Text

Technical Requirements Manual, Revision 66
	ML18249A160
Person / Time
Site:	Brunswick
Issue date:	08/13/2018
From:	; Duke Energy Progress
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML18249A165	List: ML18249A126; ML18249A128; ML18249A129; ML18249A130; ML18249A131; ML18249A133; ML18249A134; ML18249A135; ML18249A140; ML18249A142; ML18249A143; ML18249A145; ML18249A146; ML18249A147; ML18249A148; ML18249A149; ML18249A150; ML18249A151; ML18249A153; ML18249A154; ML18249A155; ML18249A159; RA-18-0004, Duke Energy Transmittal of Topical Report DUKE-QAPD-001-A, Amendment 43; RA-18-0131, Technical Requirements Manual, Revision 66;
References
	RA-18-0131
	Download: ML18249A160 (293)
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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 Page No. Revision No. 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)

Brunswick Unit 2 LOEP-1 Revision No. 66

LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENTS MANUAL Page No. Revision No. 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 (continued)

Brunswick Unit 2 LOEP-2 Revision No. 66

LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENTS MANUAL Page No. Revision No. Page No. Revision No.

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)

Brunswick Unit 2 LOEP-3 Revision No. 66

LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENTS MANUAL Page No. Revision No. Page No. Revision No.

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)

Brunswick Unit 2 LOEP-4 Revision No. 65

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

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 0.0-1 Revision No. 55

Matrix of Responsible Group(s) for TRM Sections, associated Bases, and Appendices RESPONSIBLE SECTION TITLE GROUP 3.0 Technical Requirements Manual Specifications (TRM) and Test Licensing /

Requirements (TR) Applicability 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 BESS - ELEC/I&C Instrumentation 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 Ventilation (CREV) System - Smoke BESS - MECH Protection Mode 3.19 Control Room Emergency Ventilation (CREV) System - Chlorine BESS - MECH Protection Mode 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 0.0-2 Revision No. 66

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 Tank Radioactivity Monitoring E&RC Program 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 BESS - ELEC/I&C Setpoints List APPENDIX C Technical Requirements Manual Instrumentation Numbers and BESS - ELEC/I&C Trip Setpoints List 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 0.0-3 Revision No. 45

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 OPERABILITYSHUTDOWN ....................... 3.16-1 3.17 SERVICE WATER SYSTEMSHUTDOWN OPERATIONS ....................... 3.17-1 (continued)

Brunswick Unit 2 0.0-4 Revision No. 23

TABLE OF CONTENTS (continued) 3.18 CONTROL ROOM EMERGENCY VENTILATION (CREV)

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

SYSTEMCHLORINE 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 TRAVELSPENT 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)

Brunswick Unit 2 0.0-5 Revision No. 23

TABLE OF CONTENTS (continued)

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 OPERABILITYSHUTDOWN ................... B 3.16-1 B 3.17 SERVICE WATER SYSTEMSHUTDOWN OPERATIONS ................... B 3.17-1 B 3.18 CONTROL ROOM EMERGENCY VENTILATION (CREV)

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

SYSTEMCHLORINE 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 TRAVELSPENT 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)

Brunswick Unit 2 0.0-6 Revision No. 23

Definitions 1.1 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)

Brunswick Unit 2 1.1-1 Revision No. 23

Definitions 1.1 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.

OPERABLEOPERABILITY 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)

Brunswick Unit 2 1.1-2 Revision No. 23

Definitions 1.1 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.

Brunswick Unit 2 1.1-3 Revision No. 23

Logical Connectors 1.2 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)

Brunswick Unit 2 1.2-1 Revision No. 23

Logical Connectors 1.2 TRMS 1.2 Logical Connectors EXAMPLES EXAMPLE 1.2-1 (continued)

COMPENSATORY MEASURES REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE 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)

Brunswick Unit 2 1.2-2 Revision No. 23

Logical Connectors 1.2 TRMS 1.2 Logical Connectors EXAMPLES EXAMPLE 1.2-2 (continued)

COMPENSATORY MEASURES REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE 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.

Brunswick Unit 2 1.2-3 Revision No. 23

Completion Times 1.3 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 Specifications (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)

Brunswick Unit 2 1.3-1 Revision No. 23

Completion Times 1.3 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)

Brunswick Unit 2 1.3-2 Revision No. 23

Completion Times 1.3 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 REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory Measure and AND associated Completion B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Time not met.

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)

Brunswick Unit 2 1.3-3 Revision No. 23

Completion Times 1.3 TRMS 1.3 Completion Times EXAMPLES EXAMPLE 1.3-2 (continued)

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

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory Measure and AND associated Completion B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Time not met.

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)

Brunswick Unit 2 1.3-4 Revision No. 23

Completion Times 1.3 TRMS 1.3 Completion Times EXAMPLES EXAMPLE 1.3-3 (continued)

COMPENSATORY MEASURES REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. One Function X A.1 Restore 7 days subsystem Function X inoperable. subsystem to AND OPERABLE status. 10 days from discovery of failure to meet the TRMS B. One Function Y B.1 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem Function Y inoperable. subsystem to AND OPERABLE status. 10 days from discovery of failure to meet the TRMS C. One Function X C.1 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem Function X inoperable. subsystem to OPERABLE AND status.

One Function Y OR subsystem inoperable. C.2 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Function Y subsystem to OPERABLE status.

(continued)

Brunswick Unit 2 1.3-5 Revision No. 23

Completion Times 1.3 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)

Brunswick Unit 2 1.3-6 Revision No. 23

Completion Times 1.3 TRMS 1.3 Completion Times EXAMPLES EXAMPLE 1.3-4 (continued)

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

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory Measure and AND associated Completion B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Time not met.

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)

Brunswick Unit 2 1.3-7 Revision No. 23

Completion Times 1.3 TRMS 1.3 Completion Times EXAMPLES EXAMPLE 1.3-5 (continued)

COMPENSATORY MEASURES

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

Separate Condition entry is allowed for each inoperable valve.

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

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory Measure and AND associated Completion B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Time not met.

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)

Brunswick Unit 2 1.3-8 Revision No. 23

Completion Times 1.3 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 REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. One channel A.1 Perform Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months inoperable. TR 3.x.x.x.

OR A.2 Reduce 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months THERMAL POWER to 50% RTP.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory Measure and associated Completion Time not met.

(continued)

Brunswick Unit 2 1.3-9 Revision No. 23

Completion Times 1.3 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)

Brunswick Unit 2 1.3-10 Revision No. 23

Completion Times 1.3 TRMS 1.3 Completion Times EXAMPLES EXAMPLE 1.3-7 (continued)

COMPENSATORY MEASURES REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. One subsystem A.1 Verify affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. subsystem isolated. AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND A.2 Restore 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months subsystem to OPERABLE status.

B. Required B.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Compensatory Measure and AND associated Completion B.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Time not met.

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)

Brunswick Unit 2 1.3-11 Revision No. 23

Completion Times 1.3 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.

Brunswick Unit 2 1.3-12 Revision No. 23

Frequency 1.4 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)

Brunswick Unit 2 1.4-1 Revision No. 23

Frequency 1.4 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)

Brunswick Unit 2 1.4-2 Revision No. 23

Frequency 1.4 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)

Brunswick Unit 2 1.4-3 Revision No. 23

Frequency 1.4 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)

Brunswick Unit 2 1.4-4 Revision No. 23

Frequency 1.4 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 1.4-5 Revision No. 23

2.0 Not used.

Brunswick Unit 2 2.0-1 Revision No. 23

TRMS Applicability 3.0 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 service or declared inoperable to comply with COMPENSATORY MEASURES may be returned to service under administrative control solely to perform 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.

Brunswick Unit 2 3.0-1 Revision No. 23

TR Applicability 3.0 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)

Brunswick Unit 2 3.0-2 Revision No. 23

TR Applicability 3.0 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 TRMSs 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.

Brunswick Unit 2 3.0-3 Revision No. 23

Control Rod Drive Housing Support 3.1 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 REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. Control rod drive housing A.1 Be in MODE 3 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months support not in place.

AND A.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Brunswick Unit 2 3.1-1 Revision No. 23

Control Rod Drive Housing Support 3.1 TEST REQUIREMENTS TEST FREQUENCY TR 3.1.1 Verify the control rod drive housing support is in place Once prior to by inspection after reassembly. 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 3.1-2 Revision No. 23

3.2 Not used.

Brunswick Unit 2 3.2-1 Revision No. 23

Control Rod Block Instrumentation 3.3 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.

REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. --------------NOTE--------------- A.1 Restore channel(s) to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Only applicable for OPERABLE status.

Functions 1, 2 and 3.

One or more functions with one or more required channels inoperable.

B. One or more functions with B.1 Place one channel in trip. 1 hour`

control rod block capability not maintained.

OR Required Compensatory Measures and associated Completion Time of Condition A not met.

Brunswick Unit 2 3.3-1 Revision No. 23

Control Rod Block Instrumentation 3.3 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 Once within flow. 7 days after reaching equilibrium conditions following refueling outage (continued)

Brunswick Unit 2 3.3-2 Revision No. 23

Control Rod Block Instrumentation 3.3 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 Brunswick Unit 2 3.3-3 Revision No. 23

Control Rod Block Instrumentation 3.3 Table 3.3-1 (page 1 of 1)

Control Rod Block Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED TEST ALLOWABLE FUNCTION CONDITIONS CHANNELS REQUIREMENTS VALUE

1. Average Power Range Monitors

a. Upscale (Flow Biased) 1 3 TR 3.3.3 0.55W +

TR 3.3.4 55.0%RTP(a)

TR 3.3.5 and 109.3% RTP

b. Inoperative 1,2 3 TR 3.3.5 NA

c. Downscale 1 3 TR 3.3.5 1.1% APRM power

d. Upscale (Fixed) 2 3 TR 3.3.3 TR 3.3.5 14% RTP

2. Source Range Monitors

a. Detector Not Full In 2(b),5 2 TR 3.3.1 NA (c)

b. Upscale 2 ,5 2 TR 3.3.1 5x 105cps

c. Inoperative 2(c),5 2 TR 3.3.1 NA (b)

d. Downscale 2 ,5 2 TR 3.3.1 3 cps

3. Intermediate Range Monitors

a. Detector Not Full In 2,5 6 TR 3.3.1 NA

b. Upscale 2,5 6 TR 3.3.1 108/125 of full scale

c. Inoperable 2,5 6 TR 3.3.1 NA

d. Downscale 2(e),5 6 TR 3.3.1 3/125 of full scale (f)

4. Scram Discharge Volume Water LevelHigh 1,2,5 1(g) TR 3.3.2 73 gallons TR 3.3.3 (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) RemovalRefueling," or 3.10.6, "Multiple Control Rod WithdrawalRefueling."

(g) Signal is contained in Channel A logic only.

Brunswick Unit 2 3.3-4 Revision No. 36

Accident Monitoring Instrumentation 3.4 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.

REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. --------------NOTE--------------- A.1 Restore required channel 31 days Only applicable to to OPERABLE status.

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

One or more Functions with one required channel inoperable.

B. One or more Functions with B.1 Restore one required 7 days two required channels channel to OPERABLE inoperable. status.

OR

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

Only applicable to Functions 4 and 5.

One or more Functions with one required channel inoperable.

(continued)

Brunswick Unit 2 3.4-1 Revision No. 60

Accident Monitoring Instrumentation 3.4 COMPENSATORY MEASURES (continued)

REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME C. Required Compensatory C.1 Submit a Special Report to 14 days Measure and associated the NRC outlining the Completion Time not met. preplanned alternate monitoring method, the cause of the inoperability, and plans for restoring the instrumentation to OPERABLE status.

TEST REQUIREMENTS TEST FREQUENCY TR 3.4.1 Perform CHANNEL CHECK. 31 days TR 3.4.2 Perform CHANNEL CALIBRATION except for Drywell 24 months and Suppression Chamber H2 and O2 Analyzers.

TR 3.4.3 Perform CHANNEL CALIBRATION of the Drywell and 92 days Suppression Chamber H2 and O2 Analyzers.

