ventilation System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

NOMINAL TRIP SETPOINT

1. Control Building Air Intake Radiation-High

1-D22-RM-K600-1-2, 1-D22-RE-N001-1-2 1-D22-RM-K600-1-3, 1-D22-RE-N001-1-3

7 mR/hr 2. Unit 2 Secondary Containment Isolation - CREV Auto-Start

a. Reactor Vessel Water Level-Low Level 2

b. Drywell Pressure-High

B21-LT-N024A-1, B-1 B21-LT-N025A-1, B-1 B21-LTM-N024A-1-1, B-1-1 B21-LTM-N025A-1-1, B-1-1

C72-PT-N002A, B, C, D C72-PTM-N002A-1, B-1, C-1, D-1

105 inches

1.7 psig TRM TS Instrument List Appendix B

Brunswick Unit 2 B-25 Revision No. 23 TRM Table 3.3.7.2-1 (page 1 of 1) Condenser Vacuum Pump Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

NOMINAL TRIP SETPOINT

1. Main Steam Line Radiation-High

D12-RM-K603A, B, C, D

2.8 times

background radiation (mR/hr)

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-26 Revision No. 63 TRM Table 3.3.8.1-1 (page 1 of 1) Loss of Power Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

NOMINAL TRIP SETPOINT

1. 4.16 kV Emergency Bus Undervoltage (Loss of Voltage)

a. Bus Undervoltage

Relay Type - IAV53K Device Number - 27/59E

3255 V (a) 93 V(b)(c) b. Time Delay

Relay Type - IAV53K Device Number - 27/59E

1.15 seconds (e) 2. 4.16 kV Emergency Bus Undervoltage (Degraded Voltage)

a. Bus Undervoltage

Device Number - 27/DV

3732 V (a) 106.64 V (b)(d) b. Time Delay

Device Number - 27/DV

10 seconds

(a) Based on 4.16 kV bus voltage.

(b) Based on 120 V bus voltage.

(c) The Allowable Value based on 4.16 kV bus voltage is specified in the TS. The Allowable Value based on 120 V bus voltage is 89.0 V to 97.1 V.

(d) The Allowable Value based on 4.16 kV bus voltage is specified in the TS. The Allowable Value based on 120 V bus voltage is 105.9 V to 107.1 V.

(e) This is an inverse time delay relay. The time delay is inversely related to the ratio of reset voltage to setpoint voltage.

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-27 Revision No. 64 TRM Table 3.3.8.2-1 (page 1 of 1) Reactor Protection System (RPS) Electric Power Monitoring TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

NOMINAL TRIP SETPOINT

1. RPS Motor Generator Set Electric Power Monitoring Assembly a. Overvoltage

2-C72-EPA1, 2, 3, 4

125 V b. Undervoltage

2-C72-EPA1, 2, 3, 4 109 V

c. Underfrequency

2-C72-EPA1, 2, 3, 4 57.7 Hz

2. RPS Alternate Power Supply Electric Power Monitoring Assembly

a. Overvoltage

2-C72-EPA5, 6

125 V b. Undervoltage

2-C72-EPA5, 6 109 V

c. Underfrequency

2-C72-EPA5, 6 57.7 Hz

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-28 Revision No. 23 TRM Table 3.4.4-1 (page 1 of 1) Reactor Coolant System Operational LEAKAGE TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

1. Drywell Floor Drain Sump Flow Monitor

G16-FQ-K601, G16-FYQ-K601, G16-FT-N003

2. Drywell Equipment Drain Sump Flow Monitor

G16-FQ-K603, G16-FYQ-K603, G16-FT-N013

TRM TS Instrument List Appendix B

Brunswick Unit 2 B-29 Revision No. 23 TRM Table 3.4.5-1 (page 1 of 1) Reactor Coolant System Leakage Detection Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

1. Drywell Floor Drain Sump Flow Monitor

G16-FQ-K601, G16-FYQ-K601, G16-FT-N003

2. Primary Containment Atmosphere Particulate Monitor

CAC-AQH-1260-1 CAC-AQH-1262-1

3. Atmosphere Gaseous Radioactivity Monitor CAC-AQH-1260-3 CAC-AQH-1262-3

Brunswick Unit 2 Revision No. 23 APPENDIX C TECHNICAL REQUIREMENTS MANUAL (TRM) INSTRUMENT LIST

TRM TRM Instrument List Appendix C

Brunswick Unit 2 C-1 Revision No. 23 APPENDIX C TECHNICAL REQUIREMENTS MANUAL (TRM) INSTRUMENT LIST

PURPOSE This appendix provides instrument tables to aid in complying with the TRM instrumentation

requirements. This appendix does not define OPERABILITY for individual channels. For

OPERABILITY of instrument channels, refer to the Bases of the associated TRM Specification, the Updated Final Safety Analysis Report, or the associated Design Basis Document.

Each table in the TRM Instrument List corresponds to the associated TRM. For example; TRM

Table 3.3-2, "Control Rod Block Instrumentation," corresponds to TRM 3.3, "Control Rod Block

Instrumentation." Each TRM Instrument List Table includes the applicable instrument

number(s) associated with each TRM instrument function and the trip setpoint associated with

each TRM instrument function, where applicable.

Each TRM instrument function with a trip setpoint value specified is considered to be properly

adjusted when the "as left" value of the instrumentation is in compliance with the trip setpoint

specified in the TRM and in compliance with the "as-left" tolerance specified in the surveillance

test. Additionally, the "as found" value must be in compliance with the Allowable Value

specified in the TRM.

TRM TRM Instrument List Appendix C

Brunswick Unit 2 C-2 Revision No. 44 TRM Table 3.3-2 (page 1 of 1) Control Rod Block Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

TRIP SETPOINT

1. Average Power Range Monitors

a. Simulated Thermal Power - High

C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11

0.55W + 53.5% RTP (a) and 108.0% RTP

b. Inoperative

C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11

NA

c. Downscale

C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11

2.4% RTP

d. Simulated Thermal Power - High (Setdown)

C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11

12.0% RTP

2. Source Range Monitors

a. Detector Not Full In

C51-SRM-A, B, C, D

NA

b. Upscale

C51-SRM-A, B, C, D

1 X 10 5 cps c. Inoperative

C51-SRM-A, B, C, D

NA

d. Downscale

C51-SRM-A, B, C, D

3 cps

3. Intermediate Range Monitors

a. Detector Not Full In

C51-IRM-A, B, C, D C51-IRM-E, F, G, H

NA

b. Upscale

C51-IRM-A, B, C, D C51-IRM-E, F, G, H

108/125 of full scale

c. Inoperative

C51-IRM-A, B, C, D C51-IRM-E, F, G, H

NA

d. Downscale

C51-IRM-A, B, C, D C51-IRM-E, F, G, H

3/125 of full scale

4. Scram Discharge Volume Water Level-High

C12-LSH-N013E

73 gallons (a) [(0.55(W - W) + 53.5 RTP] when Specification 3.3.1.1, Function 2.b, is reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating." The setpoint value of W is defined in plant procedures.

TRM TRM Instrument List

Appendix C

Brunswick Unit 2 C-3 Revision No. 61 TRM Table 3.4-2 (page 1 of 1)

Accident Monitoring Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

1. Suppression Chamber Atmosphere Temperature(b)

CAC-TE-1258-17 or 18 CAC-TY-4426-1 CAC-TR-4426-1A-5 or 1A-6 CAC-TE-1258-19 or 20 CAC-TY-4426-2 CAC-TR-4426-2A-5 or 2A-6

2. Drywell Radiation (c)

CAC-AR-1260

CAC-AQH-1260-1, 2, 3

CAC-AR-1262

CAC-AQH-1262-1, 2, 3

3. Safety/Relief Valve Position Indication

a. Primary-Sonic

b. Secondary-Temperature

B21-FY-4157 Thru 4167

B21-TR-R614 Points 1 Thru 11

4. Turbine Building Ventilation Monitor(d)

D12-RE-4563, D12-RR-4548-3

D12-RE-4562, D12-RR-4548-2

D12-RE-4561, D12-RR-4548-1 5. Offgas Stack Ventilation Monitor(d) D12-RE-4573, D12-RR-4599-2

D12-RE-4574, D12-RR-4599-1

D12-RE-4982, D12-RR-4599-3 6. Drywell and Suppression Chamber H 2 Analyzer (e) CAC-AT-4409-38, CAC-AR-4409-41/42 (Channel 3), CAC-AI-4409-32 CAC-AT-4410-38, CAC-AR-4410-41/42 (Channel 3), CAC-AI-4410-32 7. Drywell and Suppression Chamber O 2 Analyzer (e) CAC-AT-4409-37, CAC-AR-4409-41/42 (Channel 1), CAC-AI-4409-40 CAC-AT-4410-37, CAC-AR-4410-41/42 (Channel 1), CAC-AI-4410-40

(a) Not used (b) Also reference TS 3.3.3.1 and TRM 3.8 (c) Also reference TS 3.4.5 (d) Also reference ODCM 7.3.2 (e) An OPERABLE instrument shall consist of the AT instrument and either the AI instrument or the AR instrument.

TRM TRM Instrument List Appendix C

Brunswick Unit 2 C-4 Revision No. 28 TRM Table 3.5-2 (page 1 of 1) Chloride Intrusion Monitors TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

TRIP SETPOINT

1. Chloride Leak Detectors in the Condenser Hotwell Outlet Headers

CO-CR-24 CO-CIT-24A, CO-CIT-24B CO-CE-24-1, CO-CE-24-2, CO-CE-24-3, CO-CE-24-4

1.0 mhos/cm 2. Chloride Leak Detector in the Condensate Pump Discharge

a. Wide Range Monitor

b. Narrow Range Monitor

CO-CIS-3075-1

TS-CIT-863-3

2.0 mhos/cm 0.3 mhos/cm 3. Chloride Leak Detector in the Inlet to the Condensate Filter Demineralizer

CFD-CIT-1

0.3 mhos/cm 4. Chloride Leak Detector in the Inlet to the Deep Bed Demineralizer

CDD-CIT-1

0.3 mhos/cm TRM TRM Instrument List Appendix C

Brunswick Unit 2 C-5 Revision No. 23 TRM Table 3.6-2 (page 1 of 1) Bus Power Monitors TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

1. Core Spray System Bus Power Monitor

E21-K1A, E21-K1B

2. Low Pressure Coolant Injection (Residual Heat Removal System) Bus Power Monitor

E11-K106A, E11-K106B

3. High Pressure Coolant Injection System Bus Power Monitor

E41-K55, E41-K56

4. Automatic Depressurization System Bus Power Monitor

B21-K1A, B21-K1B

5. RCIC System Bus Power Monitor

E51-K42, E51-K43

TRM TRM Instrument List Appendix C

Brunswick Unit 2 C-6 Revision No. 23 TRM Table 3.7-1 (page 1 of 1) Automatic Depressurization System (ADS) Inhibit Switch TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

1. ADS Inhibit Switch A

B21-CS-S5A

2. ADS Inhibit Switch B

B21-CS-S5B

TRM TRM Instrument List Appendix C

Brunswick Unit 2 C-7 Revision No. 23 TRM Table 3.8-1 (page 1 of 1) Suppression Chamber Water Temperature Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

TRIP SETPOINT

1. Suppression Chamber Water Temperature

CAC-TE-4426-2 Thru 13, CAC-TY-4426-1, CAC-TR-4426-1A CAC-TE-4426-15 Thru 26, CAC-TY-4426-2, CAC-TR-4426-2A

95°F

TRM TRM Instrument List Appendix C

Brunswick Unit 2 C-8 Revision No. 47 TRM Table 3.9-2 (page 1 of 1) Seismic Monitoring Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

1. Passive Triaxial Peak Shock Recorders

a. Reactor Building Basement/Equipment Drain Tank (-17' level)

2-ENV-XRH-823-1 b. Reactor Building RHR Heat Exchanger Support (+20' level)

c. Reactor Building Refueling Area (+117' level)

2-ENV-XRH-823-2

2-ENV-XRH-823-3 2. Active Triaxial Accelerometers

a. Reactor Building (+89' 4" level)

b. Reactor Building (-17' level)

2-ENV-XT-823-2

2-ENV-XT-823-1

3. Active Seismic Recording System

a. Control Room

2-ENV-XT-823

TRM TRM Instrument List Appendix C

Brunswick Unit 2 C-9 Revision No. 52 TRM Table 3.10-1 (page 1 of 1) Intake Canal High Water Level Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

1. Intake Canal High Water Level(a) 2-SCW-LT-285 2-SCW-LI-285 2-SCW-LR-285 2-SCW-LRA-285-1

(a) Also reference TS 3.7.2 and TRM 3.20

TRM TRM Instrument List Appendix C

Brunswick Unit 2 C-10 Revision No. 51 TRM Table 3.11-2 (page 1 of 1) Primary Containment Isolation Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

TRIP SETPOINT

1. Main Steam Line Tunnel Temperature-High

B21-TE-N011A, B, C, D B21-TE-N012A, B, C, D B21-TE-N013A, B, C, D

190°F 2. Turbine Building Area Temperature-High

B21-TE-3225A, B, C, D B21-TE-3226A, B, C, D B21-TE-3227A, B, C, D B21-TE-3228A, B, C, D B21-TE-3229A, B, C, D B21-TE-3230A, B, C, D B21-TE-3231A, B, C, D B21-TE-3232A, B, C, D

190°F TRM TRM Instrument List Appendix C

Brunswick Unit 2 C-11 Revision No. 57 TRM Table 3.12-2 (page 1 of 1)

Control Room Emergency Ventila tion System Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S)

TRIP SETPOINT

1. Chlorine Isolation

a. Control Building Air Intake (Local)

1-X-AT-2977

2-X-AT-2977

1-X-AT-2977-1

2-X-AT-2977-1

5 ppm

b. Chlorine Tank Car Area (Remote)

1-X-AT-2979

2-X-AT-2979

1-X-AT-2979-1

2-X-AT-2979-1

5 ppm

2. Control Room Envelope Smoke Protection

a. Control Building Intake Air Duct Smoke Detectors

2-FP-CB-4-22

2-FP-CB-4-23

NA

Brunswick Unit 2 Revision No. 23 APPENDIX D PRIMARY CONTAINMENT ISOLATION VALVE (PCIV) LIST

TRM PCIV List Appendix D

Brunswick Unit 2 D-1 Revision No. 23 APPENDIX D PRIMARY CONTAINMENT ISOLATION VALVE (PCIV) LIST

PURPOSE This appendix provides two PCIV tables to aid in complying with the requirements of Technical

Specification (TS) 3.6.1.3, "Primary Containment Isolation Valves (PCIVs)."

TRM Table 3.6.1.3-1, "Primary Containment Isol ation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges," pr ovides a list of all isolation devices that are considered passive isolation devices and, with the exception of check valves and EFCVs, are normally closed while in MODE 1, 2, or 3. TRM Table 3.6.1.3-1 includes a reference to the

applicable TS Conditions and Surveillance Require ments. Manual valves and flanges that are locked, sealed, or otherwise secured in position are not required to be verified closed to meet

SR 3.6.1.3.1 or SR 3.6.1.3.2. Manual valves and flanges that are not locked, sealed, or otherwise secured in position are required to be verified closed to meet SR 3.6.1.3.1 or SR

3.6.1.3.2, as applicable.

TRM Table 3.6.1.3-2, "Power Operated and Automatic PCIVs," provides a list of all PCIVs that

are considered active isolation devices. TRM Table 3.6.1.3-2 includes a reference to the

applicable TS Conditions, Surveillance Requirements, the required Allowable Isolation Times, and primary containment Automatic Isolation Group, where applicable.

TRM PCIV List Appendix D

Brunswick Unit 2 D-2 Revision No. 26 TRM Table 3.6.1.3-1 (Page 1 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-B21-F008 REACTOR PRESSURE RIP VALVE TO B21-PS-N002 C SR 3.6.1.3.7 2-B21-F010A FEEDWATER LINE 'A' RPV INLET CHECK VALVE A, B NA 2-B21-F010B FEEDWATER LINE 'B' RPV INLET CHECK VALVE A, B NA 2-B21-F014A EFCV TO B21-PDT-N006A & B C SR 3.6.1.3.7 2-B21-F014B EFCV TO B21-PDT-N006A & B C SR 3.6.1.3.7 2-B21-F014C EFCV TO B21-PDT-N006C & D C SR 3.6.1.3.7 2-B21-F014D EFCV TO B21-PDT-N006C & D C SR 3.6.1.3.7 2-B21-F014E EFCV TO B21-PDT-N007A & B C SR 3.6.1.3.7 2-B21-F014F EFCV TO B21-PDT-N007A & B C SR 3.6.1.3.7 2-B21-F014G EFCV TO B21-PDT-N007C & D C SR 3.6.1.3.7 2-B21-F014H EFCV TO B21-PDT-N007C & D C SR 3.6.1.3.7 2-B21-F014J EFCV TO B21-PDT-N008A & B C SR 3.6.1.3.7 2-B21-F014K EFCV TO B21-PDT-N008A & B C SR 3.6.1.3.7 2-B21-F014L EFCV TO B21-PDT-N008C & D C SR 3.6.1.3.7 2-B21-F014M EFCV TO B21-PDT-N008C & D C SR 3.6.1.3.7 2-B21-F014N EFCV TO B21-PDT-N009A & B C SR 3.6.1.3.7 2-B21-F014P EFCV TO B21-PDT-N009A & B C SR 3.6.1.3.7 2-B21-F014R EFCV TO B21-PDT-N009C & D C SR 3.6.1.3.7 2-B21-F014S EFCV TO B21-PDT-N009C & D C SR 3.6.1.3.7 2-B21-F017 B21-F019 INBOARD TEST CONNECTION VALVE A, B NA 2-B21-F025A OUTBOARD B21-F028A INBOARD TEST VALVE A, B NA 2-B21-F025B OUTBOARD B21-F028B INBOARD TEST VALVE A, B NA 2-B21-F025C OUTBOARD B21-F028C INBOARD TEST VALVE A, B NA 2-B21-F025D OUTBOARD B21-F028D INBOARD TEST VALVE A, B NA 2-B21-F030A FEEDWATER LINE A INBOARD TEST VALVE A, B NA 2-B21-F030B FEEDWATER LINE B INBOARD TEST VALVE A, B NA 2-B21-F040

REACTOR LEVEL RIP VALVE TO B21-LT-3331 AND N027 C SR 3.6.1.3.7 (continued)

TRM PCIV List Appendix D

Brunswick Unit 2 D-3 Revision No. 23 TRM Table 3.6.1.3-1 (Page 2 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-B21-F042A REACTOR LEVEL RIP VALVE TO B21-LT-N024A-1 & 2 C SR 3.6.1.3.7 2-B21-F042B REACTOR LEVEL INSTRUMENT EFCV (X-69A) C SR 3.6.1.3.7 2-B21-F044A REACTOR LEVEL RIP VALVE TO B21-LT-N025A-1 & 2 C SR 3.6.1.3.7 2-B21-F044B REACTOR LEVEL INSTRUMENT EFCV (X-69B) C SR 3.6.1.3.7 2-B21-F046A REACTOR LEVEL RIP VALVE TO B21-LT-N017-1 & 2 C SR 3.6.1.3.7 2-B21-F046B REACTOR LEVEL INSTRUMENT EFCV (X-69C) C SR 3.6.1.3.7 2-B21-F047C PENETRATION X53-B EFCV C SR 3.6.1.3.7 2-B21-F047D REACTOR INSTRUMENT EFCV (X-83A) C SR 3.6.1.3.7 2-B21-F048A REACTOR LEVEL RIP VALVE TO B21-LT-N036, N017-1 C SR 3.6.1.3.7 2-B21-F048B REACTOR LEVEL INSTRUMENT EFCV (X-69D) C SR 3.6.1.3.7 2-B21-F049C PENETRATION X53-A EFCV C SR 3.6.1.3.7 2-B21-F049D REACTOR LEVEL EFCV B21-LT-N017A-1&2 C SR 3.6.1.3.7 2-B21-F050A JP-5 FLOW HI PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F050B JP-15 FLOW HI PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F050C JP-10 FLOW HI PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F050D JP-20 FLOW HI PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F052A JP-5 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F052B JP-15 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F052C JP-10 FLOW HI PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F052D JP 20 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F054 X-61B EFCV TO B21-PDT-N032 C SR 3.6.1.3.7 2-B21-F056 X-61A EFCV HIGH C SR 3.6.1.3.7 2-B21-F058A JP-1 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058B JP-11 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058C JP-2 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058D JP-12 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058E JP-3 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058F JP-13 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058G JP-4 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058H JP-14 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058L JP-6 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058M

JP-16 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 (continued)

TRM PCIV List Appendix D

Brunswick Unit 2 D-4 Revision No. 30 TRM Table 3.6.1.3-1 (Page 3 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-B21-F058N JP-7 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058P JP-17 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058R JP-8 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058S JP-18 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058T JP-9 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058U JP-19 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F060 JP-11-20 FLOW HI PRESSURE EFCV TO CORE PLATE C SR 3.6.1.3.7 2-B21-IV-2149 EFCV (X-69E) CAPPED C SR 3.6.1.3.7 2-B21-IV-2196 E21-PDS-N004B REACTOR INSTRUMENT PENETRATION VALVE C SR 3.6.1.3.7 2-B21-IV-2455 EFCV TO B21-LT-N026A C SR 3.6.1.3.7 2-B21-IV-2456 EFCV TO B21-LT-N026B C SR 3.6.1.3.7 2-B21-V10 B21-F032A VALVE INBOARD BODY DRAIN VALVE A, B NA 2-B21-V13 B21-F032B VALVE INBOARD BODY DRAIN VALVE A, B NA 2-B21-V83 RPV FLANGE SEAL LEAK DETECTION TEST LINE C NA 2-B21-V160 B21-LT-N026B INSTRUMENT LINE INBOARD TEST VALVE C NA 2-B21-V161 B21-LT-N026A INSTRUMENT LINE INBOARD TEST VALVE C NA 2-B32-F005A RECIRC. PUMP 2A UPPER SEAL PRESSURE RIP VALVE C SR 3.6.1.3.7 2-B32-F005B RECIRC. PUMP 2B UPPER SEAL PRESSURE RIP VALVE C SR 3.6.1.3.7 2-B32-F006A RECIRC. PUMP 2A LOWER SEAL PRESSURE RIP VALVE C SR 3.6.1.3.7 2-B32-F006B RECIRC. PUMP 2B LOWER SEAL PRESSURE RIP VALVE C SR 3.6.1.3.7 2-B32-F021 SAMPLE LINE DRAIN ROOT VALVE A, B NA 2-B32-F039A LO PRESSURE RIP VALVE TO B32-PDT-N015A C SR 3.6.1.3.7 2-B32-F039B HI PRESSURE RIP VALVE TO B32-PDT-N015B C SR 3.6.1.3.7 2-B32-F039C HI PRESSURE RIP VALVE TO B32-PDT-N015A C SR 3.6.1.3.7 2-B32-F039D LO PRESSURE RIP VALVE TO B32-PDT-N015B C SR 3.6.1.3.7 2-B32-F041A LO PRESSURE RIP VALVE TO B32-FT-N014A & B C SR 3.6.1.3.7 2-B32-F041B LO PRESSURE RIP VALVE TO B32-FT-N024A & B C SR 3.6.1.3.7 2-B32-F041C LO PRESSURE RIP VALVE TO B32-FT-N014C & D C SR 3.6.1.3.7 2-B32-F041D

LO PRESSURE RIP VALVE TO B32-FT-N024C & D C SR 3.6.1.3.7 (continued)

TRM PCIV List Appendix D

Brunswick Unit 2 D-5 Revision No. 26 TRM Table 3.6.1.3-1 (Page 4 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-B32-F042A HI PRESSURE RIP VALVE TO B32-FT-N014A & B C SR 3.6.1.3.7 2-B32-F042B HI PRESSURE RIP VALVE TO B32-FT-N024A & B C SR 3.6.1.3.7 2-B32-F042C HI PRESSURE RIP VALVE TO B32-FT-N014C & D C SR 3.6.1.3.7 2-B32-F042D HI PRESSURE RIP VALVE TO B32-FT-N024C & D C SR 3.6.1.3.7 2-B32-F058A RIP VALVE B32-PS-N018A & B32-PS-N018A-1 C SR 3.6.1.3.7 2-B32-F058B RIP VALVE TO B32-PS-N018B C SR 3.6.1.3.7 2-B32-V24 RECIRC PUMP 2A SEAL INJECTION CHECK VALVE A, B NA 2-B32-V32 RECIRC PUMP 2B SEAL INJECTION CHECK VALVE A, B NA 2-B32-V97 EFCV B32-F006B INLET TEST VALVE C NA 2-B32-V98 EFCV B32-F005B INLET TEST VALVE C NA 2-B32-V99 EFCV B32-F006A INLET TEST VALVE C NA 2-B32-V100 EFCV B32-F005A INLET TEST VALVE C NA 2-B32-V105 LLRT VALVE FOR B32-V22 A, B NA 2-B32-V109 LLRT VALVE FOR B32-V30 A, B NA 2-CAC-IV-695 CAC-PT-4175 INSTRUMENT DRAIN VALVE C NA 2-CAC-IV-696 CAC-PSH-2684 INSTRUMENT DRAIN VALVE C NA 2-CAC-IV-899 CAC-PT-1257-2A INSTRUMENT DRAIN VALVE C NA 2-CAC-IV-933 CAC-PT-4176 INSTRUMENT DRAIN VALVE C NA 2-CAC-IV-934 CAC-PT-2685 INSTRUMENT DRAIN VALVE C NA 2-CAC-IV-940 CAC-PT-3341 INSTRUMENT DRAIN VALVE C NA 2-CAC-IV-1368 CAC-LT-2601 LOW PRESSURE INSTRUMENT CALIBRATION VALVE C NA 2-CAC-IV-1369 CAC-LT-2601 HIGH PRESSURE INSTRUMENT CALIBRATION VALVE C NA 2-CAC-IV-1473 CAC-LT-4177 HIGH PRESSURE INSTRUMENT CALIBRATION VALVE C NA 2-CAC-IV-1474 CAC-LT-4177 LOW PRESSURE INSTRUMENT CALIBRATION VALVE C NA 2-CAC-IV-1475 CAC-LG-4336 SUPPRESSION POOL LEVEL SIGHT GLASS LINE LOWER ISOLATION VALVE C NA 2-CAC-IV-1476 CAC-LG-4336 SUPPRESSION POOL LEVEL SIGHT GLASS LINE UPPER ISOLATION VALVE C NA 2-CAC-IV-1481 SURGE VOLUME RESERVOIR LEVEL GAUGE CAC-LG-5121 UPPER ISOLATION VALVE C NA 2-CAC-IV-1482 SURGE RESERVOIR LEVEL GAUGE CAC-LG-5120 UPPER ISOLATION VALVE C NA 2-CAC-IV-1492 CAC-LT-3342 LOW PRESSURE INSTRUMENT CALIBRATION VALVE C NA (continued)