Brunswick Unit 2 3.4-2 Revision No. 29

Accident Monitoring Instrumentation 3.4 Table 3.4-1 (page 1 of 1)

Accident Monitoring Instrumentation APPLICABLE MODES OR OTHER SPECIFIED REQUIRED FUNCTION CONDITIONS CHANNELS

1. Suppression Chamber 1,2 2 Atmosphere Temperature

2. Drywell Radiation 1,2,3 2

3. Safety/Relief Valve 1,2 1 per valve Position Indication

a. Primary-Sonic

b. Secondary-Temperature

4. Turbine Building 1,2,3 1 Ventilation Monitor

5. Offgas Stack 1,2,3 1 Ventilation Monitor

6. Drywell and Suppression 1,2 1 Chamber H2 Analyzer

7. Drywell and Suppression 1,2 1 Chamber O2 Analyzer Brunswick Unit 2 3.4-3 Revision No. 60

Chloride Intrusion Monitors 3.5 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.

REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. Three or four Functions with A.1 Sample one parameter 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months one or more required monitored by the channels inoperable. inoperable Function(s). AND Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months thereafter Brunswick Unit 2 3.5-1 Revision No. 32

Chloride Intrusion Monitors 3.5 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 Brunswick Unit 2 3.5-2 Revision No. 23

Chloride Intrusion Monitors 3.5 Table 3.5-1 (page 1 of 1)

Chloride Intrusion Monitors REQUIRED TEST ALLOWABLE FUNCTION CHANNELS REQUIREMENTS VALUE

1. Chloride Leak Detectors in 4 TR 3.5.1 2.0 mhos/cm the Condenser Hotwell TR 3.5.2 Outlet Headers TR 3.5.4

2. Chloride Leak Detector in 1 TR 3.5.1 the Condensate Pump TR 3.5.2 Discharge (Wide Range or TR 3.5.3 Narrow Range)

a. Wide Range 10 mhos/cm

b. Narrow Range 0.5 mhos/cm

3. Chloride Leak Detector in 1 TR 3.5.1 0.5 mhos/cm the Inlet to the Condensate TR 3.5.2 Filter Demineralizer TR 3.5.3

4. Chloride Leak Detector in 1 TR 3.5.1 0.5 mhos/cm the Inlet to the Deep Bed TR 3.5.2 Demineralizer TR 3.5.3 Brunswick Unit 2 3.5-3 Revision No. 23

Bus Power Monitors 3.6 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.

REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. One or more channels A.1 Verify bus power 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable. availability to the system's logic. AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter B. Required Compensatory B.1 Declare associated Immediately Measure and associated supported equipment Completion Time not met. inoperable.

Brunswick Unit 2 3.6-1 Revision No. 31

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

Bus Power Monitors 3.6 Table 3.6-1 (page 1 of 1)

Bus Power Monitors APPLICABLE MODES OR OTHER REQUIRED SPECIFIED CHANNELS FUNCTION CONDITIONS PER BUS

1. Core Spray System 1,2,3 1 Bus Power Monitor 4(a),5(a)

2. Low Pressure Coolant Injection (Residual 1,2,3 1 Heat Removal System) 4(a),5(a)

Bus Power Monitor

3. High Pressure Cooling Injection System Bus 1,2,3 1 Power Monitor

4. Automatic Depressurization System 1,2(a),3(a) 1 Bus Power Monitor

5. RCIC System 1,2,3 1 Bus Power Monitor (a) When associated subsystems are required to be OPERABLE.

Brunswick Unit 2 3.6-3 Revision No. 23

ADS Inhibit Switch 3.7 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 REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. One or both ADS Inhibit A.1 Place both ADS Inhibit 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Switches not in the Switches in the automatic automatic position. position.

AND A.2 Declare ADS inoperable. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B. One or both ADS Inhibit B.1 Declare ADS inoperable. 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Switch channels inoperable.

TEST REQUIREMENTS TEST FREQUENCY TR 3.7.1 Verify ADS Inhibit Switches are in the automatic 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months position.

TR 3.7.2 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months Brunswick Unit 2 3.7-1 Revision No. 23

Suppression Chamber Water Temperature 3.8 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 REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. One suppression chamber A.1 Restore channel to 7 days water temperature OPERABLE status.

instrumentation channel inoperable.

B. Two suppression chamber B.1 Restore one channel to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months water temperature OPERABLE status.

instrumentation channels inoperable.

C. Required Compensatory C.1 Verify suppression 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Measure and associated chamber water Completion Time not met. temperature is within AND required limits.

Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter Brunswick Unit 2 3.8-1 Revision No. 31

Suppression Chamber Water Temperature Instrumentation 3.8 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 24 months Value of the alarm shall be 95°F.

Brunswick Unit 2 3.8-2 Revision No. 23

Seismic Monitoring Instrumentation 3.9 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.

REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. One or more seismic A.1 Restore seismic 31 days monitoring instruments monitoring instrument to inoperable. OPERABLE status.

B. Required Compensatory B.1 Submit a Special Report to 14 days Measure A.1 and associated the NRC outlining the Completion Time not met. cause of the malfunction and plans for restoring the instrument to OPERABLE status.

C. --------------NOTE--------------- C.1 Restore seismic 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Required Compensatory monitoring instrument to Measures C.2 and C.3 shall OPERABLE status.

be completed whenever Condition C is entered. AND C.2 Perform TR 3.9.3. 10 days OBE exceedance light is energized. AND C.3 Submit a Special Report to 14 days 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.

Brunswick Unit 2 3.9-1 Revision No. 47

Seismic Monitoring Instrumentation 3.9 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 Brunswick Unit 2 3.9-2 Revision No. 47

Seismic Monitoring Instrumentation 3.9 Table 3.9-1 (page 1 of 1)

Seismic Monitoring Instrumentation INSTRUMENTS AND MEASUREMENT REQUIRED TEST SENSOR LOCATIONS RANGE INSTRUMENTS REQUIREMENTS

1. Passive Triaxial Peak Shock Recorders

a. Reactor Building 2-25 Hz 1 TR 3.9.3 Basement/Equipment Drain Tank (-17' level)

b. Reactor Building RHR 2-25 Hz 1 TR 3.9.3 Heat Exchanger Support

(+20' level)

c. Reactor Building 2-25 Hz 1 TR 3.9.3 Refueling Area (+117' level)

2. Active Triaxial Accelerometers 0-1.0g 1 TR 3.9.1

a. Reactor Building TR 3.9.2

(+894 level) TR 3.9.3 0-1.0g 1 TR 3.9.1

b. Reactor Building TR 3.9.2

(-17' level) TR 3.9.3

3. Active Seismic Recording System

a. Control Room 0-1.0g 1 TR 3.9.1 TR 3.9.2 TR 3.9.3 Brunswick Unit 2 3.9-3 Revision No. 47

Intake Canal High Water Level Instrumentation 3.10 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 REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. Intake canal high water level A.1 Verify intake canal water Immediately instrumentation inoperable. level is 17'6" mean sea level USGS datum. 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 Brunswick Unit 2 3.10-1 Revision No. 31

Primary Containment Isolation Instrumentation 3.11 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.

REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. One or more required A.1 ---------------NOTE------------

channels inoperable. -

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.

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

(continued)

Brunswick Unit 2 3.11-1 Revision No. 23

Primary Containment Isolation Instrumentation 3.11 COMPENSATORY MEASURES (continued)

REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME B. Required Compensatory B.1 Restore isolation 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Measure and associated capability.

Completion Time not met.

OR OR 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B.2.1 Prepare a plan to restore One or more functions with channel(s) to OPERABLE isolation capability not status and assign a maintained. responsible individual to ensure the restoration plan is carried out.

AND 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B.2.2 Initiate a condition report.

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 24 months simulated automatic operation.

Brunswick Unit 2 3.11-2 Revision No. 51

Primary Containment Isolation Instrumentation 3.11 Table 3.11-1 (page 1 of 1)

Primary Containment Isolation Instrumentation REQUIRED CHANNELS ALLOWABLE FUNCTION PER TRIP SYSTEM VALUE

1. Main Steam Line Tunnel Temperature 2(a) 197°F High (except for Main Steam Isolation Valve Pit instruments)

2. Turbine Building Area TemperatureHigh 4(b) 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.

Brunswick Unit 2 3.11-3 Revision No. 51

CREV System Instrumentation 3.12 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.

REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. One or both Chlorine A.1 Restore detector(s) to 7 days Isolation Functions with one OPERABLE status.

chlorine detector inoperable in one or both associated trip subsystems.

B. Required Compensatory B.1 Place the CREV System in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Measure and associated the chlorine protection Completion Time of mode of operation.

Condition A not met.

C. One or both Chlorine C.1 Place the CREV System in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Isolation Functions with two the chlorine protection chlorine detectors mode of operation.

inoperable in one or both associated trip subsystems.

(continued)

Brunswick Unit 2 3.12-1 Revision No. 23

CREV System Instrumentation 3.12 COMPENSATORY MEASURES (continued)

REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME D. One Control Building Intake D.1 Restore detector(s) to 7 days Air Duct Detector Inoperable OPERABLE status.

E. Required Compensatory E.1 Place CREV System in the 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Measure and associated radiation/smoke protection Completion Time of mode of operation.

Condition D not met.

F. Both Control Building Intake F.1 Place the CREV System in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months Air Duct Detectors the radiation/smoke Inoperable protection mode of operation.

Brunswick Unit 2 3.12-2 Revision No. 57

CREV System Instrumentation 3.12 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 Brunswick Unit 2 3.12-3 Revision No. 23

CREV System Instrumentation 3.12 Table 3.12-1 (page 1 of 1)

CREV System Instrumentation FUNCTION APPLICABLE REQUIRED TEST ALLOWABLE MODES OR DETECTORS REQUIREMENTS VALUE OTHER PER TRIP SPECIFIED SYSTEM CONDITIONS

1. Chlorine Isolation (b)

a. Control Building (a) 4 TR 3.12.1 5 ppm Air Intake (Local) TR 3.12.3 (b)

b. Chlorine Tank Car (a) 4 TR 3.12.1 5 ppm Area (Remote) TR 3.12.3

2. Control Room Envelope Smoke Protection

a. Control Building Intake Air Duct 1,2,3,4 1 TR 3.12.2 NA (c)

Smoke Detectors 5, (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.

Brunswick Unit 2 3.12-4 Revision No. 57

RCS Chemistry 3.13 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 REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. Conductivity greater than A.1 Verify by administrative Immediately the limit of Table 3.13-1 but means that operation

< 10mhos/cm at 25°C in under this condition shall MODE 1, 2, or 3. not exceed 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per year.

OR AND Chloride concentration greater than the limit of A.2 ---------------NOTE------------

Table 3.13-1 but < 0.5 ppm -

in MODE 1, 2, or 3. TRMS 3.0.4 is not applicable.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Restore chemistry parameter(s) to within limit(s).

B. Required Compensatory B.1 Submit a Special Report to 14 days Measure A.1 and associated the NRC outlining the Completion Time not met. cause of the non-compliance, plans for restoring the parameter to within limit, and the impact of the non-compliance on RCS integrity.

(continued)

Brunswick Unit 2 3.13-1 Revision No. 23

RCS Chemistry 3.13 COMPENSATORY MEASURES (continued)

REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME C. Required Compensatory C.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Measure A.2 and associated Completion Time not met. AND OR C.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months Conductivity 10mhos/cm

@ 25°C in MODE 1, 2, or 3.

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

D. Conductivity greater than D.1 Restore chemistry 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months the limit of Table 3.13-1 in parameter to within limit.

MODE 4 or 5.

OR Chloride concentration greater than the limit of Table 3.13-1 in MODE 4 or 5.

Brunswick Unit 2 3.13-2 Revision No. 23

RCS Chemistry 3.13 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 Brunswick Unit 2 3.13-3 Revision No. 23

RCS Chemistry 3.13 Table 3.13-1 (page 1 of 1)

RCS Chemistry Limits CHEMISTRY APPLICABLE LIMIT PARAMETER MODES OR OTHER SPECIFIED CONDITION

1. Chlorides 1 < 0.5 ppm 2,3,4,5 < 0.2 ppm

2. Conductivity 1,2 < 2.0 mhos/cm @ 25°C 3,4,5 < 10.0 mhos/cm @ 25°C Brunswick Unit 2 3.13-4 Revision No. 23

Structural Integrity 3.14 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 COMPLETION MEASURE TIME A. -------------NOTE------------ A.1 Evaluate the impact of the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Required Action A.1 shall be indication or failed completed if this Condition is inspection on entered. OPERABILITY and

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

failed inspection is found in an ASME Code Class 1, 2, 3 MC, or CC component(s), or structural support component(s).

B. Structural integrity of any of B.1 Declare the associated Immediately ASME Code Class 1 system, structure, or component(s) not component inoperable.

maintained.

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

AND B.3 Restore the structural Prior to entering integrity of affected MODES 1, 2, or 3 component(s) to within limits.