TRM PCIV List Appendix D

Brunswick Unit 2 D-6 Revision No. 26 TRM Table 3.6.1.3-1 (Page 5 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-CAC-IV-1493 CAC-LT-3342 HIGH PRESSURE INSTRUMENT CALIBRATION VALVE C NA 2-CAC-IV-1494 CAC-LT-2602 LOW PRESSURE INSTRUMENT CALIBRATION VALVE C NA 2-CAC-IV-1495 CAC-LT-2602 HIGH PRESSURE INSTRUMENT CALIBRATION VALVE C NA 2-CAC-IV-2117 SURGE VOLUME RESERVOIR LEVEL GAUGE CAC-LG-5120 LOWER ISOLATION VALVE C NA 2-CAC-IV-2118 SURGE VOLUME RESERVOIR LEVEL GAUGE CAC-LG-5121 LOWER ISOLATION VALVE C NA 2-CAC-IV-2151 CAC-PT-5113 INSTRUMENT DRAIN VALVE C NA 2-CAC-LT-1216-6 CAC-LT-1216 HIGH PRESSURE INSTRUMENT DRAIN VALVE C NA 2-CAC-LT-1216-7 CAC-LT-1216 LOW PRESSURE INSTRUMENT DRAIN VALVE C NA 2-CAC-PDS-4222-6 CAC-PDS-4222 INSTRUMENT DRAIN VALVE C NA 2-CAC-PDS-4223-6 CAC-PDS-4223 INSTRUMENT DRAIN VALVE C NA 2-CAC-PT-1230-10 CAC-PT-1230 INSTRUMENT TEST VALVE C NA 2-CAC-PT-1257-2B-6 CAC-PT-1257-2B INSTRUMENT DRAIN VALVE C NA 2-CAC-V28 LINE 4-18-152 DRAIN VALVE A, B NA 2-CAC-V34 SUPPRESSION POOL PURGE EXHAUST LINE INBOARD DRAIN VALVE A, B NA 2-CAC-V41 CAC-X20A BEFORE SEAT DRAIN VALVE A, B NA 2-CAC-V44 CAC-X20B BEFORE SEAT DRAIN VALVE A, B NA 2-CAC-V53 CAC-V49 BEFORE SEAT DRAIN VALVE A, B NA 2-CAC-V54 CAC-V49 BEFORE SEAT DRAIN VALVE A, B NA 2-CAC-V79 DRYWELL PURGE EXHAUST LINE INBOARD DRAIN VALVE A, B NA 2-CAC-V81 DRYWELL HEAD PURGE LINE INBOARD DRAIN VALVE A, B NA 2-CAC-V164 CAD N2 INJECTION LINE VENT VALVE A, B NA 2-CAC-V166 SUPP POOL PURGE EXHAUST LINE VENT VALVE A, B NA 2-CAC-V169 CAD N2 INJECTION LINE VENT VALVE A, B NA 2-CAC-V179 TEST CONNECTION VALVE ON LINE CAC-734 C NA 2-CAC-V180 TEST CONNECTION VALVE ON LINE CAC-733 C NA 2-CAC-V183 SURGE VOLUME RESERVOIR LEVEL GAUGE CAC-LG-5777 ISOLATION VALVE C NA 2-CAC-V184 SURGE VOLUME RESERVOIR LEVEL GAUGE CAC-LG-5777 ISOLATION VALVE C NA 2-CAC-V185 SURGE VOLUME RESERVOIR LEVEL GAUGE CAC-LG-5776 ISOLATION VALVE C NA (continued)

TRM PCIV List Appendix D

Brunswick Unit 2 D-7 Revision No. 26 TRM Table 3.6.1.3-1 (Page 6 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-CAC-V186 SURGE VOLUME RESERVOIR LEVEL GAUGE CAC-LG-5776 ISOLATION VALVE C NA 2-C12-F101 (XX-XX) HCU INSERT HEADER VENT VALVE C SR 3.6.1.3.1 2-C12-F102 (XX-XX) HCU WITHDRAW HEADER VENT VALVE C SR 3.6.1.3.1 2-C41-F006 SLC OUTBOARD INJECTION CHECK VALVE A, B NA 2-C41-F007 SLC INBOARD INJECTION CHECK VALVE A, B NA 2-C41-F026 C41-F006 INBOARD TEST VALVE A, B NA 2-C51-TIP-CHV TIP NITROGEN PURGE LINE CHECK VALVE C NA 2-C72-IV-1378 C72-PT-N002C DRAIN VALVE C NA 2-C72-IV-1379 C72-PT-N002D INSTRUMENT DRAIN VALVE C NA 2-C72-IV-1414 C72-PT-N002B INSTRUMENT DRAIN VALVE C NA 2-C72-IV-1415 C72-PT-N002A INSTRUMENT DRAIN VALVE C NA 2-C72-PS-N004-6 C72-PS-N004 INSTRUMENT DRAIN VALVE C NA 2-C72-V5000 C72-701 FIRST SPARE INSTRUMENT ISOLATION VALVE C NA 2-C72-V5001 C72-701 SECOND SPARE INSTRUMENT ISOLATION VALVE C NA 2-C72-V5002 C72-702 FIRST SPARE INSTRUMENT ISOLATION VALVE C NA 2-C72-V5003 C72-702 SECOND SPARE INSTRUMENT ISOLATION VALVE C NA 2-E11-F025A RHR HEAT EXCHANGER 2A OUTLET PRESSURE RELIEF VALVE C NA 2-E11-F025B RHR HEAT EXCHANGER 2B OUTLET PRESSURE RELIEF VALVE C NA 2-E11-F029 SHUTDOWN COOLING SUCTION HEADER RELIEF C NA 2-E11-F036A CONTAINMENT SPRAY INBOARD AIR TEST ISOLATION VALVE A, B NA 2-E11-F055A RHR HEAT EXCHANGER 2A RE LIEF VALVE BLANK FLANGE C NA 2-E11-F055B RHR HEAT EXCHANGER 2B RE LIEF VALVE BLANK FLANGE C NA 2-E11-F058A LPCI LINE INBOARD TEST ISOLATION VALVE A, B NA 2-E11-F058B

LPCI LINE INBOARD TEST VALVE A, B NA (continued)

TRM PCIV List Appendix D

Brunswick Unit 2 D-8 Revision No. 23 TRM Table 3.6.1.3-1 (Page 7 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-E11-F063 E11-F008 UPSTREAM INBOARD DRAIN VALVE A, B NA 2-E11-F097 RCIC SUCTION FROM RHR SYSTEM RELIEF VALVE BLANK FLANGE C NA 2-E11-IV-1380 E11-PT-N019B INSTRUMENT DRAIN VALVE C NA 2-E11-IV-1381 E11-PT-N019D INSTRUMENT DRAIN VALVE C NA 2-E11-IV-1408 E11-PT-N019C INSTRUMENT DRAIN VALVE C NA 2-E11-IV-1409 E11-PT-N019A INSTRUMENT DRAIN VALVE C NA 2-E11-PT-N011A-6 E11-PT-N011A INSTRUMENT DRAIN VALVE C NA 2-E11-PT-N011B-6 E11-PT-N011B INSTRUMENT DRAIN VALVE C NA 2-E11-PT-N011C-6 E11-PT-N011C INSTRUMENT DRAIN VALVE C NA 2-E11-PT-N011D-6 E11-PT-N011D INSTRUMENT DRAIN VALVE C NA 2-E11-V20 RHR HEAT EXCHANGER 2A SHELL RELIEF VALVE C NA 2-E11-V21 RHR HEAT EXCHANGER 2B SHELL RELIEF VALVE C NA 2-E11-V74 VALVE E11-F020A INBOARD BODY DRAIN VALVE C NA 2-E11-V81 LPCI LINE HIGH POINT VENT VALVE A, B NA 2-E11-V82 VALVE E11-F015A INBOARD BODY DRAIN VALVE A, B NA 2-E11-V83 LPCI LINE HIGH POINT VENT VALVE A, B NA 2-E11-V84 VALVE E11-F021B INBOARD BODY DRAIN VALVE A, B NA 2-E11-V86 VALVE E11-F021B OUTBOARD BODY DRAIN VALVE A, B NA 2-E11-V87 VALVE E11-F024A BODY DRAIN VALVE A, B NA 2-E11-V91 VALVE E11-F028A BODY DRAIN VALVE A, B NA 2-E11-V92 VALVE E11-F015A OUTBOARD BODY DRAIN VALVE A, B NA 2-E11-V103 VALVE E11-F008 INBOARD BODY DRAIN VALVE A, B NA 2-E11-V121 VALVE E11-F021A OUTBOARD BODY DRAIN VALVE A, B NA (continued)

TRM PCIV List Appendix D

Brunswick Unit 2 D-9 Revision No. 42 TRM Table 3.6.1.3-1 (Page 8 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-E11-V122 VALVE E11-F021A INBOARD BODY DRAIN VALVE A, B NA 2-E11-V125 VALVE E11-F016B BODY DRAIN VALVE A, B NA 2-E11-V126 VALVE E11-F028B BODY DRAIN VALVE A, B NA 2-E11-V127 VALVE E11-F024B BODY DRAIN VALVE A, B NA 2-E11-V135 VALVE E11-F020B INBOARD BODY DRAIN VALVE C NA 2-E11-V169 VALVE E11-F015B INBOARD BODY DRAIN VALVE A, B NA 2-E11-V170 VALVE E11-F015B OUTBOARD BODY DRAIN VALVE A, B NA 2-E11-V189 CONTAINMENT SPRAY LINE INBOARD AIR TEST ISOLATION VALVE A, B NA 2-E11-V5003 E11-703 FIRST SPARE INSTRUMENT ISOLATION VALVE C NA 2-E11-V5004 E11-703 SECOND SPARE INSTRUMENT ISOLATION VALVE C NA 2-E11-V5005 E11-706 SPARE RACK ISOLATION VALVE C NA 2-E11-V5013 2-E11-F009 DOWNSTREAM SIDE BODY INBOARD VENT VALVE A, B NA 2-E21-F013A CS INJECTION LINE INBOARD TEST VALVE A, B NA 2-E21-F013B CS INJECTION LINE INBOARD TEST VALVE A, B NA 2-E21-F017A E21-PDS-N004A EFCV C SR 3.6.1.3.7 2-E21-F017B E21-PDS-N004B EFCV C SR 3.6.1.3.7 2-E21-V21 DIV I FULL FLOW BYPASS LINE DRAIN VALVE C NA 2-E21-V33 DIV II FULL FLOW BYPASS LINE DRAIN VALVE C NA 2-E21-V47 CS A MINIMUM FLOW BYPASS LINE TO SUPPRESSION POOL VENT VALVE C NA 2-E21-V49 CS B MINIMUM FLOW BYPASS LINE TO SUPPRESSION POOL VENT VALVE C NA 2-E21-V55 INBOARD BODY DRAIN VALVE (E21-F005A)

A, B NA 2-E21-V56 OUTBOARD BODY DRAIN VALVE (E21-F005A)

A, B NA 2-E21-V57 INBOARD BODY DRAIN VALVE (E21-F005B)

A, B NA 2-E21-V58

OUTBOARD BODY DRAIN VALVE (E21-F005B)

A, B NA (continued)

TRM PCIV List Appendix D

Brunswick Unit 2 D-10 Revision No. 26 TRM Table 3.6.1.3-1 (Page 9 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-E21-V77 INBOARD BODY DRAIN VALVE (E21-F001A) C NA 2-E21-V79 INBOARD BODY DRAIN VALVE (E21-F001B) C NA 2-E41-F013 HPCI TURBINE EXHAUST LINE INBOARD TEST VALVE A, B NA 2-E41-F014 HPCI STEAM SUPPLY LINE INBOARD TEST VALVE A, B NA 2-E41-F021 HPCI TURBINE EXHAUST LINE ISOLATION VALVE A, B NA 2-E41-F022 HPCI TURBINE EXHAUST DRAIN POT DRAIN VALVE TO TORUS A, B NA 2-E41-F023A E41-PDS-N004 & PS-N001A STEAM LINE PRESSURE C SR 3.6.1.3.7 2-E41-F023B HPCI STEAM LINE PRESSURE RIP VALVE C SR 3.6.1.3.7 2-E41-F023C HPCI STEAM LINE PRESSURE RIP VALVE C SR 3.6.1.3.7 2-E41-F023D HPCI STEAM LINE PRESSURE RIP VALVE C SR 3.6.1.3.7 2-E41-F040 HPCI EXHAUST DRAIN POT DRAIN TO TORUS CHECK VALVE A, B NA 2-E41-F047 EXHAUST DRAIN POT DRAIN LINE INBOARD TEST VALVE A, B NA 2-E41-F049 HPCI TURBINE EXHAUST LINE CHECK VALVE A, B NA 2-E41-F078 HPCI VACUUM BREAKER LINE DRAIN VALVE A, B NA 2-E41-F090 HPCI VACUUM BREAKER LINE DRAIN VALVE A, B NA 2-E41-F091 HPCI VACUUM BREAKER LINE DRAIN VALVE A, B NA 2-E41-IV-980 E41-LSH-N015A INSTRUMENT DRAIN VALVE C NA 2-E41-IV-981 E41-LSH-N015B INSTRUMENT DRAIN VALVE C NA 2-E41-V55 HPCI INJECTION LINE INBOARD TEST VALVE A, B NA 2-E41-V68 E41-F021 INBOARD BODY DRAIN VALVE C NA 2-E41-V70 E41-F042 INBOARD BODY DRAIN VALVE C NA 2-E41-V124 TEST CONNECTION VALVE ON LINE E41-716 C NA 2-E41-V126 TEST CONNECTION VALVE ON LINE E41-714 C NA 2-E41-V163 HPCI INJECTION LINE INBOARD DRAIN/TEST A, B NA 2-E41-V177

HPCI STEAM SUPPLY LINE OUTBOARD TEST VALVE (F003) A, B NA (continued)

TRM PCIV List Appendix D

Brunswick Unit 2 D-11 Revision No. 26 TRM Table 3.6.1.3-1 (Page 10 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-E41-V186 HPCI PUMP MINIMUM FLOW BYPASS LINE TEST VALVE C NA 2-E41-V188 E41-LSH-N015A TEST VENT VALVE C NA 2-E41-V189 E41-LSH-N015B TEST VENT VALVE C NA 2-E51-F001 RCIC TURBINE STEAM EXHAUST TO TORUS A, B NA 2-E51-F036 RCIC STEAM SUPPLY LINE INBOARD TEST VALVE A, B NA 2-E51-F040 RCIC TURBINE STEAM TO SUPPRESSION POOL A, B NA 2-E51-F041 RCIC TURBINE EXHAUST INBOARD TEST VALVE A, B NA 2-E51-F043A X-61F EFCV TO E51-PDT-N017 C SR 3.6.1.3.7 2-E51-F043B X-72F EFCV TO E51-PDT-N018 C SR 3.6.1.3.7 2-E51-F043C X-61E EFCV TO E51-PDT-N017 C SR 3.6.1.3.7 2-E51-F043D X-72E EFCV TO E51-PDT-N018 C SR 3.6.1.3.7 2-E51-F060 RCIC TURBINE EXHAUST VACUUM RELIEF TEST VALVE A, B NA 2-E51-F061 RCIC TURBINE EXHAUST VACUUM RELIEF TEST VALVE A, B NA 2-E51-F065 RCIC TURBINE EXHAUST VACUUM RELIEF TEST VALVE A, B NA 2-E51-V104 RCIC STEAM SUPPLY LINE OUTBOARD TEST VALVE (F008)