(continued)

Brunswick Unit 2 3.14-1 Revision No. 65

Structural Integrity 3.14 COMPENSATORY MEASURES (continued)

CONDITION REQUIRED COMPENSATORY COMPLETION MEASURE TIME C. Structural integrity of any of C.1.1 Initiate action to isolate the Immediately ASME Code Class 2 or affected component(s).

Class 3 component(s) not maintained. OR C.1.2 Declare the affected Immediately component(s) inoperable/nonfunctional.

AND C.2 Initiate action to restore Immediately structural integrity of affected component(s) to within limits.

AND C.3 Restore the structural Prior to entering integrity of affected MODES 1, 2, or 3 component(s) to within limits.

D. Structural integrity of any of D.1 Declare the affected Immediately ASME Code Class MC or component(s)

Class CC component(s) not inoperable/nonfunctional.

maintained.

AND D.2 Initiate action to restore Immediately structural integrity of affected component(s) to within limits.

AND D.3 Restore the structural Prior to entering integrity of affected MODES 1, 2, or 3 component(s) to within limits.

E. Condition A, B, C, or D or E.1 Declare the associated Immediately associated Completion Time systems, structures, or not met. components inoperable/nonfunctional.

Brunswick Unit 2 3.14-2 Revision No. 65

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

3.15 Not used.

Brunswick Unit 2 3.15-1 Revision No. 23

Service Water System OPERABILITYShutdown 3.16 3.16 SERVICE WATER SYSTEM OPERABILITYSHUTDOWN 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 REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. One required NSW pump --------------------NOTE-------------------

inoperable due to inoperable TRMS 3.0.4 is not applicable.

Unit 2 nuclear service water -----------------------------------------------

header.

A.1 Verify by administrative Immediately means that two Unit 1 NSW pumps are OPERABLE.

AND A.2 Administratively control Immediately nuclear service water header valves to ensure cooling water to the required diesel generators.

AND A.3 Verify two Unit 2 SW Immediately pumps are OPERABLE on the conventional service water header.

AND (continued)

Brunswick Unit 2 3.16-1 Revision No. 58

Service Water System OPERABILITYShutdown 3.16 COMPENSATORY MEASURES (continued)

REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. (continued) A.4 Administratively control Immediately valves to isolate OPERABLE CSW pumps and required loads from the inoperable nuclear header.

AND A.5 Restore required NSW 14 days pump.

B. One required NSW pump B.1 Restore required NSW 7 days inoperable for reasons other pump.

than Condition A.

C. Required Compensatory C.1 Declare required diesel Immediately Measure and associated generators inoperable.

Completion Time of Condition A or B not met.

OR Two or more required NSW pumps inoperable.

D. One required SW pump D.1 Restore required SW 7 days inoperable. pump.

E. Required Compensatory E.1 Declare required Immediately Measure and associated supported equipment Completion Time of inoperable.

Condition D not met.

OR Two required SW pumps inoperable.

Brunswick Unit 2 3.16-2 Revision No. 58

Service Water System OPERABILITYShutdown 3.16 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 31 days 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.

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 92 days cooling water supply from the normal service water supply to the alternate service water supply on low diesel generator jacket cooling water supply pressure.

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 24 months component actuates on an actual or simulated initiation signal.

Brunswick Unit 2 3.16-3 Revision No. 33

Service Water System-Shutdown Operations 3.17 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.

Brunswick Unit 2 3.17-1 Revision No. 23

Service Water System-Shutdown Operations 3.17 COMPENSATORY MEASURES REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. Requirements of TRMS not A.1 Initiate action to restore Immediately met. conventional service water header to operation.

OR A.2 Initiate action to restore Immediately nuclear service water header to OPERABLE status.

TEST REQUIREMENTS TEST FREQUENCY TR 3.17.1 Verify the conventional service water header is lined Prior to securing up to supply cooling water for ECCS by verifying that all service water each valve servicing safety related equipment that is pumps not locked in the proper position is administratively controlled in the proper position.

TR 3.17.2 Verify two way communications between the control Prior to securing room and the service water building. all service water pumps AND 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter (continued)

Brunswick Unit 2 3.17-2 Revision No. 23

Service Water System-Shutdown Operations 3.17 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 Brunswick Unit 2 3.17-3 Revision No. 23

CREV System-Smoke Protection Mode 3.18 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.

REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. One control room A.1 Restore control room 7 days emergency filtration emergency filtration subsystem inoperable. subsystem to OPERABLE status.

OR A.2.1 Prepare a plan to return 7 days 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 (continued)

Brunswick Unit 2 3.18-1 Revision No. 23

CREV System-Smoke Protection Mode 3.18 COMPENSATORY MEASURES (continued)

REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME B. Two control room B.1 Prepare a plan to return 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months emergency filtration the control room subsystems inoperable. emergency filtration subsystems to OPERABLE status and assign a responsible individual to ensure the restoration plan is carried out.

AND 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months B.2 Initiate a condition report.

TEST REQUIREMENTS TEST FREQUENCY TR 3.18.1 Verify the CREV System automatically diverts its inlet 24 months flow through the HEPA filters and charcoal adsorber banks of the Control Room Emergency Filtration System on an actual or simulated smoke detection signal.

Brunswick Unit 2 3.18-2 Revision No. 23

CREV SystemChlorine Protection Mode 3.19 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 REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. Chlorine protection mode of A.1 Remove the chlorine tank 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months the CREV System car from the exclusion inoperable for reasons other area.

than inoperable chlorine isolation instrumentation. OR 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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.

8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Initiate a condition report.

Brunswick Unit 2 3.19-1 Revision No. 23

CREV SystemChlorine Protection Mode 3.19 TEST REQUIREMENTS TEST FREQUENCY TR 3.19.1 Verify the CREV System automatically isolates on an 24 months 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.

Brunswick Unit 2 3.19-2 Revision No. 23

Flood Protection 3.20 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 REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. Intake canal water not within A.1 Initiate applicable Immediately limit. emergency procedure to mitigate consequences of flooding vital equipment.

AND A.2. Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months AND A.3 Be in MODE 4. 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 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months level USGS datum.

Brunswick Unit 2 3.20-1 Revision No. 23

Snubbers 3.21 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 REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. ---------------NOTE-------------- A.1 Determine snubber failure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Required Compensatory mode and that supported Measure A.1 shall be system is acceptable for completed if this Condition is continued operation.

entered.

AND One or more snubbers A.2 Restore snubber to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months inoperable that are OPERABLE status.

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.

B. ---------------NOTE-------------- B.1 Determine snubber failure 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months Required Compensatory mode and that supported Measure B.1 shall be system is acceptable for completed if this Condition is continued operation.

entered.

AND One or more snubbers B.2 Restore snubber to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months inoperable that are OPERABLE status.

associated with more than one train or subsystem of a multiple train or subsystem supported system.

C. Required Compensatory C.1 Declare associated Immediately Measure and associated system(s) inoperable.

Completion Time not met.

Brunswick Unit 2 3.21-1 Revision No. 40

Snubbers 3.21 TEST REQUIREMENTS TEST FREQUENCY TR 3.21.1 Perform snubber testing in accordance with the In accordance with Snubber Program Plan. AD-EG-BNP-1618, "Snubber Program Plan."

Brunswick Unit 2 3.21-2 Revision No. 66

Sealed Source Contamination 3.22 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.

REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. One or more sealed sources A.1 Withdraw the sealed Immediately with removable source from use.

contamination 0.005Ci.

AND A.2.1 Initiate action to Immediately decontaminate and repair the sealed source.

OR A.2.2 Initiate action to dispose of Immediately the sealed source in accordance with NRC regulations.

AND A.3 Submit a Special Report to 12 months the NRC.

Brunswick Unit 2 3.22-1 Revision No. 23

Sealed Source Contamination 3.22 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 184 days each sealed source containing radioactive material with a half-life > 30 days and in any form other than gas, excluding hydrogen 3.

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 Prior to use or and fission detector source that is stored and not in transfer to another use. licensee TR 3.22.3 Perform testing of sealed sources transferred without a Prior to use certificate indicating the last test date.

(continued)

Brunswick Unit 2 3.22-2 Revision No. 23

Sealed Source Contamination 3.22 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 Once within fission detector. 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 Brunswick Unit 2 3.22-3 Revision No. 23

Decay Time 3.23 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 REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. Reactor subcritical A.1 Suspend movement of Immediately

< 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . irradiated fuel in the reactor pressure vessel.

TEST REQUIREMENTS TEST FREQUENCY TR 3.23.1 Determine the reactor has been subcritical for Prior to movement 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verification of the date and time of of irradiated fuel in subcriticality. the reactor pressure vessel Brunswick Unit 2 3.23-1 Revision No. 23

Communications 3.24 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 REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. Direct communications A.1 Suspend CORE Immediately between control room and ALTERATIONS except for refueling platform personnel normal control rod not maintained. movement.

TEST REQUIREMENTS TEST FREQUENCY TR 3.24.1 Verify the availability of direct communications 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months between the control room and refueling platform personnel.

Brunswick Unit 2 3.24-1 Revision No. 23

Crane and Hoist OPERABILITY 3.25 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 REQUIRED COMPENSATORY COMPLETION CONDITION MEASURE TIME A. Requirements of TRMS not A.1 Suspend use of any Immediately met. 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.

Brunswick Unit 2 3.25-1 Revision No. 23

Crane and Hoist OPERABILITY 3.25 TEST REQUIREMENTS TEST FREQUENCY TR 3.25.1 Demonstrate operation of the overload cutoff of each Once within crane or hoist to be used for movement of fuel 7 days prior to assemblies or control rods within the RPV: start of movement of fuel assemblies

a. When the load is 1600 lbs for the mast fuel or control rods gripper; and within the RPV using the

b. When the load is 1050 lbs for all other cranes associated crane and hoists. or hoist, if not performed within the previous 30 days.

TR 3.25.2 Demonstrate operation of the loaded interlock of each Once within crane or hoist to be used for movement of fuel 7 days prior to assemblies or control rods within the RPV: start of movement of fuel assemblies

a. When the load is 750 lbs for the mast fuel or control rods gripper; and within the RPV using the

b. When the load is 350 lbs for all other cranes associated crane and hoists. or hoist, if not performed within the previous 30 days.

(continued)

Brunswick Unit 2 3.25-2 Revision No. 23

Crane and Hoist OPERABILITY 3.25 TEST REQUIREMENTS (continued)

TEST FREQUENCY TR 3.25.3 Demonstrate operation of the slack cable cutoff of the Once within mast fuel gripper when the load is < 50 +/- 25 lbs. 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 Once within hoist to be used for movement of fuel assemblies or 7 days prior to control rods within the RPV. 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)

Brunswick Unit 2 3.25-3 Revision No. 23

Crane and Hoist OPERABILITY 3.25 TEST REQUIREMENTS (continued)

TEST FREQUENCY TR 3.25.5 Demonstrate operation of the uptravel stop of each Once within crane or hoist (other than the mast fuel gripper) to be 7 days prior to used for movement of fuel assemblies or control rods start of movement within the RPV when uptravel would bring the top of of fuel assemblies active fuel to 7 ft below the normal spent fuel pool or control rods water level. within the RPV using the associated crane or hoist, if not performed within the previous 30 days.

Brunswick Unit 2 3.25-4 Revision No. 23

Crane TravelSpent Fuel Storage Pool 3.26 3.26 CRANE TRAVELSPENT 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 REQUIRED COMPENSATORY COMPLETION CONDITION ACTION TIME A. Requirements of TRMS not A.1 Place the load in a safe Immediately met. condition.

TEST REQUIREMENTS TEST FREQUENCY TR 3.26.1 Verify loads, other than fuel assemblies, are 1600 Prior to movement lbs. of loads over fuel assemblies in the spent fuel pool storage racks Brunswick Unit 2 3.26-1 Revision No. 23

4.0 Not used.

Brunswick Unit 2 4.0-1 Revision No. 23

Programs and Manuals 5.0 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)

Brunswick Unit 2 5.0-1 Revision No. 45

Programs and Manuals 5.0 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)

Brunswick Unit 2 5.0-2 Revision No. 41

Programs and Manuals 5.0 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)

Brunswick Unit 2 5.0-3 Revision No. 45

Programs and Manuals 5.0 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 exemptions. 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)

Brunswick Unit 2 5.0-4 Revision No. 45

Programs and Manuals 5.0 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)

Brunswick Unit 2 5.0-5 Revision No. 62

Programs and Manuals 5.0 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.

Brunswick Unit 2 5.0-6 Revision No. 45

TRMS Applicability B 3.0 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)

Brunswick Unit 2 B 3.0-1 Revision No. 23

TRMS Applicability B 3.0 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 component 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)

Brunswick Unit 2 B 3.0-2 Revision No. 26

TRMS Applicability B 3.0 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)

Brunswick Unit 2 B 3.0-3 Revision No. 23

TRMS Applicability B 3.0 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)

Brunswick Unit 2 B 3.0-4 Revision No. 23

TRMS Applicability B 3.0 BASES TRMS 3.0.5 occurring during the performance of a TR on another channel in the (continued) other trip system. A similar 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.

Brunswick Unit 2 B 3.0-5 Revision No. 23

TR Applicability B 3.0 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)

Brunswick Unit 2 B 3.0-6 Revision No. 23

TR Applicability B 3.0 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)

Brunswick Unit 2 B 3.0-7 Revision No. 23

TR Applicability B 3.0 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)

Brunswick Unit 2 B 3.0-8 Revision No. 23

TR Applicability B 3.0 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)

Brunswick Unit 2 B 3.0-9 Revision No. 23

TR Applicability B 3.0 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.

Brunswick Unit 2 B 3.0-10 Revision No. 23

Control Rod Drive Housing Support B 3.1 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 coolant 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 3.1-1 Revision No. 23

B 3.2 Not used.

Brunswick Unit 2 B 3.2-1 Revision No. 23

Control Rod Block Instrumentation B 3.3 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.

Brunswick Unit 2 B 3.3-1 Revision No. 23

Accident Monitoring Instrumentation B 3.4 B 3.4 ACCIDENT MONITORING INSTRUMENTATION BASES The OPERABILITY of the post-accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters 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 H2 and O2 Analyzer from the Technical Specifications, the H2 portion of the analyzer will be maintained as Regulatory Guide 1.97, Category 3, instrumentation. The O2 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 H2 portion or the O2 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 H2 and O2 Analyzer will be capable of diagnosing beyond design-basis accidents.

The H2 and O2 portions of each overall Drywell and Suppression Chamber H2 and O2 Analyzer are primarily separate from one another such that there are many failure modes that would only result in either the H2 or O2 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 H2 and O2 Analyzer has internal to it an H2 analyzer and an O2 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 Line 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 Requirements for Hydrogen and Oxygen Monitors Using The Consolidated Line Item Improvement Process (TAC Nos. MC3866 and MC3867)," dated February 2, 2005.

Brunswick Unit 2 B 3.4-1 Revision No. 60

Chloride Intrusion Monitors B 3.5 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.

Brunswick Unit 2 B 3.5-1 Revision No. 23

Bus Power Monitors B 3.6 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 monitor the availability of power to logic system.

The bus power monitors are required to be OPERABLE 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 instrumentation 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.

Brunswick Unit 2 B 3.6-1 Revision No. 31

ADS Inhibit Switch B 3.7 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.

Brunswick Unit 2 B 3.7-1 Revision No. 23

Suppression Chamber Water Temperature Instrumentation B 3.8 B 3.8 SUPPRESSION CHAMBER WATER TEMPERATURE INSTRUMENTATION BASES The suppression chamber water temperature monitoring 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.

Brunswick Unit 2 B 3.8-1 Revision No. 31

Seismic Monitoring Instrumentation B 3.9 B 3.9 SEISMIC MONITORING INSTRUMENTATION BASES BACKGROUND Seismic Monitoring Instrumentation 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 structures, 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)

Brunswick Unit 2 B 3.9-1 Revision No. 47

Seismic Monitoring Instrumentation B 3.9 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)

Brunswick Unit 2 B 3.9-2 Revision No. 47

Seismic Monitoring Instrumentation B 3.9 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)

Brunswick Unit 2 B 3.9-3 Revision No. 47

Seismic Monitoring Instrumentation B 3.9 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 instruments 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)

Brunswick Unit 2 B 3.9-4 Revision No. 47

Seismic Monitoring Instrumentation B 3.9 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 Function 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)

Brunswick Unit 2 B 3.9-5 Revision No. 47

Seismic Monitoring Instrumentation B 3.9 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.

Brunswick Unit 2 B 3.9-6 Revision No. 47

Intake Canal High Water Level Instrumentation B 3.10 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.

Brunswick Unit 2 B 3.10-1 Revision No. 31

Primary Containment Isolation Instrumentation B 3.11 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 inadvertent 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 Actuation 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 TemperatureHigh (except for Main Steam Isolation Valve Pit instruments) Function and the Turbine Building Area TemperatureHigh Function are each capable of isolating valves in Group 1 except for valves B32-F019 and B32-F020.

Brunswick Unit 2 B 3.11-1 Revision No. 23

CREV System Instrumentation B 3.12 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 external smoke event. These events form the basis for the design of the Control Room Emergency Ventilation (CREV) System function of the CBHVAC System. The radiation protection function of the CREV System is addressed in Technical Specifications.

During an external smoke event, the CBHVAC System 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 pressure 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)

Brunswick Unit 2 B 3.12-1 Revision No. 57

CREV System Instrumentation B 3.12 BASES (continued)

TRMS OPERABILITY of the CREV System instrumentation 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 automatically 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)

Brunswick Unit 2 B 3.12-2 Revision No. 23

CREV System Instrumentation B 3.12 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 protection 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)

Brunswick Unit 2 B 3.12-3 Revision No. 57

CREV System Instrumentation B 3.12 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 consistency 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.

Brunswick Unit 2 B 3.12-4 Revision No. 23

RCS Chemistry B 3.13 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 continuous 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 that 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.

Brunswick Unit 2 B 3.13-1 Revision No. 23

Structural Integrity 3.14 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)

Brunswick Unit 2 B 3.14-1 Revision No. 65

Structural Integrity 3.14 BASES TRMS (continued)

NRC Approved ASME Code Alternative Section XI/ e.g.,

Pipe Class/ Construction RG approved Code Case Energy Code Code Case N-513(1) GL 90-05 (2)

Class 1/HE 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 operating 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 modify 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)

Brunswick Unit 2 B 3.14-2 Revision No. 65

Structural Integrity 3.14 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)

Brunswick Unit 2 B 3.14-3 Revision No. 65

Structural Integrity 3.14 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)

Brunswick Unit 2 B 3.14-4 Revision No. 65

Structural Integrity 3.14 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)

Brunswick Unit 2 B 3.14-5 Revision No. 65

Structural Integrity B 3.14 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)

Brunswick Unit 2 B 3.14-6 Revision No. 65

Structural Integrity B 3.14 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 3.14-7 Revision No. 65

B 3.15 Not used.

Brunswick Unit 2 B 3.15-1 Revision No. 23

Service Water System OPERABILITYShutdown B 3.16 B 3.16 SERVICE WATER SYSTEM OPERABILITYSHUTDOWN 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 System 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 powered 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 service water pump must be powered from a separate emergency bus to be considered OPERABLE.

(continued)

Brunswick Unit 2 B 3.16-1 Revision No. 58

Service Water System OPERABILITYShutdown B 3.16 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)

Brunswick Unit 2 B 3.16-2 Revision No. 58

Service Water System OPERABILITYShutdown B 3.16 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.

Brunswick Unit 2 B 3.16-3 Revision No. 58

Service Water SystemShutdown Operations B 3.17 B 3.17 SERVICE WATER SYSTEMSHUTDOWN OPERATIONS BASES This Specification permits securing the Service 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.

Brunswick Unit 2 B 3.17-1 Revision No. 23

CREV SystemSmoke Protection Mode B 3.18 B 3.18 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEMSMOKE 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 external smoke event. These events form the basis for the design of the Control Room Emergency Ventilation (CREV) System function of the CBHVAC System. The radiation protection function of CREV System is addressed in Technical Specifications.

The CREV System is designed to meet 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).

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)

Brunswick Unit 2 B 3.18-1 Revision No. 23

CREV SystemSmoke Protection Mode B 3.18 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 (washroom) 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 System 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 pressure 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 inoperable, 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)

Brunswick Unit 2 B 3.18-2 Revision No. 23

CREV SystemSmoke Protection Mode B 3.18 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 capability 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.

Brunswick Unit 2 B 3.18-3 Revision No. 23

CREV SystemChlorine Protection Mode B 3.19 B 3.19 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEMCHLORINE 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 external smoke event. These events form the basis for the design of the Control Room Emergency Ventilation (CREV) System function of the CBHVAC System. The radiation protection function of CREV System is addressed in Technical Specifications.

The CREV System is designed to meet 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 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)

Brunswick Unit 2 B 3.19-1 Revision No. 23

CREV SystemChlorine Protection Mode B 3.19 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 (washroom) 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)

Brunswick Unit 2 B 3.19-2 Revision No. 23

CREV SystemChlorine Protection Mode B 3.19 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 capability 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.

Brunswick Unit 2 B 3.19-3 Revision No. 23

Flood Protection B 3.20 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.

Brunswick Unit 2 B 3.20-1 Revision No. 23

Snubbers B 3.21 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, would 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 train 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)

Brunswick Unit 2 B 3.21-1 Revision No. 66

Snubbers B 3.21 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).

Brunswick Unit 2 B 3.21-2 Revision No. 66

Sealed Source Contamination B 3.22 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.

Brunswick Unit 2 B 3.22-1 Revision No. 23

Decay Time B 3.23 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.

Brunswick Unit 2 B 3.23-1 Revision No. 23

Communications B 3.24 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.

Brunswick Unit 2 B 3.24-1 Revision No. 23

Crane and Hoist Operability B 3.25 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.

Brunswick Unit 2 B 3.25-1 Revision No. 23

Crane TravelSpent Fuel Storage Pool B 3.26 B 3.26 CRANE TRAVELSPENT 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 B 3.26-1 Revision No. 23

APPENDIX A RELOCATED ITEMS MATRIX Brunswick Unit 2 Revision No. 23

TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-1) Revision No. 23 General Specific Location ITS CTS Description Location 2.0 LA.2 6.7.1.b, Safety Limit Violations and the notification of the Vice UFSAR Section 13.5.1 6.7.1.c, and President-Brunswick Nuclear Plant along with submittal of 6.7.1.d a report.

3.0 LA.1 3.0.4 Discussion of intent of CTS 3.0.4 phrase "Exceptions to Bases B 3.0: LCO 3.0.4 this Specification are stated in individual Specifications."

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 Bases B 3.1.2: Action A.1 the reactivity difference.

3.1.3 LA.1 3.1.3.1 Details for method of disarming stuck control rods. Bases B 3.1.3: Actions A.1, A.2, Actions a.1.b A.3, and A.4 3.1.3 LA.1 3.1.3.1 Details for method of disarming non-stuck control rods. Bases B 3.1.3: Actions C.1 and Actions b.1.c C.2 and b.2.a.

3.1.3.6 Action a.2 3.1.3 LA.2 4.1.3.6 Details of method of performing the control rod coupling Bases B 3.1.3: SR 3.1.3.5 integrity checks.

3.1.3 LA.3 3.1.3.7 Methods for determining the position of a control rod and Bases B 3.1.3: SR 3.1.3.1 Action a details of which control rod position switches are required.

3.1.3 LA.4 3.1.3.6 Method of coupling a control rod. Bases B 3.1.3: Actions C.1 and Action a.2 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, Details of the method for performing control rod scram Bases B 3.1.4: SR 3.1.4.1, 4.1.3.3, and time testing. SR 3.1.4.2, and 4.1.3.4 SR 3.1.4.4 3.1.4 LA.2 4.1.3.2.c Details of what constituted a representative sample of Bases B 3.1.4: SR 3.1.4.2 control rods to be tested.

TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-2) Revision No. 23 General Specific Location ITS CTS Description Location 3.1.5 LA.1 4.1.3.5 Details of the method of verifying OPERABILITY of control Bases B 3.1.5: SR 3.1.5.1 rod scram accumulators (not in alarmed condition).

3.1.5 LC.1 4.1.3.5.a and Control rod scram accumulators, leak detectors, and UFSAR Section 3.9.4.1.2.4 4.1.3.5.b pressure detectors testing.

3.1.7 LA.1 3.1.5 Details of what constitutes an OPERABLE Standby Liquid Bases B 3.1.7: Background and Control (SLC) System. LCO 3.1.7 LA.2 4.1.5.b.3 Details of the method for performing test that verifies SLC Bases B 3.1.7: SR 3.1.7.5 boron concentration.

3.1.7 LA.2 4.1.5.c.1 Details of the method for performing test that verifies SLC Bases B 3.1.7: SR 3.1.7.7 flow of system to reactor.