A, B NA 2-G16-V1110 DRYWELL FLOOR DRAIN LINE INBOARD DRAIN VALVE A, B NA 2-G16-V1112 DRYWELL EQUIPMENT DRAIN LINE INBOARD DRAIN VALVE A, B NA 2-G31-F037

RWCU RETURN TO REACTOR LINE TEST VALVE A, B NA (continued)

TRM PCIV List Appendix D

Brunswick Unit 2 D-12 Revision No. 26 TRM Table 3.6.1.3-1 (Page 11 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-RCC-IV-2374 RECIRC PUMP 2A COOLER OUTLET SAMPLE TEST C NA 2-RCC-IV-2375 RECIRC PUMP 2B COOLER OUTLET SAMPLE TEST C NA 2-RNA-V350 DIV II NON-INTERRUPTIBLE INSTRUMENT AIR SUPPLY INBOARD CHECK VALVE A, B NA 2-RNA-V351 DIV I NON-INTERRUPTIBLE INSTRUMENT AIR SUPPLY INBOARD CHECK VALVE A, B NA 2-RNA-V5000 2-RNA-SV-5261 LLRT CONNECTION A, B NA 2-RNA-V5001 2-RNA-SV-5262 LLRT CONNECTION A, B NA 2-TD-V2 TORUS DRAIN C NA TRM PCIV List Appendix D

Brunswick Unit 2 D-13 Revision No. 23 TRM Table 3.6.1.3-2 (Page 1 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S)

SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds)

AUTOMATIC ISOLATION GROUP 2-B21-F016 MAIN STEAM LINE DRAIN INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 1 2-B21-F019 MAIN STEAM LINE DRAIN OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 1 2-B21-F022A INBOARD MSIV A A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F022B INBOARD MSIV B A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F022C INBOARD MSIV C A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F022D INBOARD MSIV D A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F028A OUTBOARD MSIV A A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F028B OUTBOARD MSIV B A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F028C OUTBOARD MSIV C A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F028D OUTBOARD MSIV D A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F032A FEEDWATER SUPPLY LINE A ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-B21-F032B FEEDWATER SUPPLY LINE B ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-B32-F019 SAMPLE LINE INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 5 1 2-B32-F020 SAMPLE LINE OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 5 1 2-B32-V22 RECIRC PUMP 2A SEAL INJECTION A, B SR 3.6.1.3.4 (a) NA 2-B32-V30 RECIRC PUMP 2B SEAL INJECTION A, B SR 3.6.1.3.4 (a) NA 2-CAC-SV-1200B CAC-AT-1261 INBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (continued)

(a) Allowable Isolation Time specified in the Inservice Testing Program.

TRM PCIV List Appendix D

Brunswick Unit 2 D-14 Revision No. 49 TRM Table 3.6.1.3-2 (Page 2 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S)

SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds)

AUTOMATIC ISOLATION GROUP 2-CAC-SV-1205E CAC-AT-4409 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1209A CAC-AT-4409 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1209B CAC-AT-4409 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1211E CAC-AT-1262 INBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1211F CAC-AT-1262 INBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1213A CAC-AT-4409 TORUS INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1215E CAC-AT-4409 INBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1218A CAC-AT-4410 TORUS INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1225B COMMON INBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1227A CAC-AT-4410 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1227B CAC-AT-4410 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1227C CAC-AT-1260 INBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1227E CAC-AT-4410 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6

15 6 (b) (continued)

(a) Allowable Isolation Time specified in the Inservice Testing Program.

(b) The PCIV receives a Group 6 isolation signal for instrument protection. The PCIV is considered OPERABLE if it is capable of closing from the control room within the specified Allowable Isolation Time.

TRM PCIV List Appendix D

Brunswick Unit 2 D-15 Revision No. 49 TRM Table 3.6.1.3-2 (Page 3 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S)

SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds)

AUTOMATIC ISOLATION GROUP 2-CAC-SV-1231B CAC-AT-4410 INBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1260 CAC-AT-1260 OUTBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1261 CAC-AT-1261 OUTBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1262 CAC-AT-1262 OUTBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-3439 CAC-AT-1262 OUTBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-3440 COMMON OUTBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-4409-1 CAC-AT-4409 TORUS OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4409-2 CAC-AT-4409 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4409-3 CAC-AT-4409 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4409-4 CAC-AT-4409 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4410-1 CAC-AT-4410 TORUS OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4410-2 CAC-AT-4410 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4410-3 CAC-AT-4410 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4410-4 CAC-AT-4410 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4540 CAC-AT-4409 OUTBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4541 CAC-AT-4410 OUTBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) (continued)

(a) Allowable Isolation Time specified in the Inservice Testing Program.

(b) The PCIV receives a Group 6 isolation signal for instrument protection. The PCIV is considered OPERABLE if it is capable of closing from the control room within the specified Allowable Isolation Time.

TRM PCIV List Appendix D

Brunswick Unit 2 D-16 Revision No. 23 TRM Table 3.6.1.3-2 (Page 4 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S)

SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds)

AUTOMATIC ISOLATION GROUP 2-CAC-V4 INBOARD PRIMARY CONTAINMENT N2 INERTING INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V5 SUPPRESSION POOL N2 INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V6 DRYWELL N2 INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V7 INBOARD SUPPRESSION POOL PURGE EXHAUST A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V8 OUTBOARD SUPPRESSION POOL PURGE EXHAUST A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V9 INBOARD DRYWELL PURGE EXHAUST A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V10 OUTBOARD DRYWELL PURGE EXHAUST A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V15 PRIMARY CONTAINMENT PURGE AIR INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V22 SUPPRESSION POOL 2" EXHAUST A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V23 DRYWELL 2" EXHAUST A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V49 DRYWELL HEAD INBOARD PURGE EXHAUST A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V50 DRYWELL HEAD OUTBOARD PURGE EXHAUST A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V55 DRYWELL CAD N2 INJECTION SOLENOID A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V56 DRYWELL CAD N2 INJECTION SOLENOID A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V160 SUPPRESSION POOL CAD N2 INJECTION INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V161 DRYWELL CAD N2 INJECTION INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V162 SUPPRESSION POOL CAD N2 INJECTION INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V163 DRYWELL CAD N2 INJECTION INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V172 SUPPRESSION POOL PURGE EXHAUST SOLENOID A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V216 HARDENED WETWELL VENT OUTBOARD ISOLATION

A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (continued)

TRM PCIV List Appendix D

Brunswick Unit 2 D-17 Revision No. 59 TRM Table 3.6.1.3-2 (Page 5 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S)

SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds)

AUTOMATIC ISOLATION GROUP 2-C51-J004A A TIP BALL VALVE AND SHEAR VALVE ASSEMBLY A, B SR 3.6.1.3.3 SR 3.6.1.3.4 SR 3.6.1.3.6 SR 3.6.1.3.8 (a) 2 2-C51-J004B B TIP BALL VALVE AND SHEAR VALVE ASSEMBLY A, B SR 3.6.1.3.3 SR 3.6.1.3.4 SR 3.6.1.3.6 SR 3.6.1.3.8 (a) 2 2-C51-J004C C TIP BALL VALVE AND SHEAR VALVE ASSEMBLY A, B SR 3.6.1.3.3 SR 3.6.1.3.4 SR 3.6.1.3.6 SR 3.6.1.3.8 (a) 2 2-C51-J004D D TIP BALL VALVE AND SHEAR VALVE ASSEMBLY A, B SR 3.6.1.3.3 SR 3.6.1.3.4 SR 3.6.1.3.6 SR 3.6.1.3.8 (a) 2 2-E11-F007A MINIMUM FLOW BYPASS VALVE A TO SUPPRESSION POOL C SR 3.6.1.3.4 (a) NA 2-E11-F007B MINIMUM FLOW BYPASS VALVE B TO SUPPRESSION POOL C SR 3.6.1.3.4 (a) NA 2-E11-F008 SHUTDOWN COOLING OUTBOARD SUCTION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 43 8(c) 2-E11-F009 SHUTDOWN COOLING INBOARD SUCTION THROTTLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 8(c) 2-E11-F011A RHR HEAT EXCHANGER 2A DRAIN TO SUPPRESSION POOL C SR 3.6.1.3.4 (a) NA 2-E11-F011B RHR HEAT EXCHANGER 2B DRAIN TO SUPPRESSION POOL C SR 3.6.1.3.4 (a) NA 2-E11-F015A LPCI A INBOARD INJECTION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 8(c) 2-E11-F015B LPCI B INBOARD INJECTION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 8(c) 2-E11-F016A DRYWELL SPRAY A OUTBOARD ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F016B DRYWELL SPRAY B OUTBOARD ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F017A LPCI A OUTBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E11-F017B LPCI B OUTBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E11-F020A RHR PUMP 2A AND 2C TORUS SUCTION C SR 3.6.1.3.4 (a) NA (continued)

(a) Allowable Isolation Time specified in the Inservice Testing Program.

(c) Except as noted in TS Table 3.3.6.1-1 (Note (d)), these PCIVs are also required to be OPERABLE in MODES 4 and 5 to support the OPERABILITY of Function 6.b of TS Table 3.3.6.1-1.

TRM PCIV List Appendix D

Brunswick Unit 2 D-18 Revision No. 23 TRM Table 3.6.1.3-2 (Page 6 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S)

SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds)

AUTOMATIC ISOLATION GROUP 2-E11-F020B RHR PUMP 2B AND 2D TORUS SUCTION C SR 3.6.1.3.4 (a) NA 2-E11-F021A DRYWELL SPRAY A INBOARD ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F021B DRYWELL SPRAY B INBOARD ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F024A SUPPRESSION POOL COOLING A ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F024B SUPPRESSION POOL COOLING B ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F027A SUPPRESSION POOL SPRAY A ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F027B SUPPRESSION POOL SPRAY B ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F028A SUPPRESSION POOL SPRAY A ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F028B SUPPRESSION POOL SPRAY B ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F103A RHR HEAT EXCHANGER 2A OUTBOARD VENT C SR 3.6.1.3.4 (a) NA 2-E11-F103B RHR HEAT EXCHANGER 2B OUTBOARD VENT C SR 3.6.1.3.4 (a) NA (continued)

(a) Allowable Isolation Time specified in the Inservice Testing Program.

TRM PCIV List Appendix D

Brunswick Unit 2 D-19 Revision No. 23 TRM Table 3.6.1.3-2 (Page 7 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S)

SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds)

AUTOMATIC ISOLATION GROUP 2-E21-F001A SUPPRESSION POOL A SUCTION C SR 3.6.1.3.4 (a) NA 2-E21-F001B SUPPRESSION POOL B SUCTION C SR 3.6.1.3.4 (a) NA 2-E21-F004A CORE SPRAY PUMP 2A OUTBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E21-F004B CORE SPRAY PUMP 2B OUTBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E21-F005A CORE SPRAY PUMP 2A INBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E21-F005B CORE SPRAY PUMP 2B INBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E21-F015A CORE SPRAY FULL FLOW TEST BYPASS C SR 3.6.1.3.4 (a) NA 2-E21-F015B CORE SPRAY FULL FLOW TEST BYPASS C SR 3.6.1.3.4 (a) NA 2-E21-F031A CORE SPRAY MINIMUM FLOW BYPASS C SR 3.6.1.3.4 (a) NA 2-E21-F031B CORE SPRAY MINIMUM FLOW BYPASS C SR 3.6.1.3.4 (a) NA 2-E41-F002 HPCI STEAM SUPPLY INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 50 4 2-E41-F003 HPCI STEAM SUPPLY OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 50 4 2-E41-F006 HPCI INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E41-F012 HPCI MINIMUM FLOW BYPASS TO SUPPRESSION POOL C SR 3.6.1.3.4 20 NA 2-E41-F042 HPCI SUPPRESSION POOL SUCTION C SR 3.6.1.3.4 SR 3.6.1.3.6

80 4 (continued)

(a) Allowable Isolation Time specified in the Inservice Testing Program.

TRM PCIV List Appendix D

Brunswick Unit 2 D-20 Revision No. 23 TRM Table 3.6.1.3-2 (Page 8 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S)

SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds)

AUTOMATIC ISOLATION GROUP 2-E41-F075 HPCI TURBINE EXHAUST VACUUM BREAKER A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 7 2-E41-F079 HPCI TURBINE EXHAUST VACUUM BREAKER A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 7 2-E51-F007 RCIC STEAM SUPPLY INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 5 2-E51-F008 RCIC STEAM SUPPLY OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 5 2-E51-F013 RCIC INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E51-F019 RCIC MINIMUM FLOW BYPASS TO SUPPRESSION POOL C SR 3.6.1.3.4 (a) NA 2-E51-F031 RCIC SUPPRESSION POOL SUCTION C SR 3.6.1.3.4 SR 3.6.1.3.6 80 5 2-E51-F062 RCIC TURBINE EXHAUST VACUUM BREAKER A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 9 2-E51-F066 RCIC TURBINE EXHAUST VACUUM BREAKER A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 9 2-G16-F003 DRYWELL FLOOR DRAIN INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 20 2 2-G16-F004 DRYWELL FLOOR DRAIN OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 20 2 2-G16-F019 DRYWELL EQUIPMENT DRAIN INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 20 2 2-G16-F020 DRYWELL EQUIPMENT DRAIN OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 20 2 2-G31-F001 RWCU INLET INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 35 3 (e) 2-G31-F004 RWCU INLET OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 35 3 2-G31-F042 RWCU RETURN TO REACTOR A, B SR 3.6.1.3.4 (a) NA 2-RCC-SV-1222B RECIRC PUMP 2A COOLER OUTLET SAMPLE C SR 3.6.1.3.4 (a) NA (continued)

(a) Allowable Isolation Time specified in the Inservice Testing Program.