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- Statement that boron concentration range in Bases B 3.1.7: Applicable Safety 1 Figure 3.1.5-1 supports a boron concentration of 660 Analysis ppm.

3.1.8 LA.1 4.1.3.1.1 Allowance for scram discharge volume vent and drain Bases B 3.1.8: SR 3.1.8.1 Note

valves to be closed intermittently under administrative control during testing.

None 3/4.1.3.8 Requirement for CRD housing support to be in place. TRM TRMS 3.1 LA.1 3.2.1 LA.1 3.2.1 The types of APLHGR limits, the methodology used to Bases B 3.2.1: LCO determine the limits, and the COLR location of the limits to be used when hand calculations are required.

3.2.1 LA.2 3.2.1 Action Requirement to "initiate corrective action within 15 Bases B 3.2.1: Action A.1 minutes and continue corrective action" to restore limit.

3.2.2 LA.1 3.2.2.1 Details that MPCR limits in the COLR are provided as a Bases B 3.2.2: LCO function of core flow, core power, and cycle average exposure.

3.2.2 LA.2 3.2.2.1 Action Requirement to "initiate corrective action within 15 Bases B 3.2.2: Action A.1 minutes and continue corrective action" to restore limit.

TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-3) Revision No. 23 General Specific Location ITS CTS Description Location 3.2.2 LA.3 3.2.2.2 Details related to the determination of average control rod UFSAR Section 4.4.1.5 scram time (Tau) and the use of Tau in determining the operating limits of MCPRs.

3.3.1.1 Table 2.2.1-1 Trip setpoints for associated instrumentation. TRM Appendix B: TRM LA.1 Table 3.3.1.1-1 3.3.1.1 Table 2.2.1-1 Design details of IRM RPS instrumentation. Bases B 3.3.1.1: ASA/ LCO/ APP LA.2 Note (a) of Function 1.a 3.3.1.1 Table 2.2.1-1 Design details of APRM RPS instrumentation. Bases B 3.3.1.1: ASA/ LCO/ APP LA.2 Notes (c) and of Functions 2.b and 2.c (d) 3.3.1.1 Table 2.2.1-1 Note (b): APRM Neutron Flux - High, Startup Function is a UFSAR Section 7.6.1.1.4 LA.3 Note (b) fixed point and is increased when the reactor mode switch is placed in run position.

3.3.1.1 Table 2.2.1-1 Note (e): Main Steam Line Isolation Valve - Closure UFSAR Section 7.2.1.1.4 LA.3 Notes (e) and Function is bypassed when not in the run mode.

(f) Note (f): TSV - Closure and TCV Fast Closure Functions are bypassed < 30% rated thermal power.

3.3.1.1 Table 2.2.1-1 Vessel water levels are referenced to REFERENCE Bases B 3.3.1.1: ASA/ LCO/ APP LA.4 Note (g) LEVEL ZERO. of Function 4 3.3.1.1 3.3.1 Actions Details relating to placing channels in trip. Bases B 3.3.1.1: Actions A.1 and LA.5

and ** A.2; B.1 and B.2 Notes 3.3.1.1 4.3.1.2 Details of the method for performing surveillances. Bases B 3.3.1.1: SR 3.3.1.1.15 LA.6 3.3.1.1 Table 4.3.1-1 Details of the method for performing surveillances. Bases B 3.3.1.1: SR 3.3.1.1.3 LA.6 Note (e) 3.3.1.1 Table 4.3.1-1 Details of the method for performing surveillances. Bases B 3.3.1.1: SR 3.3.1.1.8 LA.6 Note (g)

TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-4) Revision No. 23 General Specific Location ITS CTS Description Location 3.3.1.1 Table 3.3.1-1 Requirements associated with the removal of shorting UFSAR Section 7.6.1.1.1.2.d LA.7 Note (b) links.

3.3.1.1 Table 3.3.1-1 Number of LPRM inputs for APRM OPERABILITY. Bases B 3.3.1.1: ASA/LCO/APP LA.8 Note (c) of APRM.

3.3.1.1 Table 4.3.1-1 Details on how to perform calibration of position switches. Bases B 3.3.1.1: SR 3.3.1.1.13 LA.9 Note (h) 3.3.1.2 4.3.5.4.b Details of the method for performing the surveillance. Bases B 3.3.1.2: LCO LA.1 3.3.1.2 3/4.9.2 Details relating to SRM OPERABILITY. Bases B 3.3.1.2: LCO; LA.2 SR 3.3.1.2.4 3.3.1.2 3.9.2.c Removal of RPS shorting links. UFSAR Section 7.6.1.1.1.2.d LA.3 3.3.2.1 Table 3.3.4-2 Trip setpoints for associated instrumentation. TRM Appendix B: TRM LA.1 Table 3.3.2.1-1 3.3.2.1 Table 4.3.1-1 Details of the methods for performing the RBM CHANNEL Bases B 3.3.2.1: SR 3.3.2.1.7 LA.2 Note (a) CALIBRATION.

3.3.2.1 3.1.4.1 Details relating to actions when an individual control rod is Bases B 3.3.2.1: Actions C.1, LA.3 Action d.2 bypassed on the RWM. C.2.1.1, C.2.1.2, and C.2.2 3.3.2.1 4.1.4.1.1 Details of the methods for performing RWM CHANNEL Bases B 3.3.2.1: SR 3.3.2.1.2 LA.4 FUNCTIONAL TEST. and SR 3.3.2.1.3 3.3.2.1 R.1 3/4.3.4.1 Control Rod Block Instrumentation for APRM, IRM, SRM, TRM TRMS 3.3 and Appendix 3/4.3.4.3 and SDV LCO's and Surveillance Requirements. C: TRM Table 3.3-2 3/4.3.4.4 3/4.3.4.5 3.3.3.1 Table 3.3.5.3- The use of alternate methods of post accident monitoring. Bases B 3.3.3.1: Action B.1 LA.1 1 ACTION 81

TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-5) Revision No. 23 General Specific Location ITS CTS Description Location 3.3.3.1 Table 4.3.5.3- Details of the method for performing the surveillance. Bases B 3.3.3.1: SR 3.3.3.1.2 LA.2 1 Note (a) and SR 3.3.3.1.3 3.3.3.1 3.6.6.4 Details relating to system design. Bases B 3.3.3.1: LCO for LA.3 Function 9 3.3.3.1 4.6.6.4 Details of the method for performing the surveillance. Bases B 3.3.3.1: SR 3.3.3.1.2 LA.4 and SR 3.3.3.1.3 3.3.3.1 R.1 3/4.3.5.3 Accident Monitoring Instrumentation; Suppression TRM TRMS 3.4 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.

3.3.3.2 3/4.3.5.2 Details relating to system design and operation. Bases B 3.3.3.2: LCO and Table LA.1 B 3.3.3.2-1 3.3.4.1 3/4.3.6.1 Trip setpoints for associated instrumentation. TRM Appendix B: TRM LA.1 Table 3.3.4.1-1 3.3.4.1 Table 3.3.6.1- Vessel water levels are referenced to REFERENCE Bases B 3.3.4.1: ASA/ LCO/ APP LA.2 2 Note (a) LEVEL ZERO. of Function a 3.3.5.1 3/4.3.3 Trip setpoints for associated instrumentation. TRM Appendix B: TRM LA.1 Table 3.3.5.1-1 3.3.5.1 4.3.3.2 Details of methods of performing the LOGIC SYSTEM Bases B 3.3.5.1: SR 3.3.5.1.5 LA.2 FUNCTIONAL TESTS.

3.3.5.1 Table 3.3.3-1 Reactor Vessel Shroud Level Function is a permissive for Bases B 3.3.5.1: ASA/ LCO/ APP LA.3 Function 2.c drywell spray. of Function 2.e 3.3.5.1 Table 3.3.3-1 CS and RHR Pump Discharge Pressure-High Functions Bases B 3.3.5.1: ASA/ LCO/ APP LA.3 Functions 4.e are permissives for ADS. of Functions 4.d, 4.e, 5.d, and 4.f and 5.e 3.3.5.1 Table 3.3.3-1 Details associated with equipment started by the LPCI Bases B 3.3.5.1: ASA/ LCO/ APP LA.4 Function Reactor Steam Dome Pressure-Low Function. of Functions 1.c and 2.c 2.d.1

TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-6) Revision No. 23 General Specific Location ITS CTS Description Location 3.3.5.1 Table 3.3.3-1 Detail which describes what equipment receives the HPCI Bases B 3.3.5.1: ASA/ LCO/ APP LA.5 Note (c) pump suction swap over signals. of Functions 3.d and 3.e 3.3.5.1 Table 3.3.3-1 Requirement to place all inoperable channels that do not Bases B 3.3.5.1: Actions B.1, LA.6 ACTION 30, cause the trip function to occur in the tripped condition. B.2, and B.3 item b 3.3.5.1 Table 3.3.3-2 Note (b): Reactor vessel water levels are referenced to Bases B 3.3.5.1: ASA/ LCO/ APP LA.7 Note (b) REFERENCE LEVEL ZERO. 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 Table 3.3.3-2 Note (c): Suppression chamber water level zero is the Bases B 3.3.5.1: ASA/ LCO/ APP LA.7 Note (c) torus centerline minus 1 inch. of Function 3.e 3.3.5.1 R.1 3/4.3.3.1.e ECCS Actuation Instrumentation LCO and Surveillances TRM TRMS 3.6 3/4.3.3.2.f associated with:

3/4.3.3.3.e Core Spray Bus Power Monitor; 3/4.3.3.4.g LPCI Bus Power Monitor; HPCI Bus Power Monitor; and ADS Bus Power Monitor.

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 3/4.3.7 Trip setpoints for associated instrumentation. TRM Appendix B: TRM LA.1 Table 3.3.5.2-1 3.3.5.2 4.3.7.2 Details relating to the methods for performing the LOGIC Bases B 3.3.5.2: SR 3.3.5.2.5 LA.2 SYSTEM FUNCTIONAL TEST.

3.3.5.2 Table 3.3.7-1 RCIC System design and operational details. Bases B 3.3.5.2: Background LA.3 Notes (b) and (c) 3.3.5.2 Table 3.3.7-1 RCIC System design and operational details. Bases B 3.3.5.2: ASA/ LCO/

LA.3 Note (d) APP of Function 3 3.3.5.2 Table 3.3.7-2 Reactor vessel water levels are referenced to Bases B 3.3.5.2: ASA/ LCO/

LA.4 Note (a) REFERENCE LEVEL ZERO. APP of Functions 1 and 2

TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-7) Revision No. 23 General Specific Location ITS CTS Description Location 3.3.6.1 3/4.3.2 Trip setpoints for associated instrumentation. TRM Appendix B: TRM LA.1 Table 3.3.6.1-1 3.3.6.1 4.3.2.2 Details relating to the method for performing LOGIC Bases B 3.3.6.1: SR 3.3.6.1.7 LA.2 SYSTEM FUNCTIONAL TEST.

3.3.6.1

Note to Details of the method for performing Required Actions of Bases B 3.3.6.1: Action A.1 LA.3 3.3.2 Actions which trip system to trip.

3.3.6.1 Table 3.3.2-1 Details relating to system design and operation. Bases B 3.3.6.1: ASA/LCO/APP LA.4 of all Functions 3.3.6.1 Table 3.3.2-1 Details relating to system design and operation. Bases B 3.3.6.1: ASA/LCO/APP LA.4 Note (k) of Functions 3.e and 4.e 3.3.6.1 Table 3.3.2-1 Requirement for bypassing the Condenser Vacuum-Low UFSAR Section 7.3.1.1.6.20 LA.5 Function 1.e Function when <500 psig.

3.3.6.1 Table 3.3.2-2 Reactor vessel water levels are referenced to Bases B 3.3.6.1: ASA/LCO/APP LA.7 Note (a) REFERENCE LEVEL ZERO. of Functions 1.a, 2.a, 5.g, and 6.b 3.3.6.1 R.1 3/4.3.2.4.a.5 HPCI and RCIC Bus Power Monitoring. TRM TRMS 3.6 3/4.3.2.4.b.5 3.3.6.1 R.2 3/4.3.2.1.d Main Steam Line Tunnel and Turbine Bldg Area TRM TRMS 3.11 and and Temperature Instrumentation for MSIV isolation function Appendix C: TRM 3/4.3.2.1.f (except for MSIV pit). Table 3.11-2 3.3.6.2 3/4.3.2 Trip setpoints for associated instrumentation. TRM Appendix B: TRM LA.1 Table 3.3.6.2-1 3.3.6.2 4.3.2.2 Details relating to the method for performing the LOGIC Bases B 3.3.6.2: SR 3.3.6.2.5 LA.2 SYSTEM FUNCTIONAL TEST.