(e) Valve does not automatically close on an isolation signal associated with Function 5.f of TS Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation."

TRM PCIV List Appendix D

Brunswick Unit 2 D-21 Revision No. 24 TRM Table 3.6.1.3-2 (Page 9 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S)

SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds)

AUTOMATIC ISOLATION GROUP 2-RCC-SV-1222C RECIRC PUMP 2B COOLER OUTLET SAMPLE C SR 3.6.1.3.4 (a) NA 2-RCC-V28 RBCCW DRYWELL DISCHARGE HEADER ISOLATION C SR 3.6.1.3.4 (a) NA 2-RCC-V52 RBCCW DRYWELL SUPPLY HEADER ISOLATION C SR 3.6.1.3.4 (a) NA 2-RNA-SV-5251 BACKUP NITROGEN SUPPLY TO DRYWELL ISOLATION VALVE - DIVISION II C SR 3.6.1.3.4 (a) NA 2-RNA-SV-5253 BACKUP NITROGEN SUPPLY TO DRYWELL ISOLATION VALVE - DIVISION I C SR 3.6.1.3.4 (a) NA 2-RNA-SV-5261 NON-INTERRUPTIBLE REACTOR INSTRUMENT AIR SOLENOID A, B SR 3.6.1.3.4 SR 3.6.1.3.6 (a) 10 2-RNA-SV-5262 NON-INTERRUPTIBLE REACTOR INSTRUMENT AIR SOLENOID A, B SR 3.6.1.3.4 SR 3.6.1.3.6 (a) 10 2-RXS-SV-4186 LIQUID SAMPLE RETURN INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-RXS-SV-4187 LIQUID SAMPLE RETURN OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-RXS-SV-4188 GAS SAMPLE RETURN INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-RXS-SV-4189 GAS SAMPLE RETURN OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (a) Allowable Isolation Time specified in the Inservice Testing Program.

Brunswick Unit 2 Revision No. 23 APPENDIX E SECONDARY CONTAINMENT ISOLATION DAMPER (SCID) LIST

TRM SCID List Appendix E

Brunswick Unit 2 E-1 Revision No. 23 APPENDIX E SECONDARY CONTAINMENT ISOLATION DAMPER (SCID) LIST

PURPOSE This appendix provides a table to aid in complying with the requirements of Technical

Specification (TS) 3.6.4.2, "Secondary Containment Isolation Dampers (SCIDs)."

TRM Table 3.6.4.2-1, "Secondary Containment Automatic Isolation Dampers," provides a list of

the SCIDs that are required to automatically close on a secondary containment isolation signal.

TRM Table 3.6.4.2-1 includes a reference to the applicable TS Surveillance Requirements and

the required Allowable Isolation Times.

TRM SCID List Appendix E

Brunswick Unit 2 E-2 Revision No. 23 TRM Table 3.6.4.2-1 (Page 1 of 1) Secondary Containment Automatic Isolation Dampers DAMPER NUMBER DAMPER DESCRIPTION SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds) 2-VA-2A-BFIV-RB Reactor Building Ventilation Supply Inboard Isolation SR 3.6.4.2.1 SR 3.6.4.2.2 4 2-VA-2B-BFIV-RB Reactor Building Ventilation Supply Outboard Isolation SR 3.6.4.2.1 SR 3.6.4.2.2 4 2-VA-2C-BFIV-RB Reactor Building Ventilation Exhaust Inboard Isolation SR 3.6.4.2.1 SR 3.6.4.2.2 4 2-VA-2D-BFIV-RB Reactor Building Ventilation Exhaust Outboard Isolation SR 3.6.4.2.1 SR 3.6.4.2.2 4 2-VA-2A-BFV-RB Purge System Exhaust Outlet Valve SR 3.6.4.2.1 SR 3.6.4.2.2 (a) 2-VA-2I-BFV-RB Purge System Inlet Valve SR 3.6.4.2.1 SR 3.6.4.2.2 (a)

(a) Allowable Isolation Time specified in the Inservice Testing Program.

Brunswick Unit 2 Revision No. 23 APPENDIX F SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)

TRM SFDP Appendix F SFDP Definitions Brunswick Unit 2 SFDP-1 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)

1.0 SFDP DEFINITIONS

Loss of Safety Inability to accomplish a Safety Function as defined Function(LOSF) in this program. See the definition of Safety Function below.

For the performance of a Safety Function Determination (SFD), identifies specific conditions which constitute a

LOSF. This attachment includes any Technical Specification (TS)

Condition which requires entry into LCO 3.0.3 or a unit shutdown. Safety Function A TS function that must be performed to mitigate the consequences of an accident, transient, or special event as

defined in the current BNP licensing basis, including TS functions

that have been deemed important contributors to risk reduction.

Support Feature A TS system/subsystem/component which supports a required TS system(s) in order for the TS syst em to perform its required Safety Function.

Supported Feature A TS system/subsystem/component that performs a specific Safety Function.

TRM SFDP Appendix F Cascading Requirements Brunswick Unit 2 SFDP-2 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)

2.0 CASCADING

REQUIREMENTS

2.1 Technical

Specification (TS) LCO 3.0.2 requires that the TS ACTIONS (Conditions and Required Actions) be entered and performed when an

applicable LCO is not met, except as provided in LCO 3.0.5 and LCO 3.0.6. 2.2 TS LCO 3.0.6 is applicable in instances when a Supported Feature LCO is not met solely due to a Support Feature LCO not being met.

of this program provides a limited cross reference of

Support Feature TS and associated Supported Feature TS. In the event

LCO 3.0.6 is applicable, the following should be considered:

2.2.1 The applicable Conditions for the inoperable Support Feature shall be entered and the associated Required Actions

performed. Document the Required Actions in accordance

with Procedure No. OOI-01.08, "Control of Equipment and

System Status." 2.2.2 --------------------------------------NOTE-------------------------------------

For the purposes of this program, the single failure criterion is

not required when determining OPERABILITY of the

Supported Feature(s).

The inoperable Support Feature may impact multiple Supported Features and the inoperable Support Feature may

be several support levels up from the Supported Feature. As

such, OPERABILITY Determinations may be required to

determine if an inoperable Support Feature does result in one

or more Supported Features becoming inoperable. If an

OPERABILITY Determination is required, an Engineering

Service Request should be generated in accordance with

Procedure No. EGR-NGGC-0005, "Engineering Service

Requests." Attachments 2 and 3 of this program and

Procedure No. OI-18, "Definition of Instrument Channels and

Trip Systems for Selected Instruments," may be used as an

aid in the OPERABILITY Determinations.

(continued)

TRM SFDP Appendix F Cascading Requirements Brunswick Unit 2 SFDP-3 Revision No. 23

2.0 CASCADING

REQUIREMENTS (continued)

2.2.3 If the inoperable Support Feature results in a Supported Feature(s) becoming inoperable, then the Supported

Feature(s) shall be considered inoperable. 2.2.4 The applicable TS Conditions for the inoperable Supported Feature(s) shall be entered and the associated Required

Actions performed (i.e., "cascade" to the Supported Feature

TS ACTIONS) when: 2.2.4.1 The inoperability is not associated with a Support Feature TS but does impact OPERABILITY of a

Supported Feature(s); 2.2.4.2 The TS Required Actions for the inoperable Support Feature direct that the inoperable Supported

Feature(s) be declared inoperable; or 2.2.4.3 Any Note to the TS Required Actions for the inoperable Support Feature that direct the Conditions

and Required Actions for the inoperable Supported

Feature(s) be entered. Document the Required Actions per Procedure No. 0OI-01.08.

2.3 -------------------------------------------NOTE----------------------------------------------

If only one Support Feature is inoperable and no other TS

system/subsystem/component is inoperable, the Safety Function

Determination (SFD) may be delayed until a subsequent inoperability

occurs.

Unless cascading to the Supported Feature TS ACTIONS is required (as described in Section 2.2.4 of this program), it is not required to enter the

TS ACTIONS for the inoperable Supported Feature(s). If the TS

ACTIONS for the inoperable Supported Feature(s) are not entered, then a

SFD shall be performed. 2.4 A SFD includes performing cross division checks in order to determine if redundant features are capable of performing their required Safety

Function. Figure 2-1 of this program provides guidance on the process of

performing a SFD. Refer to the SFDP Bases for SFD evaluation

examples.

(continued)

TRM SFDP Appendix F Cascading Requirements Brunswick Unit 2 SFDP-4 Revision No. 23

2.0 CASCADING

REQUIREMENTS (continued)

2.5 If the SFD indicates that a LOSF exists, then the appropriate Conditions in the TS where the LOSF has occurred shall be entered and the

associated Required Actions performed. Attachment 4 of this program

should be used to determine if a LOSF exists.

TRM SFDP Appendix F Cascading Requirements Brunswick Unit 2 SFDP-5 Revision No. 23

Figure 2-1 (page 1 of 1)

Safety Function Determination Program Flowchart

TRM SFDP Appendix F Maximum Completion Time Brunswick Unit 2 SFDP-6 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)

3.0 MAXIMUM

COMPLETION TIME

3.1 A Supported Feature(s) made inoperable by Support Feature inoperabilities shall be restored to OPERABLE status within the Maximum

Completion Time. The Maximum Completion Time, for the purposes of

this program, is the Completion Time specified in the Technical

Specifications (TS) for restoring the first inoperable Support Feature to OPERABLE status plus the Completion Time specified in the TS for restoring the Supported Feature to OPERABLE status. 3.2 If the Supported Feature is not restored to OPERABLE status (by restoring the Supported Feature and all associated Support Features to

OPERABLE status) within the Maximum Completion Time, the associated

Condition for the inoperable Supported Feature's Completion Time not

being met shall be entered and the Required Actions shall be performed.

TRM SFDP Appendix F SFD Review Brunswick Unit 2 SFDP-7 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)

4.0 SAFETY

FUNCTION DETERMINATION (SFD) REVIEW

4.1 A review of the SFD shall be performed after every subsequent inoperability. If a review of the SFD indicates a LOSF has occurred, then

the appropriate Conditions in the TS where the LOSF has occurred shall

be entered and the associated Required Actions performed.

TRM SFDP Appendix F Attachment 1 Brunswick Unit 2 SFDP-8 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)

Support Feature/Supported Feature TS Cross Reference - Attachment 1

Support System TS

Number Support System Supported System TS

Number Supported System 3.3.5.1 ECCS Instrumentation 3.5.1 3.5.2 3.6.2.3 3.8.1 3.8.2 ECCS - Operating

ECCS - Shutdown

RHR Suppression Pool Cooling

AC Sources - Operating

AC Sources - Shutdown 3.3.5.2 RCIC Instrumentation 3.5.3 RCIC System 3.3.6.1 Primary Containment Isolation Instrumentation 3.1.7 3.6.1.3 3.6.1.5 SLC System

PCIVs Reactor Building-to-Suppression

Chamber Vacuum Breakers 3.3.6.2 Secondary Containment Isolation Instrumentation 3.6.4.2 3.6.4.3 SCIDs SGT System 3.3.7.1 CREV System Instrumentation 3.7.3 CREV System 3.3.8.1 LOP Instrumentation 3.3.5.1 3.7.2 3.8.1 3.8.2 ECCS Instrumentation

SW System and UHS

AC Sources - Operating

AC Sources - Shutdown 3.6.1.5 Reactor Building-to-Suppression Chamber

Vacuum Breakers 3.6.1.1 Primary Containment 3.6.1.6 Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.1 Primary Containment (continued)

TRM SFDP Appendix F Attachment 1 Brunswick Unit 2 SFDP-9 Revision No. 23 (continued)

Support System TS

Number Support System Supported System TS

Number Supported System 3.6.4.2 SCIDs 3.6.4.1 Secondary Containment 3.6.4.3 SGT System 3.6.4.1 Secondary Containment 3.7.1 RHRSW System 3.4.7 3.6.2.3 RHR SDC System - Hot Shutdown

RHR Suppression Pool Cooling 3.7.2 SW System and UHS 3.5.1 3.4.7 3.6.2.3 ECCS - Operating

RHR SDC System - Hot Shutdown

RHR Suppression Pool Cooling 3.8.1 AC Sources - Operating 3.8.7 Distribution Systems - Operating (AC portion only) 3.8.2 AC Sources - Shutdown 3.8.8 Distribution Systems - Shutdown (AC portion only) 3.8.4 DC Sources - Operating 3.8.7 Distribution Systems - Operating (DC portion only) 3.8.5 DC Sources - Shutdown 3.8.8 Distribution Systems - Shutdown (DC portion only)

(continued)

TRM SFDP Appendix F Attachment 1 Brunswick Unit 2 SFDP-10 Revision No. 23 (continued)

Support System TS

Number Support System Supported System TS

Number Supported System 3.8.7 (AC only)

Distribution Systems -

Operating (AC portion

only) provides a

listing of equipment

supported by AC

distribution.

provides a

listing of electrical power

supplies supporting

PCIVs. 3.1.7 3.3.3.1 3.3.3.2

3.3.6.1

3.4.5

3.4.7 3.5.1 3.5.3 3.6.1.3 3.6.2.3 3.6.4.2 3.6.4.3 3.7.1 3.7.2 3.7.3 3.7.4 3.8.1 3.8.3 3.8.4 SLC System

PAM Instrumentation

Remote Shutdown Monitoring

Instrumentation

Primary Containment Isolation

Instrumentation

RCS Leakage Detection

Instrumentation

RHR SDC System - Hot Shutdown

ECCS - Operating

RCIC System

PCIVs RHR Suppression Pool Cooling

SCIDs SGT System

RHRSW System

SW System and UHS

CREV System

Control Building AC System

AC Sources - Operating

Diesel Fuel Oil

DC Sources - Operating (continued)

TRM SFDP Appendix F Attachment 1 Brunswick Unit 2 SFDP-11 Revision No. 23 (continued)

Support System TS

Number Support System Supported System TS

Number Supported System 3.8.7 (DC only)

Distribution Systems - Operating (DC portion only) provides a listing of

electrical power supplies

supporting PCIVs.