3.3.6.2

Note to Details of the method for performing Required Actions of Bases B 3.3.6.2: Action A.1 LA.3 3.3.2 Actions which trip system to trip.

3.3.6.2 Table 3.3.2-1 Details relating to system design and operation. Bases B 3.3.6.2: Background LA.4

TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-8) Revision No. 23 General Specific Location ITS CTS Description Location 3.3.6.2 Table 3.3.2-2 Reactor vessel water levels are referenced to Bases B 3.3.6.2: ASA/LCO/APP LA.5 Note (a) REFERENCE LEVEL ZERO. of Function 1 3.3.7.1 3/4.3.5.5 Trip setpoints for associated instrumentation. TRM Appendix B: TRM LA.1 Table 3.3.7.1-1 3.3.7.1 R.1 3/4.3.5.5.1 CREV System Chlorine Protection Instrumentation and TRM TRMS 3.12 and 3/4.3.5.5.3 Smoke Protection Mode Instrumentation requirements. Appendix C: TRM Table 3.12-2 3.3.7.2 3.3.8 Details relating to instrumentation OPERABILITY. Bases B 3.3.7.2: LCO LA.1 3.3.8.1 3/4.3.3 Trip setpoints for associated instrumentation. TRM Appendix B: TRM LA.1 Table 3.3.8.1-1 3.3.8.1 4.3.3.2 Details relating to the methods for performing the LOGIC Bases B 3.3.8.1: SR 3.3.8.1.4 LA.2 SYSTEM FUNCTIONAL TEST.

3.3.8.1 Table 3.3.3-1 Details relating to system design (i.e number of channels Bases B 3.3.8.1: Background LA.3 Table 3.3.3-2 provided, etc.).

3.3.8.1 Table 3.3.3-2 Bases for 120V loss of power instrumentation trip TRM Appendix B: TRM LA.4 setpoints and Allowable Values. Table 3.3.8.1-1 None 3/4.3.5.1 R.1 Seismic Monitoring Instrumentation Technical TRM TRMS 3.9 Specification.

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 ODCM ODCMS 7.3.1 Technical Specification.

None 3/4.3.5.9 Requirements for the Main Condenser Off-Gas Treatment ODCM ODCMS 7.3.2 LC.1 System Explosive Gas Monitoring System (Function G).

None 3/4.3.5.9 R.1 Radioactive Gaseous Effluent Monitoring Instrumentation ODCM ODCMS 7.3.2 Technical Specification.

TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-9) Revision No. 27 General Specific Location ITS CTS Description Location 3.4.2 LA.1 4.4.1.2.2 Requirements that each jet pump be operable prior to UFSAR Deleted in Section 3.9.5.4 entering OPERATIONAL CONDITION 2 and at least once per LDCR 04FSAR-038.

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.

3.4.3 LA.1

footnote to Details relating to lift setting pressures of the safety/relief Bases B 3.4.3: SR 3.4.3.1 3.4.2 valves.

3.4.4 LA.1 4.4.3.2 Details of the methods for performing the Reactor Coolant Bases B 3.4.4: SR 3.4.4.1 System leakage surveillance.

3.4.6 LA.1 Table 4.4.5-1 Requirements for isotopic analysis for xenon and krypton. UFSAR Section 11.1.2 Item 5 3.4.9 LA.1 3.4.6.1.c Limitations on the maximum RCS temperature change in Bases B 3.4.9: Actions C.1 and any one hour period during inservice leak and hydrostatic C.2 testing operations above the heatup and cooldown limit curves.

3.4.9 LA.2 4.4.6.1.3 Requirements for reactor material irradiation surveillance UFSAR Section 5.3.1.6 specimen location, removal and examination.

3.4.9 LA.2 Table Requirements for reactor material irradiation surveillance UFSAR Table 5-8 4.4.6.1.3-1 specimen location, removal and examination.

3.4.9 LA.3 3.4.1.3.c and Operational limits during single recirculation loop UFSAR Section 5.4.1.2.2 3.4.1.3 Action operation.

3.4.9 LA.4 3.4.6.1 Action Details of method for determining RCS is acceptable for Bases B 3.4.9: Actions A.1 and continued operation. 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 Bases B 3.4.9: SR 3.4.9.4 and startup temperature differential verification (specific RCS SR 3.4.9.5 location to monitor temperature).

None 3/4.4.4 R.1 Reactor Coolant System Chemistry Technical TRM TRMS 3.13 Specification.

None 3/4.4.8 R.1 Reactor Coolant System Structural Integrity Technical TRM TRMS 3.14 Specification.

TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-10) Revision No. 23 General Specific Location ITS CTS Description Location 3.5.1 LA.1 3.5.1, 3.5.3.1 Details relating to system OPERABILITY. Bases B 3.5.1: Background and 3.5.3.2 3.5.1 LA.2 4.5.1.c.1, Details of methods for performing Surveillances. Bases B 3.5.1: SR 3.5.1.9 4.5.3.1.d, and 4.5.3.2.c 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 Details of methods for performing Surveillances. Bases B 3.5.1: SR 3.5.1.6, and 4.5.3.2.d 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 UFSAR Section 7.3.3.1.3.7 Surveillance Requirements.

3.5.2 LA.1 3.5.3.1, Details relating to system OPERABILITY. Bases B 3.5.2: LCO 3.5.3.2, and 3.5.4 3.5.2 LA.2 4.5.3.1.c.1, Details relating to methods for performing surveillances. Bases B 3.5.2: SR 3.5.2.3, 4.5.3.1.d. SR 3.5.2.5, SR 3.5.2.6, 4.5.3.2.b, and and SR 3.5.2.7 4.5.3.2.c 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 Details relating to methods for performing surveillances. Bases B 3.5.3: SR 3.5.3.5 (including Note +)

TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-11) Revision No. 23 General Specific Location ITS CTS Description Location 3.5.3 LA.2 4.7.4.b and Details relating to methods for performing surveillances. Bases B 3.5.3: SR 3.5.3.3 and 4.7.4.c.2 SR 3.5.3.4 3.5.3 LA.3 4.7.4.c.3 Verification of automatic transfer of the RCIC pump Bases B 3.5.3: SR 3.5.3.5 suction.

3.6.1.1 1.0 Details of Primary Containment Integrity definition. Bases B 3.6.1.1: Background LA.1 3.6.1.2 3.6.1.3.a Details comprising OPERABILITY of the air lock. Bases B 3.6.1.2: LCO LA.1 3.6.1.3 4.6.3.4 Details relating to methods for performing surveillances. Bases B 3.6.1.3: SR 3.6.1.3.7 LA.1 3.6.1.3 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 LA.2 3.6.1.4 4.6.1.6 Details of the methods for performing the drywell average Bases B 3.6.1.4: SR 3.6.1.4.1 LA.1 air temperature surveillance.

3.6.1.5 3.6.4.2.b Details relating to the OPERABILITY of the Nitrogen Bases B 3.6.1.5: Background LA.1 Backup System.

3.6.1.5 4.6.4.2.1.a.1 Details of the method for performing surveillances. Bases B 3.6.1.5: SR 3.6.1.5.3 LA.2 and 4.6.4.2.1.a.2 3.6.1.5 4.6.4.2.1.b.1 Details of the method for performing surveillances. Bases B 3.6.1.5: SR 3.6.1.5.4 LA.2 and 4.6.4.2.1.b.2 3.6.1.5 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 LA.2 3.6.1.5 4.6.4.2.1.b.3 Details of visual inspection of reactor building-to- UFSAR Section 6.2.1.6.2 LA.3 suppression chamber vacuum breakers.

3.6.1.6 4.6.4.1.b Details of the methods for performing surveillances. Bases B 3.6.1.6: SR 3.6.1.6.2 LA.2

TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-12) Revision No. 23 General Specific Location ITS CTS Description Location 3.6.1.6 4.6.4.1.c Details of the methods for performing surveillances. Bases B 3.6.1.6: SR 3.6.1.6.1 LA.2 3.6.2.3 3.6.2.2 Details relating to system OPERABILITY. Bases B 3.6.2.3: Background LA.1 and LCO 3.6.3.2 3.6.6.2 Details relating to system OPERABILITY. Bases B 3.6.3.2: LCO LA.1 3.6.3.2 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 LA.2 3.6.4.1 1.0 Details of Secondary Containment Integrity definition. Bases B 3.6.4.1: LCO LA.1 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 4.6.5.1.a and Cycling of each automatic Secondary Containment UFSAR Section 6.2.3.4 LA.1 4.6.5.2.a Isolation Damper.

3.6.4.2 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 LA.2 3.6.4.3 3.6.6.1 Details relating to system design. Bases B 3.6.4.3: Background LA.1 3.6.4.3 4.6.6.1.a Details of the methods for performing standby gas Bases B 3.6.4.3: SR 3.6.4.3.1 LA.2 treatment subsystem operating surveillance.

3.6.4.3 4.6.6.1.a Details of performance of standby gas treatment Bases B 3.6.4.3: SR 3.6.4.3.1 LA.3 subsystem surveillance with heaters "on automatic control."

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 General Specific Location ITS CTS Description Location 3.7.2 LA.2 3.7.1.2 Requirements and Actions relating to system Bases B 3.4.8: LCO; OPERABILITY in non-operating MODES (i.e., MODES 4 and B 3.9.7: LCO; and 5). TRM 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 Details defining the radioactivity involved, methods for Bases B 3.7.5: SR 3.7.5.1 4.11.2.7.2 performing the surveillance, and methods for determining when an increase has occurred.

3.7.5 LA.2 4.11.2.7.1 Requirements to monitor the radioactivity rate of noble ODCM ODCMS Table 7.3.2-1, gases at the main condenser. 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 Bases B 3.7.7: Action A.1 equipment in a safe condition.

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 UFSAR Section 8.3.1.1.6.6 procedures prepared in accordance with manufacturer's recommendations.

3.8.1 LA.2 4.8.1.1.2.a.4 Details associated with manually starting the DG for Bases B 3.8.1: SR 3.8.1.2 and Note

surveillances. SR 3.8.1.7

TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-14) Revision No. 25 General Specific Location ITS CTS Description 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 Details relating to system design. Bases B 3.8.1: Background 3.8.1.1.b 3.8.4 LA.1 3.8.2.3.a and Details relating to system OPERABILITY. Bases B 3.8.4: Background and 3.8.2.3.b LCO 3.8.4 LA.3 4.8.2.3.2.d.1 Details of the DC loads and the licensed service duration UFSAR Section 8.3.2.1.4 for battery service test.

3.8.4 LA.4 4.8.2.3.2.d.2 Details requiring battery charger to be demonstrated UFSAR Section 8.3.2.1.4 capable of recharging its associated battery after completion of the battery service test.

3.8.7 LA.1 3.8.2.1, Details relating to system design and OPERABILITY. Bases B 3.8.7: Background; 4.8.2.1, LCO; Table B 3.8.7-1 3.8.2.3, 4.8.2.3.1, 3.8.2.4.1, and 4.8.2.4.1.1 3.8.7 LA.1 3.8.2.4.1 Details relating to system design and OPERABILITY. Bases B 3.8.7: Actions B.1, B.2,

Note B.3, and B.4 3.8.7 LA.2 3.8.2.4.1 Details of the methods for performing verification of power Bases B 3.8.7: Actions B.1, B.2, Actions b.1 availability. B.3, and B.4 and b.3 3.8.8 LA.1 3.8.2.2 and Details relating to AC and DC electrical power distribution Bases B 3.8.7: Table B 3.8.7-1 3.8.2.4.2 system design and OPERABILITY.

3.9.5 LA.1 4.1.3.5.a Details of the method of verifying OPERABILITY of the Bases B 3.9.5: SR 3.9.5.1 and control rod accumulators. SR 3.9.5.2 3.9.5 LC.1 4.1.3.5.a and Control rod scram accumulators, leak detectors, and UFSAR Section 3.9.4.1.2.4 4.1.3.5.b pressure detectors testing.

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 General Specific Location ITS CTS Description 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 TRM TRMS 3.26 Specification.

3.10.2 LA.1 Table 1.2 Details of the method used to verify control rods remain Bases B 3.10.2: SR 3.10.2.1 and Note # fully inserted (by verification using a second licensed SR 3.10.2.2 operator or other technically qualified member of the unit technical staff.).