3.3.3.1 3.3.3.2 3.3.5.1 3.3.5.2

3.3.6.1

3.3.8.1 3.4.7

3.5.1 3.5.3 3.6.1.3 3.6.2.3

3.7.1 3.7.2 3.8.1 PAM Instrumentation

Remote Shutdown System

ECCS Instrumentation

RCIC System

Instrumentation

Primary Containment

Isolation Instrumentation

LOP Instrumentation

RHR SDC System - Hot

Shutdown ECCS - Operating

RCIC System

PCIVs RHR Suppression Pool

Cooling RHRSW System

SW System and UHS

AC Sources - Operating

(continued)

TRM SFDP Appendix F Attachment 1 Brunswick Unit 2 SFDP-12 Revision No. 23 (continued)

Support System TS

Number Support System Supported System TS

Number Supported System 3.8.8 (AC only)

Distribution Systems - Shutdown (AC portion only) provides a listing of

equipment supported by AC

distribution.

provides a listing of

electrical power supplies

supporting PCIVs.

3.3.6.1

3.4.8

3.5.2 3.6.1.3 3.6.4.2 3.6.4.3 3.7.3 3.7.4

3.8.2 3.8.3 3.8.5 3.9.7

3.9.8 Primary

Containment

Isolation Instrumentation

RHR SDC System - Cold

Shutdown ECCS - Shutdown

PCIVs SCIDs SGT System

CREV System

Control Building AC

System AC Sources - Shutdown

Diesel Fuel Oil

DC Sources - Shutdown

RHR - High Water Level

RHR - Low Water Level

(continued)

TRM SFDP Appendix F Attachment 1 Brunswick Unit 2 SFDP-13 Revision No. 23 (continued)

Support System TS

Number Support System Supported System TS

Number Supported System 3.8.8 (DC only)

Distribution Systems - Shutdown (DC portion only) provides a listing of

electrical power supplies

supporting PCIVs.

3.3.5.1 3.3.6.1

3.3.8.1 3.4.8

3.5.2 3.6.1.3 3.8.2 3.9.7 3.9.8 ECCS Instrumentation

Primary Containment

Isolation Instrumentation

LOP Instrumentation

RHR SDC System - Cold

Shutdown ECCS - Shutdown

PCIVs AC Sources - Shutdown

RHR - High Water Level

RHR - Low Water Level

TRM SFDP Appendix F Attachment 2 Brunswick Unit 2 SFDP-14 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)

Unit 2 AC Electrical Supported Equipment - Attachment 2

SUPPORT SYSTEM AC ELECTRICAL LOAD GROUPS LCO 3.8.7, 3.8.8 LCO SUPPORTED SUBSYSTEM E1 E2 E3 E4 3.1.7 2A SLC X 2B SLC X 3.3.3.1 2A PAM INST. (FUNC. 1)

X 1 X 1 2B PAM INST. (FUNC. 1)

X 1 X 1 2A PAM INST. (FUNC. 2)

X 2B PAM INST. (FUNC. 2)

X 1 2A PAM INST. (FUNC. 3-7,9,10)

X 2B PAM INST. (FUNC. 3-7,9,10)

X PAM PCIV POSITION (FUNC. 8) 3 X X X X 3.3.3.2 REMOTE SHUTDOWN MON. INST.

X 3.3.6.1 2A HPCI/RCIC INST.

X 2B HPCI/RCIC INST.

X 3.4.5 U2 RCS LEAKAGE DETECTION X X 3.4.7, 3.4.8 2A RHR SDC X 2 X 3.9.7, 3.9.8 2B RHR SDC X 2 X 2C RHR SDC X X 2 2D RHR SDC X 1 X 3.5.1, 3.5.3 U2 HPCI X 1 X 1 U2 RCIC X 1 2A RECIRC. DISC. VALVE X 2B RECIRC. DISC. VALVE X 3.5.1, 3.5.2 2A LPCI SUBSYSTEM X X 2 2A LPCI PUMP X 2C LPCI PUMP X 2B LPCI SUBSYSTEM X X 2 2B LPCI PUMP X 2D LPCI PUMP X 2A CORE SPRAY SUBSYSTEM X 2B CORE SPRAY SUBSYSTEM X 3.6.1.3 U2 PCIVs (MOVs) 3 X X X X 1 Provides one of two power supplies. If the affected subsystem(s)/component(s) is not capable of performing its required function, the subsystem or instrument channel is inoperable. An OPERABILITY determination may be required.

2 Provides power to an MOV. If the affected supported subsystem(s)/component(s) is not capable of performing its required function, the subsystem is inoperable. An OPERABILITY determination may be required.

3 See Attachment 3 for specific valves and indication affected.

(continued)

TRM SFDP Appendix F Attachment 2 Brunswick Unit 2 SFDP-15 Revision No. 23 (continued)

SUPPORT SYSTEM AC ELECTRICAL LOAD GROUPS LCO 3.8.7, 3.8.8 LCO SUPPORTED SUBSYSTEM E1 E2 E3 E4 3.6.2.3 2A SP COOL (A or C) X X 2B SP COOL (B or D)

X X 3.6.4.2 U2 SCIDs X X 3.6.4.3 2A SGT TRAIN X 2B SGT TRAIN X 3.7.1 2A RHRSW LOOP (A or C)

X X 2B RHRSW LOOP (B or D)

X X 3.7.2 U2 NSW X X U2 CSW X X X U1 NSW X X 3.7.3 A CREV FAN X B CREV FAN X 3.7.4 1D CONTROL ROOM AC X 2D CONTROL ROOM AC X 2E CONTROL ROOM AC X 3.8.1, 3.8.2

3.8.3 DG 1 X DG 2 X DG 3 X DG 4 X 3.8.4, 3.8.5 U-2 DIV I DC X U-2 DIV II DC X U-1 DIV I DC X U-1 DIV II DC X

TRM SFDP Appendix F Attachment 3 Brunswick Unit 2 SFDP-16 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)

Unit 2 TS LCO 3.6.1.3 "PCIVs" Electrical Power Supporting PCIVs - Attachment 3

SUPPORT SYSTEM ELECTRICAL POWER DISTRIBUTION SYSTEM LCO 3.8.7, 3.8.8 AC 480 VAC EMERGENCY BUSES 250 VDC SYSTEM PCIV - MOTOR OPERATED E-5 E-6 E-7 E-8 DIV I DIV II FW 2-B21-F032A X 2-B21-F032B X MAIN STEAM 2-B21-F016 X 2-B21-F019 X RESIDUAL HEAT REMOVAL 2-E11-F007A X 2-E11-F007B X 2-E11-F008 X 2-E11-F009 X 2-E11-F011A X 2-E11-F011B X 2-E11-F015A X 2-E11-F015B X 2-E11-F016A X 2-E11-F016B X 2-E11-F017A X 2-E11-F017B X 2-E11-F020A X 2-E11-F020B X 2-E11-F021A X 2-E11-F021B X 2-E11-F024A X 2-E11-F024B X 2-E11-F027A X 2-E11-F027B X 2-E11-F028A X 2-E11-F028B X (continued)

TRM SFDP Appendix F Attachment 3 Brunswick Unit 2 SFDP-17 Revision No. 23 (continued)

SUPPORT SYSTEM ELECTRICAL POWER DISTRIBUTION SYSTEM LCO 3.8.7, 3.8.8 AC 480 VAC EMERGENCY BUSES 250 VDC SYSTEM PCIV - MOTOR OPERATED E-5 E-6 E-7 E-8 DIV I DIV II RESIDUAL HEAT REMOVAL 2-E11-F103A X 2-E11-F103B X RWCU 2-G31-F001 X 2-G31-F004 X 2-G31-F042 X REACTOR RECIRC. 2-B32-V22 X 2-B32-V30 X RCIC 2-E51-F007 X 2-E51-F008 X 2-E51-F013 X 2-E51-F019 X 2-E51-F031 X 2-E51-F062 X 2-E51-F066 X CORE SPRAY 2-E21-F001A X 2-E21-F001B X 2-E21-F004A X 2-E21-F004B X 2-E21-F005A X 2-E21-F005B X 2-E21-F015A X 2-E21-F015B X 2-E21-F031A X 2-E21-F031B X (continued)

TRM SFDP Appendix F Attachment 3 Brunswick Unit 2 SFDP-18 Revision No. 23 (continued)

SUPPORT SYSTEM ELECTRICAL POWER DISTRIBUTION SYSTEM LCO 3.8.7, 3.8.8 AC 480 VAC EMERGENCY BUSES 250 VDC SYSTEM PCIV - MOTOR OPERATED E-5 E-6 E-7 E-8 DIV I DIV II HPCI 2-E41-F002 X 2-E41-F003 X 2-E41-F006 X 2-E41-F012 X 2-E41-F042 X 2-E41-F075 X 2-E41-F079 X CAC 2-CAC-V22 X 2-CAC-V23 X RBCCW 2-RCC-V28 X 2-RCC-V52 X

TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-19 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)

LOSF Table - Attachment 4

NOTE -----------------------------------------------------------

In addition to the TS system being a Supported Feature, the TS systems denoted with an asterisk are also Support Features. ------------------------------------------------------------------------------------------------------------------------------- LCO No. TECHNICAL SPECIFICATION SECTION

3.1.7 Standby

Liquid Control (SLC) System Two SLC subsystems inoperable. 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation For each Function, a loss of all required channels. 3.3.3.2 Remote Shutdown System For each Function (listed in Tech. Spec. Bases B 3.3.3.2), a loss of the

required channel. 3.3.4.1 ATWS-RPT Instrumentation For each Function, a loss of both channels in a trip system OR the

inability of a Recirc. pump to trip on reactor LL2 or reactor high pressure. *3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation For each Function, a loss of initiation capability as a result of a loss of one

or more required channels. *3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation 1. For Function 1, a loss of initiation capability as a result of a loss of two or more required channels. 2. For Function 2, a loss of one required channel. 3. For Function 3, a loss of both required channels. *3.3.6.1 Primary Containment Isolation Instrumentation For each Function, loss of all required channels in a trip system such that the associated Function cannot be accomplished.

(continued)

TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-20 Revision No. 23 (continued)

3.3.8.1 Loss of Power (LOP) Instrumentation For each Function, the loss of one or more channels on a 4.16 kV

emergency bus. *3.4.5 RCS Leakage Detection Instrumentation Loss of the Floor Monitoring Systems and the Primary Containment

Atmospheric Gaseous Monitoring System. 3.4.7 RHR Shutdown Cooling System-Hot Shutdown Both required SDC subsystems inoperable, Recirc. pumps not in operation, and no alternate method of decay heat removal. 3.4.8 RHR Shutdown Cooling System-Cold Shutdown Both required SDC subsystems inoperable, Recirc. pumps not in operation, and no alternate method of decay heat removal.

3.5.1 ECCS-Operating 1. Two or more required ADS valves inoperable. OR

2. HPCI and RCIC inoperable.

OR

3. HPCI and two or more required ADS valves inoperable. OR

4. Three or more low pressure ECCS pumps (LPCI and/or Core Spray (CS)) inoperable. OR

5. The following combinations of two or more low pressure ECCS injection/spray subsystems inoperable:

a. One CS subsystem and one LPCI subsystem (except one inoperable LPCI pump in the LPCI subsystem). b. Two CS subsystems.

c. Two LPCI subsystems (except one inoperable LPCI pump in each subsystem).

(continued)

TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-21 Revision No. 23 (continued)

3.5.2 ECCS-Shutdown Both required low pressure ECCS injection/spray subsystems inoperable. 3.5.3 RCIC System RCIC and HPCI inoperable. 3.6.1.1 Primary Containment 1. Determination that a breach in Primary Containment exists such that leakage exceeds the limit specified in the Primary

Containment Leakage Rate Testing Program. OR

2. Drywell to suppression chamber differential pressure decreases

> 0.25 inch of water gauge per minute. *3.6.1.3 Primary Containment Isolation Valves (PCIVs) 1. For penetrations with two PCIVs, two valves inoperable on a single penetration and the penetration is not isolated. OR

2. For penetrations with one PCIV, one valve inoperable on a single penetration and the penetration is not isolated. 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling (SPC)

Two RHR SPC subsystems inoperable. 3.6.4.1 Secondary Containment 1. An equipment hatch or combination of hatches that results in a breach of Secondary Containment. OR

2. Both SGT subsystems inoperable such that neither subsystem can draw and maintain 0.25" vacuum on Secondary Containment in accordance with SR 3.6.4.1.3.

(continued)

TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-22 Revision No. 23 (continued)

3.6.4.2 Secondary Containment Isolation Dampers (SCIDs)

Two dampers inoperable on a single penetration and the penetration is

not isolated. 3.6.4.3 Standby Gas Treatment (SGT) System Both SGT subsystems inoperable. *3.7.1 Residual Heat Removal Service Water (RHRSW) System 1. One RHRSW pump inoperable in each RHRSW loop.

OR

2. Both RHRSW subsystems inoperable.

OR

3. All four RHRSW pumps inoperable. *3.7.2 Service Water (SW) System and Ultimate Heat Sink (UHS) 1. Two required unit CSW pumps and one or both unit NSW pumps inoperable. OR

2. Two or more required site NSW pumps. OR

3. SW System inoperable such that SW cannot be provided to the vital header, RHR SW header, or the DGs. OR

4. SW System inoperable such that SW cannot be provided to the A vital header and the B RHRSW header. OR

5. SW System inoperable such that SW cannot be provided to the B vital header and the A RHRSW header. OR

6. UHS > 92

°F or level less than -6 ft. mean sea level.

(continued)

TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-23 Revision No. 23 (continued)

3.7.3 Control

Room Emergency Ventilation (CREV) System 1. Two CREV subsystems inoperable for reasons other than CREV System instrumentation. OR

2. Two CREV subsystems inoperable due to CREV System instrumentation and no CREV subsystems operating in the

radiation protection mode. *3.7.4 Control Room Air Conditioning (AC) System Three Control Room AC subsystems inoperable. *3.8.1 AC Sources-Operating 1. Two or more DGs inoperable.