3.10.4 LA.1 3/4.9.10.1.d Details of the recommended procedures for disarming Bases B 3.10.4: SR 3.10.4.1, control rods. 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 Bases B 3.10.5: SR 3.10.5.1, control rods. 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 Bases B 3.4.8: LCO; Water system in non-operating MODES (i.e., MODES 4 and B 3.9.7: LCO; and 5). TRM B 3.9.8: LCO; TRMS 3.17 None 3/4.11.1.1 Liquid Effluents Concentration Technical Specification. ODCM ODCMS 7.3.3 R.1 None 3/4.11.1.2 Dose Liquid Effluents Technical Specification. ODCM ODCMS 7.3.4 R.1 None 3/4.11.1.3 Liquid Radwaste Treatment System Technical ODCM ODCMS 7.3.5 R.1 Specification.

None 3/4.11.2.1 Gaseous Effluents Technical Specification. ODCM ODCMS 7.3.7 R.1

TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-16) Revision No. 25 General Specific Location ITS CTS Description Location None 3/4.11.2.2 Dose Noble Gases Technical Specification. ODCM ODCMS 7.3.8 R.1 None 3/4.11.2.3 Dose Iodine-131, Iodine-133, Tritium, and Radionuclides ODCM ODCMS 7.3.9 R.1 in Particulate Form Technical Specification.

None 3/4.11.2.4 Gaseous Radwaste Treatment System Technical ODCM ODCMS 7.3.10 R.1 Specification.

None 3/4.11.2.5 Ventilation Exhaust Treatment System Technical ODCM ODCMS 7.3.11 R.1 Specification.

None 3/4.11.2.8 Drywell Venting or Purging Technical Specification. ODCM ODCMS 7.3.13 R.1 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 ODCM ODCMS 7.3.15 Specification.

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 ODCM ODCMS 7.3.17 Specification.

4.0 LA.1 5.1.2 and Details of the low population zone and site boundary. UFSAR Section 2.1.1.3 5.1.3 4.0 LA.2 5.2 Configurations, design temperatures and pressures, and UFSAR Section 6.2.1 and volumes of the Primary Containment. Table 6-3 4.0 LA.2 5.4 Configurations, design temperatures and pressures, and UFSAR Section 5.3.3.7 and volumes of the Reactor Coolant System. Table 6-5 4.0 LA.3 5.3.1 Details of specific fuel types that can be inserted in the UFSAR Section 4.2.2 reactor core.

TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-17) Revision No. 25 General Specific Location ITS CTS Description 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 keff calculations UFSAR Section 9.1.2.3.2 associated with the fuel racks.

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 Corrected temperature for irradiated fuel k-infinity values. UFSAR Section 9.1.2.3.2 5.6.1.2.b 5.1 LA.1 6.1.1 and Compliance details relating to plant specific position titles. UFSAR Section 13.1.2.2 6.5.2.7 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 UFSAR Section 13.1.2.2 either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling.

5.2 LA.4 6.2.1.b, Compliance details relating to plant specific position titles. UFSAR Section 13.1.2.2 6.2.1.c, 6.2.2.e, and 6.2.4.1 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 QA Program UFSAR Chapter 17, Assurance for effluent and environmental monitoring. Description Appendix A, Section 1.1.1 5.4 LA.2 6.8.2 Details of procedure reviews and approvals for temporary QA Program UFSAR Chapter 17, changes. Description Appendix A, Section 1.1.2 5.4 LA.3 6.8.1.h Requirements for Process Control Program QA Program UFSAR Section 17.3.1.7 implementation procedures. Description

TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-18) Revision No. 25 General Specific Location ITS CTS Description 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 UFSAR Table 5-11 or Transient Limit Program.

5.5 LA.3 4.0.5 Details of the Inservice Inspection Program associated UFSAR Section 5.2.3.4.2.4 with Generic Letter 88-01.

5.5 LA.3 4.0.5 Details of the Inservice Inspection Program for Class 1 UFSAR Section 5.2.4 components..

5.5 LA.3 4.0.5 Details of the Inservice Inspection Program for Class 2 UFSAR Section 6.6 and 3 components.

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, Details of the methods for implementing testing of the TRM Section 5.5.7 4.6.6.1.c, SGTS and CREV filter system laboratory analysis.

4.7.2.b.2,and 4.7.2.c 5.5 LA.6 3/4.11.1.4 Details of the methods for implementing requirements for ODCM ODCMS 7.3.6 Liquid Holdup Tanks.

5.5 LA.6 3/4.11.2.6 Details of the methods for implementing requirements for ODCM ODCMS 7.3.12 Explosive Gas Mixtures.

5.5 LA.7 4.8.1.1.2.c References to ASTM Standards and acceptance criteria Bases B 3.8.3: SR 3.8.3.2 for diesel fuel oil.

5.6 LA.1 6.9.1.1, Details associated with Startup Report. UFSAR Section 13.4.2.1 6.9.1.2, and 6.9.1.3 5.6 LA.2 6.9.3.1.a Details associated with individual specifications Bases B 3.2.1: ASA and LCO addressing the Core Operating Limits Report.

TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-19) Revision No. 23 General Specific Location ITS CTS Description Location 5.6 LA.2 6.9.3.1.b Details associated with individual specifications Bases B 3.2.2: ASA and LCO addressing the Core Operating Limits Report.

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 UFSAR Section 13.2.2 the unit staff.

None 6.5 LA.1 Details of procedures, modification, or Operating QA Program UFSAR Chapter 17, License/Technical Specification reviews and approvals for Description Appendix A, Sections changes. 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 UFSAR Chapter 17, Description Appendix A, Sections 1.6, 1.7, 1.8, and 1.9 None 6.6 LA.2 Details of reportable events reviews. QA Program UFSAR Chapter 17, Description Appendix A, Section 2.0 None 6.10 LA.1 Details of record retention. QA Program UFSAR Chapter 17, Description 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

APPENDIX B TECHNICAL SPECIFICATION (TS) INSTRUMENT LIST Brunswick Unit 2 Revision No. 23

TRM TS Instrument List Appendix B 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 Protection 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.

Brunswick Unit 2 B-1 Revision No. 23

TRM TS Instrument List Appendix B TRM Table 3.3.1.1-1 (page 1 of 2)

Reactor Protection System Instrumentation TECHNICAL APPLICABLE NOMINAL SPECIFICATION INSTRUMENT TRIP FUNCTION NUMBER(S) SETPOINT

1. Intermediate Range Monitors

a. Neutron FluxHigh C51-IRM-A, B, C, D, E, F, G, H 117/125 divisions of full C72-K14A, B, C, D, E, F, G, H scale

b. Inop C51-IRM-A, B, C, D, E, F, G, H NA C72-K14A, B, C, D, E, F, G, H

2. Average Power Range Monitors

a. Neutron FluxHigh (Setdown) C51-APRM1-AR51 15% RTP C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11

b. Simulated Thermal PowerHigh C51-APRM1-AR51 0.55W + 61.1% RTP (a)

C51-APRM2-AR31 and 115.8% RTP C51-APRM3-AR41 C51-APRM4-AR11

c. Neutron FluxHigh C51-APRM1-AR51 117.4% RTP C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11

d. Inop C51-APRM1-AR51 NA C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11

e. 2-Out-of-4 Voter C51-APRM1-AR51 NA C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11

f. OPRM Upscale C51-APRM1-AR51 NA(c)

C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11

3. Reactor Vessel Steam Dome PressureHigh B21-PT-N023A, B, C, D 1060 psig B21-PTM-N023A-1, B-1, C-1, D-1 C72-K14A, B, C, D, E, F, G, H

4. Reactor Vessel Water LevelLow Level 1 B21-LT-N017A-1, B-1, C-1, D-1 166 inches B21-LTM-N017A-1, B-1, C-1, D-1 C72-K14A, B, C, D, E, F, G, H (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.

Brunswick Unit 2 B-2 Revision No. 44

TRM TS Instrument List Appendix B TRM Table 3.3.1.1-1 (page 2 of 2)

Reactor Protection System Instrumentation TECHNICAL APPLICABLE NOMINAL SPECIFICATION INSTRUMENT TRIP FUNCTION NUMBER(S) SETPOINT

5. Main Steam Isolation ValveClosure B21-F022A, B, C, D 1.25 inches of stem travel(b)

B21-F028A, B, C, D C72-K14A, B, C, D, E, F, G, H

6. Drywell PressureHigh C72-PT-N002A, B, C, D 1.7 psig C72-PTM-N002A-1, B-1, C-1, D-1 C72-K14A, B, C, D, E, F, G, H

7. Scram Discharge Volume C12-LSH-N013A, B, C, D 104 gallons Water LevelHigh C12-LSH-4516A, B, C, D C72-K14A, B, C, D, E, F, G, H

8. Turbine Stop ValveClosure MS-ZS-SVRP-1, 2, 3, 4 0.625 inches of stem C72-K14A, B, C, D, E, F, G, H travel(b)

9. Turbine Control Valve Fast Closure, Control Oil PressureLow EHC-PSL-1756, 1757, 1758, 1759 600 psig C72-K14A, B, C, D, E, F, G, H

10. Reactor Mode SwitchShutdown Position C72-CS-S1 NA

11. Manual Scram C72-PB-S3A, B NA (b) Nominal Trip Setpoint is referenced from valve full open position.

Brunswick Unit 2 B-3 Revision No. 23

TRM TS Instrument List Appendix B TRM Table 3.3.1.2-1 (page 1 of 1)

Source Range Monitor Instrumentation TECHNICAL APPLICABLE SPECIFICATION INSTRUMENT FUNCTION NUMBER(S)

1. Source Range Monitor C51-SRM-A, B, C, D Brunswick Unit 2 B-4 Revision No. 44

TRM TS Instrument List Appendix B TRM Table 3.3.2.1-1 (page 1 of 1)

Control Rod Block Instrumentation TECHNICAL APPLICABLE NOMINAL SPECIFICATION INSTRUMENT TRIP FUNCTION NUMBER(S) SETPOINT

1. Rod Block Monitor

a. Low Power RangeUpscale C51-RBMA-AR21 (a)

C51-RBMB-AR22

b. Intermediate Power RangeUpscale C51-RBMA-AR21 (a)

C51-RBMB-AR22

c. High Power RangeUpscale C51-RBMA-AR21 (a)

C51-RBMB-AR22

d. Inop C51-RBMA-AR21 NA C51-RBMB-AR22

2. Rod Worth Minimizer 2-C12-CNV-5516 19.1% rated steam flow

3. Reactor Mode SwitchShutdown Position C72-CS-S1 NA (a) Nominal Trip Setpoints specified in the COLR.

Brunswick Unit 2 B-5 Revision No. 23

TRM TS Instrument List Appendix B TRM Table 3.3.2.2-1 (page 1 of 1)

Feedwater and Main Turbine High Water Level Trip Instrumentation TECHNICAL APPLICABLE NOMINAL SPECIFICATION INSTRUMENT TRIP FUNCTION NUMBER(S) SETPOINT

1. Feedwater Pumps

a. Reactor Vessel Water LevelHigh C32-LT-N0O4A, B, C 206 inches C32-LY-K602A - A1, B1, A4 C32-LY-K602C - A1, B1, A4 C32-LY-K602E - A1, B1, A4 C32-LC-R602A, B

2. Main Turbine

a. Reactor Vessel Water LevelHigh C32-LT-N0O4A, B, C 206 inches C32-LY-K602A - A1, B1, A4 C32-LY-K602C - A1, B1, A4 C32-LY-K602E - A1, B1, A4 C32-LC-R602A, B Brunswick Unit 2 B-6 Revision No. 23

TRM TS Instrument List Appendix B TRM Table 3.3.3.1-1 (page 1 of 1)

Post Accident Monitoring Instrumentation TECHNICAL APPLICABLE SPECIFICATION INSTRUMENT FUNCTION NUMBER(S)

1. Reactor Vessel Pressure B21-PI-R605A, B

2. Reactor Vessel Water Level

a. -150 inches to +150 inches B21-LI-R610, B21-LR-R615

b. 0 inches to +210 inches B21-LI-R604A, B

c. +150 inches to +550 inches B21-LI-R605A, B

3. Suppression Chamber Water Level CAC-LI-2601-1, CAC-LR-2602

4. Suppression Chamber Water Temperature CAC-TR-4426-1A CAC-TR-4426-2A CAC-TY-4426-1, 2

5. Suppression Chamber Pressure CAC-PI-1257-2A, B

6. Drywell Pressure CAC-PI-4176, CAC-PR-1257-1

7. Drywell Temperature CAC-TR-4426-1A, B CAC-TR-4426-2A, B CAC-TY-4426-1, 2

8. PCIV Position See TRM Table 3.3.3.1-2, "Primary Containment Isolation Valve Position Indication."

9. (Not Used.)