OR

2. Two offsite circuits inoperable to two or more 4.16 kV emergency buses. OR

3. One DG inoperable and two or more 4.16 kV offsite circuits inoperable. OR

4. Two or more DGs inoperable and one or more 4.16 kV offsite circuits inoperable. *3.8.2 AC Sources-Shutdown All offsite circuits and the DG associated with a 4.16 kV emergency bus

required by LCO 3.8.8 are inoperable.

(continued)

TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-24 Revision No. 23 (continued)

3.8.3 Diesel Fuel Oil 1. One or more DGs with day fuel oil tank level < 22,650 gal. and main fuel oil storage tank level < 20,850 gal. per DG. OR

2. One or more DGs with day fuel oil tank level < 17,000 gal.

OR

3. One or more DGs with main fuel oil storage tank level < 13,900 gal. per DG. *3.8.4 DC Sources-Operating Two or more DC divisions (Unit 1 and 2) inoperable. *3.8.5 DC Sources-Shutdown A DC subsystem (Unit 1 or 2) required to support the shutdown unit is inoperable.

(continued)

TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-25 Revision No. 23 (continued)

3.8.7 Distribution Systems-Operating 1. Two or more 4.16 kV emergency buses are inoperable.

OR

2. A Division I 480 VAC emergency bus is inoperable concurrent with a Division II 4.16 kV emergency bus inoperability. OR

3. A Division II 480 VAC emergency bus is inoperable concurrent with a Division I 4.16 kV emergency bus inoperability. OR

4. Two or more DC divisions (Unit 1 and 2) inoperable.

OR

5. Any emergency bus (4.16 kV or 480 VAC) is inoperable concurrent with any other emergency bus (4.16 kV or 480 VAC)

inoperability such that one of the following occurs on the subject

unit:

a. Loss of SDC capability when no recirc pumps are running.

b. Two or more ECCS subsystems are inoperable.

c. Two or more RHR SPC subsystems are inoperable.

d. Both SGT subsystems are inoperable.

e. Both RHRSW subsystems are inoperable.

f. Two or more DGs are inoperable.

g. SW System is inoperable due to a loss of two or more required NSW pumps. h. Two CREV subsystems are inoperable.

i. Three Control Room AC subsystems inoperable.

(continued)

TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-26 Revision No. 23 (continued)

3.8.8 Distribution Systems-Shutdown 1. Any 4.16 kV emergency bus that is required to support the shutdown unit is inoperable. OR

2. Any 480 VAC emergency bus that is required to support the shutdown unit is inoperable. OR

3. A DC subsystem (Unit 1 or 2) that is required to support the shutdown unit is inoperable. 3.9.7 Residual Heat Removal (RHR)-High Water Level One required SDC subsystem inoperable and no alternate method of decay heat removal. 3.9.8 Residual Heat Removal (RHR)-Low Water Level Two required SDC subsystems inoperable and no alternate method of decay heat removal.

TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-1 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP) BASES

Program Use and Application

PURPOSE AND The purpose of a Safety Function Determination (SFD) evaluation is to SCOPE detect a loss of a required Safety Function associated with systems in the Technical Specifications (TS) which could exist when an inoperable

Support Feature(s) results in a Supported Feature(s) becoming

inoperable.

TS 5.5.11, "Safety Function Determination Program (SFDP)," requires

implementation of a SFDP and specifies the provisions which must be

included in the SFDP.

The purpose of the SFDP is to ensure that SFD evaluations:

1. are performed when required;

2. include the required provisions in order to detect a LOSF;

3. ensure that the unit is placed in a safe condition if a LOSF exists; and 4. limit the time that inoperable Support Features result in Supported Features being inoperable.

One example of the Support/Supported Feature relationship is the HPCI

System initiation instrumentation/logic. This instrumentation logic is a

Support Feature for the HPCI System. The HPCI System is the

Supported Feature. Another example of the Support/Supported Feature

relationship is the DC Electrical Distribution System. This Support

Feature is several support "levels" from the Supported Feature that

performs the primary Safety Function. The DC Electrical Distribution

System is a Support Feature for the Loss of Power (LOP) Instrumentation

since DC electrical distribution subs ystems provide DC control power to the LOP instrumentation functions. The LOP Instrumentation is, in turn, the Support Feature for the AC Electrical Distribution System since the

LOP instruments support the 4.16 kV emergency buses. Finally, the AC

Electrical Distribution System supports the Emergency Core Cooling

Systems (ECCS) since the AC emergency buses supply power to the low

pressure ECCS subsystems. Note that each support level has a

corresponding Safety Function. For example, the Safety (continued)

TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-2 Revision No. 23 Program Use and Application

PURPOSE AND Function of the LOP Instrumentation is to monitor and actuate, if required, SCOPE to ensure the AC Electrical Distribution System is powered (from offsite (continued) or onsite AC power sources) during assumed accidents or transients.

The Support/Supported Feature relationship is generally identified in the

associated TS Bases. Attachment 1 also provides a limited listing of

Support/Supported Feature relationships.

TS LCO 3.0.6 establishes an exception to TS LCO 3.0.2 for Support

Features that have an LCO specified in the TS. This exception is

provided because TS LCO 3.0.2 would require that the Conditions and

Required Actions of the associated inoperable Supported Feature TS be

entered solely due to the inoperability of Support Features. This

exception is justified because the remedial actions that are required to

ensure the plant is maintained in a safe condition are specified in the

Support Feature's TS ACTIONS. The TS Required Actions may include

entering the Supported Feature's Conditions and Required Actions. TS

LCO 3.0.6 specifies when a SFD must be performed.

Upon entry into TS LCO 3.0.6, the SFDP shall be used to determine if

LOSF exists. Additionally, other limitations, remedial actions, or compensatory actions may be identified as a result of the Support

Feature inoperability.

When a Support Feature is inoperable and there is an LCO specified for

the feature in TS, the Supported Feature(s) LCO may be not met as a

result of the Support Feature inoperability. However, it is not necessary

to enter the Supported Features' TS ACTIONS unless directed to do so

by the Support Feature's TS ACTIONS provided the associated Safety

Function is retained.

Definitions in the SFDP are initially capitalized throughout the SFDP and

Bases. (continued)

TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-3 Revision No. 23 Program Use and Application (continued)

CASCADING A SFD is only required during specific instances when TS LCO 3.0.6 REQUIREMENTS is entered and two or more Support or Supported Features are inoperable. Therefore, it is important to know when TS LCO 3.0.6 is

applicable. TS LCO 3.0.6 is applicable in instances when a Supported

Feature LCO is not met solely due to a Support Feature LCO not being

met (i.e., a Supported Feature is inoperable due to a Support Feature

being inoperable).

Per TS LCO 3.0.2, the applicable Conditions for the inoperable Support

Feature shall be entered and the associated Required Actions performed.

The TS ACTIONS are documented in accordance with Procedure No.

0OI-01.08, "Control of Equipment and System Status."

It may not be obvious that an associated Supported Feature is inoperable

when a Support Feature is inoperable. Therefore, an OPERABILITY

Determination should be performed to determine if the inoperable Support

Feature does result in a Supported Feature becoming inoperable. If the

inoperable Support Feature does not result in any Supported Features

becoming inoperable, then TS LCO 3.0.6 is not applicable and a SFD is

not required. However, if the inoperable Support Feature does result in a

Supported Feature(s) becoming inoperable, then the Supported

Feature(s) shall be considered inoperable and LCO 3.0.6 applies.

Typically, TS LCO 3.0.6 does not require "cascading" to the associated

Supported Feature TS since the Support Feature TS ACTIONS are

considered sufficient (e.g., the Support Feature allowable out of service

time is the same or more restrictive than the allowable out of service time

of the Supported Features). In some cases, the TS ACTIONS of the

Support Feature require cascading to the Supported Feature TS

ACTIONS. Cascading to the Supported Feature TS ACTIONS is required

if the feature is not controlled by a TS (e.g., ECCS room coolers) since

the TS definition of OPERABILITY applies and the requirements of

LCO 3.0.6 are not applicable to non-TS support features. Cascading to

the Supported Feature TS ACTIONS is also required if the Support

Feature TS ACTIONS require cascading. If cascading is required, a SFD

is not required.

(continued)

TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-4 Revision No. 23 Program Use and Application

CASCADING Unless cascading is required, TS LCO 3.0.6 does not require entry into REQUIREMENTS the TS ACTIONS for the inoperable Supported Feature(s) unless a LOSF (continued) exists. Therefore, a SFD must be performed to ensure Safety Function is maintained. The TS ACTIONS of the inoperable Supported Feature may

be entered even if the Safety Function is retained. However, this is a

conservative decision. If a decision is made to cascade to the Supported

Feature(s) TS, a SFD evaluation is not required.

The SFDP requires cross division checks to identify a LOSF for those

Support Features that support safety systems. The SFD evaluation

should include an administrative cross divisional check to verify that the

Supported Features of the redundant OPERABLE Support Features are

OPERABLE, thereby ensuring Safety Function is retained. The

evaluation should also include a conclusion as to the status of the Safety

Function (i.e., Safety Function maintained or lost). The SFD should be

performed by a licensed Senior Reactor Operator or another qualified

member of the technical staff. If this SFD evaluation determines that a

LOSF exists, the appropriate Conditions and Required Actions of the TS

in which the LOSF exists are required to be entered. Attachment 4 of the

SFDP provides all known combinations of Supported Feature

inoperabilities where a LOSF exists.

In addition, since the TS ACTIONS associated with the Support Feature

restricts plant operation, the single failure criterion does not have to be

considered when determining OPERABILITY of the Supported

Feature(s).

MAXIMUM A Supported Feature(s) made inoperable by Support Feature COMPLETION inoperabilities may only remain inoperable for a limited period of time TIME (without entering the Supported Feature TS ACTIONS). This time limit is defined as the Maximum Completion Time. The Maximum Completion

Time for restoring the Supported Feature(s) to OPERABLE status is the

Completion Time specified in TS for restoring the first inoperable Support Feature to OPERABLE status plus the Completion Time specified in TS for restoring the inoperable Supported Feature to OPERABLE status.

This Maximum Completion Time requirement includes restoring all Support Features to OPERABLE status.

(continued)

TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-5 Revision No. 23 Program Use and Application

MAXIMUM The Maximum Completion Time establishes a limit on the maximum COMPLETION time allowed for any combination of Support Features and Supported TIME Features being inoperable during a single contiguous occurrence of (continued) failing to meet the Suppor ted Feature's TS LCO. This "Maximum Completion Time" philosophy is similar to that of TS Section 1.3, Completion Times.

(continued)

TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-6 Revision No. 23 Program Use and Application

MAXIMUM COMPLETION EXAMPLE 3.1-1 TIME (continued)

Assume that Systems A and B are TS systems and they Support System C. The Completion Times for restoring the systems to OPERABLE status

are; 3 days for System A, 7 days for System B, and 7 days for System C.

If System A becomes inoperable and makes System C inoperable, then

the maximum Completion Time for restoring System C to OPERABLE

status is 10 days (3 days plus 7 days).

(continued)

Maximum Com p letion Time 3 da y s 7 da y s 3 da y s + 7 da y s = 10 da y sSystem A Da y 1 Da y 3 S y stem C Da y 10 Da y 3 S y stem B Da y 3 Da y 10 TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-7 Revision No. 23 Program Use and Application

MAXIMUM Example 3.1-1 (continued)

COMPLETION TIME If System C should then become inoperable for reasons other than the support system being inoperable on Day 3 (time from System A

inoperability; System A is restored to OPERABLE status later on Day 3),

then System C must be restored to OPERABLE status by Day 10 (within

7 days). Subsequently, if System B should become inoperable on Day 8 (time from System A inoperability), t hen System B must also be restored

to OPERABLE status by Day 10 (within 2 days instead of 7 days) in order

to restore System C to OPERABLE status within its 10-day Maximum

Completion Time.

The Maximum Completion Time is considered an acceptable limitation on

the potential to fail to meet the Supported Feature's TS LCO indefinitely.

If System C is not restored to OPERABLE status within 10 days (by

restoring Systems A and B to OPERABLE status), then the Condition in

TS for System C which states, "Required Action and associated

Completion Time not met," shall be entered and the associated Required

Actions shall be performed.

SFD For every subsequent inoperability, a review of the SFD is required to REVIEW ensure that the SFD remains valid and a LOSF has not occurred. This includes inoperabilities as a result of surveillance testing or maintenance.

This also includes inoperabilities as a result of declaring a Supported Feature inoperable per TS ACTIONS.

A complete re-evaluation of all redundant supported subsystems and

associated support subsystems should be performed to ensure the Safety

Function is maintained with the additional inoperabilities.

TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-8 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP) BASES

Safety Function Determination (SFD) Evaluation Examples

SFD The plant is operating in MODE 3 with reactor pressure at < 75 psig. The EVALUATION "A" RHR-SDC subsystem is in operation and the "C" and "D" RHR-SDC EXAMPLE 1 subsystems are OPERABLE. The "B" RHR pump has been removed from service for maintenance on the motor. Condition A of both

TS 3.6.2.3, "RHR Suppression Pool Cooling," and TS 3.5.1, "ECCS-

Operating," were entered at 1500 on 1/1/98.

At 2100 on 1/2/98, the breaker for the "C" RHRSW pump tripped on

overload. TS 3.7.1, "RHRSW System," Condition A was entered. TS 3.6.2.3 ACTIONS do not yet have to be entered per LCO 3.0.6.

The following is the SFD for the Supported Features:

Although the "C" RHR-SDC subsystem became inoperable at 2100 on 1/2/98, the "D" RHR-SDC subsystem is OPERABLE.

Therefore, LCO 3.4.7, "RHR Shutdown Cooling System - Hot

Shutdown," is met and LCO 3.0.6 is not applicable to TS 3.4.7.

The safety analysis for RHR-SPC requires 8000 gpm service water flow to ensure an RHR-SPC subsystem can perform its

Safety Function. As a result, LCO 3.6.2.3 is not met due to the "A" RHR-SPC subsystem inoperable (one RHRSW pump inoperable).

However, TS 3.6.2.3 ACTIONS do not yet have to be entered per

LCO 3.0.6.

Per LCO 3.0.6 and TS 5.5.11, a SFD must be performed and would reveal that the "B" RHR-SPC subsystem has been

inoperable since 1500 on 1/1/98. Since the "A" RHR-SPC

subsystem is inoperable concurrent with the "B" RHR-SPC

subsystem, a LOSF exists for TS 3.6.2.3.

==

Conclusion:==

TS 3.6.2.3 Condition A should be continued for the "A" RHR-SPC subsystem inoperable and TS 3.6.2.3 Condition B should be

entered immediately upon discovery of the LOSF.

(continued)

TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-9 Revision No. 23 SFD Evaluation Examples

SFD Assuming the "B" RHR pump is restored to OPERABLE status by 1500 EVALUATION on 1/8/98 and the "C" RHRSW pump is restored to OPERABLE status by EXAMPLE 1 2100 on 1/16/98, the Maximum Completion Time for restoring the "A" (continued) RHR-SPC subsystem to OPERABLE status following subsequent contiguous inoperabilities (including all Support Features) is 2100 on

1/23/98; 14 days (TS 3.7.1 Required Action A.1) plus 7 days (TS 3.6.2.3

Required Action A.1).

SFD Unit 2 is operating at 100% power. A portion of SR 3.3.5.2.5 is being EVALUATION performed to verify Relay K-52 is OPERABLE. TS 3.3.5.2, "RCIC System EXAMPLE 2 Instrumentation," Condition C was entered at 0300 on 4/2/98 due to the testing. Six hours has elapsed as allowed by Note 2 to the Surveillance

Requirements. At 2000 on 4/2/98, the 2A DC Switchboard de-energizes

due to an internal electrical short. TS 3.8.7, "Distribution Systems-

Operating," Condition C is entered.

The following is the SFD for the Supported Features:

The HPCI System is inoperable due to the loss of power to much of the system. However, TS 3.5.1, "ECCS-Operating," ACTIONS

do not have to be entered per LCO 3.0.6.

The Bases for TS 3.5.3, "RCIC System," states that the function of the RCIC System is to provide core cooling during a loss of

feedwater event. Since the RCIC System can still perform its

required function in the above condition (RCIC high water level trip

inoperable), it can be considered OPERABLE and a LOSF has not

occurred.

==

Conclusion:==

Since a LOSF has not occurred, entry into TS 3.5.1 or TS 3.5.3 ACTIONS is not required at this time. However, if SR 3.3.5.2.5 is

not satisfactorily completed by 0300 on 4/3/98, TS 3.3.5.2

Required Action E.1 requires declaring the RCIC System

inoperable and TS 3.5.3 Condition A must be entered.

(continued)

TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-10 Revision No. 23 SFD Evaluation Examples

SFD A review of the SFD (refer to Attachment 4 of the SFDP) will show that EVALUATION the HPCI and RCIC Systems are both inoperable. Therefore, TS 3.5.1 EXAMPLE 2 Condition I must be entered and TS 3.5.3 Condition B must be entered (continued) upon discovery that both systems are inoperable.

Assuming that Relay K-52 is demonstrated OPERABLE by 0300 on

4/3/98 and the 2A DC Switchboard is restored to OPERABLE status by

2000 on 4/9/98, the Maximum Completion Time for restoring the HPCI

System to OPERABLE status following subsequent contiguous

inoperabilities (including all Support Features) is 2000 on 4/23/98; 7 days (TS 3.8.7 Required Action C.1) plus 14 days (TS 3.5.1 Required Action

D.2). SFD Unit 1 is in MODE 5 and Unit 2 is operating at 100% power. At 0900 on EVALUATION 10/2/98, Diesel Generator (DG)

1 was removed from service to perform EXAMPLE 3 preventative maintenance and Unit 2 TS 3.8.1, "AC Sources-Operating," Condition C is entered. Unit 1 LCO 3.8.2, "AC Sources-Shutdown," is

met. During the performance of SR 3.3.5.1.2 on Unit 2, it was discovered

that improper grounding resulted in a failure of Relays K-11B and K-10B

on Unit 2 core spray logic. I&C reports that the "B" core spray logic is

inoperable and the "A" core spray logic is still OPERABLE. The "B" core

spray logic (TS 3.3.5.1, "ECCS Instrumentation," Functions 1.a, 1.b, and

1.c) is declared inoperable at 1500 on 10/4/98.

Unit 2 TS 3.3.5.1 Conditions B and C are entered at this time. Required

Actions B.1 and C.1 are not applicable at this time since "A" core spray

initiation capability is still available. Required Actions B.3 and C.2 allow

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to fix the relays before declaring the Supported Features

inoperable. TS 3.5.1, "ECCS-Operating," ACTIONS do not yet have to be

entered per LCO 3.0.6.

The following is the SFD for the Supported Features:

Although core spray Relay K-11B is not available to start the emergency diesel generators, Relay K-11A is still OPERABLE.

Therefore, DGs 2,3, and 4 will start if required and are still

considered OPERABLE and a LOSF has not occurred.

(continued)

TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-11 Revision No. 23 SFD Evaluation Examples

SFD * ----------------------------------------NOTE---------------------------------------- EVALUATION The DGs cannot withstand a single failure (i.e., failure of core EXAMPLE 3 spray Relay K-11A), however, plant operation is limited by (continued) TS 3.3.5.1 ACTIONS.

The 2A LPCI subsystem is still OPERABLE since offsite power is available to the E1 4.16 kV bus. However, the Completion Time

for TS 3.8.1 Required Action C.2 begins at 1500 on 10/4/98 since

E1 supplies power to the 2A LPCI subsystem (2C LPCI pump and

LPCI injection valves) and 2A LPCI is redundant to the 2B core

spray subsystem. Since only one low pressure ECCS subsystem is inoperable a LOSF has not occurred.

==

Conclusion:==

Since all ECCS will initiate except 2B core spray, the Safety Function is maintained and TS 3.5.1 ACTIONS do not have to be

entered at this time. However, at 1900 on 10/4/98, TS 3.8.1

Required Action C.2 requires declaring the 2A LPCI subsystem

inoperable and TS 3.5.1 Condition A must be entered. A review of

the SFD at this time (refer to Attachment 4 of the SFDP) will show

that the 2A LPCI subsystem and 2B core spray subsystem are

both inoperable. Therefore, TS 3.5.1 Condition J must be entered

upon discovery that both low pressure ECCS subsystems are

inoperable. In addition, TS 3.5.1 Condition A should be continued

and TS 3.5.1 Condition B should be entered for the 2B core spray

subsystem inoperable. Assuming DG#1 is restored to OPERABLE status prior to completion of the shutdown required by LCO 3.0.3 and the 2B

core spray logic is restored to OPERABLE status by 1500 10/5/98, the Maximum Completion Time for restoring the 2B core spray

subsystem to OPERABLE status following subsequent contiguous

inoperabilities (including all Support Features) is 1500 on 10/12/98; 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (TS 3.3.5.1 Required Action C.2) plus 7 days (TS 3.5.1 Required Action A.1).

(continued)

TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-12 Revision No. 23 SFD Evaluation Examples (continued)

SFD A 480 VAC emergency bus (E8) indicates a ground fault at 1300 on EVALUATION 7/2/98. Further investigation reveals that, although all E8 loads seem to EXAMPLE 4 be operating normally, a high impedance ground fault has developed on the E8 emergency bus (cause unknown). Engineering has been

contacted to provide technical support and perform an OPERABILITY

Determination.

Unit 2 is operating at 100% power. At 2300 on 7/5/98, the control power

transformer fuse fails in the 2A SGT fan motor control circuit.

Maintenance reports that the failing of the fuse damaged the fuse holder

and it may take 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to correct the problem. All secondary

containment isolation instrumentation functions are declared inoperable

for the 2A SGT subsystem and TS 3.3.6.2, "Secondary Containment

Isolation Instrumentation," Condition A is entered. TS 3.6.4.3, "SGT

System," ACTIONS do not yet have to be entered per LCO 3.0.6.

Engineering reports at 0900 on 7/6/98 that the margin in the AC

Distribution Voltage Study shows that the high impedance fault results in

E8 being inoperable. TS 3.8.7, "Distribution Systems - Operating,"

Condition A is entered at this time. TS 3.6.4.3 ACTIONS do not yet have

to be entered per LCO 3.0.6.

The following is the SFD for the Supported Features:

LCO 3.6.4.2, "SCIDs," is still met since the failure of the secondary containment isolation instrumentation functions only

affects the 2A SGT subsystem and is independent of the

secondary containment isolation dampers.

Improper voltage (as a result of the ground) on the E8 results in the 2B SGT subsystem becoming inoperable. Per LCO 3.0.6 and

TS 5.5.11, a SFD must be performed and would reveal that the 2A

SGT subsystem has been inoperable since 2300 on 7/5/98. Since

the 2A SGT subsystem is inoperable concurrent with the 2B SGT

subsystem, a loss of LOSF exists for TS 3.6.4.3.

==

Conclusion:==

TS 3.6.4.3 Conditions A and B should be entered immediately upon discovery of the LOSF.

(continued)

TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-13 Revision No. 23 SFD Evaluation Examples

SFD Assuming either E8 is restored to OPERABLE status or the 2A SGT fan EVALUATION is restored to OPERABLE status prior to the completion of the plant EXAMPLE 4 shutdown required by TS3.6.4.3 Condition B and both E8 and 2A SGT (continued) instrumentation are restored to OPERABLE status within their associated Completion Times, the Maximum Completion Time for restoring the 2A

SGT subsystem to OPERABLE status following subsequent contiguous

inoperabilities (including all Support Features) is 1100 on 7/13/98; 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (TS 3.3.6.2 Required Action A.1) plus 7 days (TS 3.6.4.3

Required Action A.1). The Maximum Completion Time for restoring the

2B SGT subsystem to OPERABLE status following subsequent

contiguous inoperabilities (including all Support Features) is 1700 on 7/13/98; 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months (TS 3.8.7 Required Action A.1) plus 7 days (TS 3.6.4.3

Required Action A.1).

TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-14 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP) BASES Attachments

ATTACHMENT 1 This attachment is an aid which identifies the Supported Features associated with each Support Feature Technical Specification (TS). The

Table includes the TS number and title of the support system and

supported systems so the appropriate TS and Bases may be reviewed.

The Table of Support vs. Supported Features does not infer that a

Support Feature inoperability results in all Supported Features becoming

inoperable. The Table only provides Supported Feature TS that may be

affected. To ensure the list is user friendly, the list is minimized to the

extent practical. Therefore, features that are not in TS are not included in since TS LCO 3.0.6 does not apply to these features (e.g.,

ECCS room cooler subsystems). Additionally, Support Features that

exclusively support only one Supported Feature and contain TS

ACTIONS that require cascading to the Supported Feature TS ACTIONS

are generally not included in Attachment 1 (e.g., Control Rod

Accumulators). Support Features that are "failsafe" upon loss of power (i.e., loss of power results in the feature automatically performing its

required Safety Function), are also not listed since the Safety Function is

performed upon loss of power (e.g., loss of DC power to RPS electric

power monitoring assemblies).

ATTACHMENT 2 This attachment provides a list of all TS equipment affected by a loss of a single emergency load group (i.e., a loss of a single 4.16 kV emergency

bus) except equipment that is "failsafe." If a supported subsystem is "failsafe" upon loss of AC power, the supported subsystem is not listed in

. Additionally, this Attachment is limited to redundant

supported subsystems and does not provide detail as to which component has lost power. Unless otherwise noted, an "X" in the support

subsystem column indicates the supported subsystem is inoperable.

ATTACHMENT 3 This attachment provides a list of all the motor-operated primary containment isolation valves (PCIVs) and their associated power

supplies. If a motor-operated valve is open and loses power, it cannot

provide the required isolation function.

(continued)

TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-15 Revision No. 23 Attachments

ATTACHMENT 3 This attachment is an aid which identifies all of the affected PCIVs.

(continued) If the PCIV is closed and loses power, inherently the Safety Function is maintained. Some of the PCIVs have a normal and alternate power

supply. As noted, PCIVs are considered OPERABLE provided power is

available to the motor-operator.

ATTACHMENT 4 This attachment provides all known combinations of inoperabilities where LOSF exists. The attachment includes combinations of inoperabilities

that require a plant shutdown or entry into TS LCO 3.0.3 per the

Supported Feature TS.

Additionally, this attachment only includes loss of function for systems

used to perform Safety Function Determinations. If a TS system is

supported by a system that is not a TS system, the non-TS support feature is not included in the attachment because TS LCO 3.0.6 is not

applicable for this case. If a TS system is supported by another TS

system but the TS ACTIONS for the inoperable TS Support Feature

require "cascading" into the TS ACTIONS for the Supported Feature TS, then a LOSF for this Supported Feature is not included in the attachment

because TS LCO 3.0.6 is not applicable for this case.

Several TS LCOs do not require all installed features (e.g., only six of

seven ADS valves are required to be OPERABLE to meet LCO 3.5.1). As

such, the word required is underlined in Attachment 4 to indicate only

those features required to meet the LCO. Since the NRC has previously

approved the TS, continued operation with plant degradations within the

bounds of the Supported Feature TS is allowed. Continued operation

with plant degradations outside the bounds of the Supported Feature TS

is not allowed. Therefore, if the combination of inoperabilities results in a

LOSF as defined in Attachment 4 (i.e., continued plant operation is not

allowed by the Supported Feature TS), the appropriate Conditions of the

Supported Feature TS must be entered and the Required Actions

performed.

ML18249A160

Text

1.1 Definitions

1.2 Logical

1.3 Completion

1.4 Frequency

3.0 TECHNICAL

3.3 CONTROL

3.4 ACCIDENT

3.7 AUTOMATIC

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3.3.2 Actions

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3.4.2 Details