10. Drywell Area Radiation D22-RI-4195 OR D22-RI-4196 OR D22-RR-4195 AND D22-RI-4197 OR D22-RI-4198 OR D22-RR-4197 Brunswick Unit 2 B-7 Revision No. 39

TRM TS Instrument List Appendix B TRM Table 3.3.3.1-2 (page 1 of 5)

Primary Containment Isolation Valve Position Indication VALVE VALVE DESCRIPTION LOCATION NUMBER 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)

Brunswick Unit 2 B-8 Revision No. 23

TRM TS Instrument List Appendix B TRM Table 3.3.3.1-2 (page 2 of 5)

Primary Containment Isolation Valve Position Indication VALVE VALVE DESCRIPTION LOCATION NUMBER 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 SUPPRESSION CHAMBER VACUUM BREAKER XU-51 2-CAC-V17 REACTOR BUILDING TO SUPPRESSION 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)

Brunswick Unit 2 B-9 Revision No. 23

TRM TS Instrument List Appendix B TRM Table 3.3.3.1-2 (page 3 of 5)

Primary Containment Isolation Valve Position Indication VALVE VALVE DESCRIPTION LOCATION NUMBER 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)

Brunswick Unit 2 B-10 Revision No. 23

TRM TS Instrument List Appendix B TRM Table 3.3.3.1-2 (page 4 of 5)

Primary Containment Isolation Valve Position Indication VALVE VALVE DESCRIPTION LOCATION NUMBER 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)

Brunswick Unit 2 B-11 Revision No. 23

TRM TS Instrument List Appendix B TRM Table 3.3.3.1-2 (page 5 of 5)

Primary Containment Isolation Valve Position Indication VALVE VALVE DESCRIPTION LOCATION NUMBER 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 Brunswick Unit 2 B-12 Revision No. 24

TRM TS Instrument List Appendix B TRM Table 3.3.3.2-1 (page 1 of 1)

Remote Shutdown Monitoring Instrumentation TECHNICAL APPLICABLE SPECIFICATION INSTRUMENT FUNCTION NUMBER(S)

1. Reactor Vessel Pressure C32-PI-3332, C32-PT-3332

2. Reactor Vessel Water Level B21-LT-N017D-3, B21-LSH-N017D-3 B21-LI-3331, B21-LI-R604BX, B21-LT-3331, B21-LT-N026B

3. Suppression Chamber Water Level CAC-LI-3342, CAC-LT-3342

4. Suppression Chamber Water Temperature CAC-TR-778-6 or CAC-TR-778-7

5. Drywell Pressure CAC-PI-3341, CAC-PT-3341

6. Drywell Temperature CAC-TR-778-1 or CAC-TR-778-3 or CAC-TR-778-4

7. Residual Heat Removal System Flow E11-FT-3338, E11-FI-3338, E11-FY-3338 Brunswick Unit 2 B-13 Revision No. 23

TRM TS Instrument List Appendix B TRM Table 3.3.4.1-1 (page 1 of 1)

Anticipated Transient Without Scram Recirculation Pump Trip Instrumentation APPLICABLE TECHNICAL INSTRUMENT NOMINAL SPECIFICATION NUMBER(S) TRIP FUNCTION SETPOINT

1. Reactor Vessel Water LevelLow Level 2 B21-LT-N024A-2, B-2 105 inches B21-LT-N025A-2, B-2 B21-LTM-N024A-2, B-2 B21-LTM-N025A-2, B-2

2. Reactor Vessel Steam Dome PressureHigh B21-PT-N045A, B, C, D 1137.8 psig B21-PTM-N045A, B, C, D Brunswick Unit 2 B-14 Revision No. 23

TRM TS Instrument List Appendix B TRM Table 3.3.5.1-1 (page 1 of 2)

Emergency Core Cooling System Instrumentation TECHNICAL APPLICABLE NOMINAL SPECIFICATION INSTRUMENT TRIP FUNCTION NUMBER(S) SETPOINT

1. Core Spray System

a. Reactor Vessel Water LevelLow Level 3 B21-LT-N031A, B, C, D 45 inches B21-LTS-N031A-4, B-4, C-4, D-4

b. Drywell PressureHigh E11-PT-N011A, B, C, D 1.7 psig E11-PTS-N011A-2, B-2, C-2, D-2

c. Reactor Steam Dome PressureLow B21-PT-N021A, B, C, D, 410 psig B21-PTS-N021A-2, B-2, C-2, D-2

d. Core Spray Pump StartTime Delay Relay E21-K16A, B 15 seconds STR/2A-1, STR/2A-2 STR/2B-1, STR/2B-2

2. Low Pressure Coolant Injection (LPCI) System

a. Reactor Vessel Water LevelLow Level 3 B21-LT-N031A, B, C, D 45 inches B21-LTS-N031A-4, B-4, C-4, D-4

b. Drywell PressureHigh E11-PT-N011A, B, C, D 1.7 psig E11-PTM-N011A-1, B-1, C-1, D-1

c. Reactor Steam Dome PressureLow B21-PT-N021A, B, C, D 410 psig B21-PTS-N021A-2, B-2, C-2, D-2

d. Reactor Steam Dome PressureLow (Recirculation Pump B21-PT-N021A, B, C, D 310 psig Discharge Valve Permissive) B21-PTM-N021A-1, B-1, C-1, D-1

e. Reactor Vessel Shroud Level B21-LT-N036, B21-LT-N037 -47.4 inches B21-LTM-N036-1, B21-LTM-N037-1

f. RHR Pump StartTime Delay Relay STR/2A-1, STR/2A-2, STR/2B-1, 10 seconds STR/2B-2, STR/1A-3, STR/1A-4, STR/1B-3, STR/1B-4

3. High Pressure Coolant Injection (HPCI) System

a. Reactor Vessel Water LevelLow Level 2 B21-LT-N031A, B, C, D 105 inches B21-LTS-N031A-2, B-2, C-2, D-2

b. Drywell PressureHigh E11-PT-N011A, B, C, D 1.7 psig E11-PTS-N011A-2, B-2, C-2, D-2 (continued)

Brunswick Unit 2 B-15 Revision No. 23

TRM TS Instrument List Appendix B TRM Table 3.3.5.1-1 (page 2 of 2)

Emergency Core Cooling System Instrumentation TECHNICAL APPLICABLE NOMINAL SPECIFICATION INSTRUMENT TRIP FUNCTION NUMBER(S) SETPOINT

3. High Pressure Coolant Injection (HPCI) System (continued)

c. Reactor Vessel Water LevelHigh B21-LT-N017 B-2, D-2 206 inches B21-LTM-N017 B-2, D-2

d. Condensate Storage Tank LevelLow E41-LS-N0O2, E41-LS-N003 23 feet 5 inches

e. Suppression Chamber Water LevelHigh E41-LSH-N015A, B -25 inches

4. Automatic Depressurization System (ADS) Trip System A

a. Reactor Vessel Water LevelLow Level 3 B21-LT-N031B, D 45 inches B21-LTS-N031B-3, D-3

b. ADS Timer B21-TDPU-K5A 83 seconds

c. Reactor Vessel Water LevelLow Level 1 B21-LT-N042B 166 inches B21-LTM-N042B-1

d. Core Spray Pump Discharge PressureHigh E21-PS-N008B 115 psig E21-PS-N009B

e. RHR (LPCI Mode) Pump Discharge PressureHigh E11-PS-N016B, D 115 psig E11-PS-N020B, D

5. ADS Trip System B

a. Reactor Vessel Water LevelLow Level 3 B21-LT-N031A, C 45 inches B21-LTS-N031A-3, C-3

b. ADS Timer B21-TDPU-K5B 83 seconds

c. Reactor Vessel Water LevelLow Level 1 B21-LT-N042A 166 inches B21-LTM-N042A-1

d. Core Spray Pump Discharge PressureHigh E21-PS-N008A 115 psig E21-PS-N009A

e. RHR (LPCI Mode) Pump Discharge PressureHigh E11-PS-N016A, C 115 psig E11-PS-N020A, C Brunswick Unit 2 B-16 Revision No. 23

TRM TS Instrument List Appendix B TRM Table 3.3.5.2-1 (page 1 of 1)

Reactor Core Isolation Cooling System Instrumentation TECHNICAL APPLICABLE NOMINAL SPECIFICATION INSTRUMENT TRIP FUNCTION NUMBER(S) SETPOINT

1. Reactor Vessel Water LevelLow Level 2 B21-LT-N031A, B, C, D 105 inches B21-LTM-N031A-1, B-1, C-1, D-1

2. Reactor Vessel Water LevelHigh B21-LT-N017A-2, C-2 206 inches B21-LTM-N017A-2, C-2

3. Condensate Storage Tank LevelLow E51-LSL-4463 23 feet E51-LSL-4464 1 inch Brunswick Unit 2 B-17 Revision No. 23

TRM TS Instrument List Appendix B TRM Table 3.3.6.1-1 (page 1 of 5)

Primary Containment Isolation Instrumentation TECHNICAL APPLICABLE NOMINAL SPECIFICATION INSTRUMENT TRIP FUNCTION NUMBER(S) SETPOINT

1. Main Steam Line Isolation

a. Reactor Vessel Water LevelLow Level 3 B21-LT-N024A-1, B-1 45 inches B21-LT-N025A-1, B-1 B21-LTS-N024A-1-2, B-1-2 B21-LTS-N025A-1-2, B-1-2

b. Main Steam Line PressureLow B21-PT-N015A, B, C, D 835 psig B21-PTM-N015A-1, B-1, C-1, D-1

c. Main Steam Line FlowHigh B21-PDT-N006A, B, C, D 137% rated steam flow 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

d. Condenser VacuumLow B21-PT-N056A, B, C, D 10 inches Hg vacuum B21-PTM-N056A-1, B-1, C-1, D-1

e. Main Steam Isolation Valve Pit TemperatureHigh B21-TS-N010A, B, C, D 190°F

f. Main Steam Line FlowHigh (Not in Run) B21-PDTS-N006A-2 30% rated steam flow B21-PDTS-N007B-2 B21-PDTS-N008C-2 B21-PDTS-N009D-2

2. Primary Containment Isolation

a. Reactor Vessel Water LevelLow Level 1 B21-LT-N017A-1, B-1, C-1, D-1 166 inches B21-LTM-N017A-1, B-1, C-1, D-1

b. Drywell PressureHigh C72-PT-N002A, B, C, D 1.7 psig 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

c. Main Stack RadiationHigh 2-D12-RM-80S (a)

d. Reactor Building Exhaust RadiationHigh D12-RM-K609A, B 4 mR/hr D12-RE-N010A, B (continued)

(a) Nominal Trip Setpoint established in accordance with the methodology in the Offsite Dose Calculation Manual.

Brunswick Unit 2 B-18 Revision No. 28

TRM TS Instrument List Appendix B TRM Table 3.3.6.1-1 (page 2 of 5)

Primary Containment Isolation Instrumentation TECHNICAL APPLICABLE NOMINAL SPECIFICATION INSTRUMENT TRIP FUNCTION NUMBER(S) SETPOINT

3. High Pressure Coolant Injection (HPCI) System Isolation

a. HPCI Steam Line FlowHigh E41-PDTM-N004-1, E41-PDTM-N005-1 220% rated steam flow E41-PDTS-N004-2, E41-PDTS-N005-2

b. HPCI Steam Line FlowHigh Time Delay Relay E41-TDR-K33, E41-TDR-K43 5 seconds

c. HPCI Steam Supply Line PressureLow E41-PSL-N001A, B, C, D 115 psig

d. HPCI Turbine Exhaust Diaphragm PressureHigh E41-PSH-N012A, B, C, D 7 psig

e. Drywell PressureHigh E11-PT-N011C, D 1.7 psig E11-PTS-N011C-2, D-2

f. HPCI Steam Line Area TemperatureHigh B21-XY-5948A 165°F Ch. A5-2: E41-TE-3488 B21-XY-5948B Ch. A5-2: E41-TE-3489

g. HPCI Steam Line Tunnel Ambient TemperatureHigh B21-XY-5948A Ch. A2-2: E41-TE-3314 165°F Ch. A5-1: E51-TE-N025C 190°F B21-XY-5948B Ch. A5-1: E51-TE-N025D 190°F

h. HPCI Steam Line Tunnel Differential TemperatureHigh B21-XY-5948A 47°F Ch. A6-1: E51-TE-N026C and E51-TE-N027C B21-XY-5948B Ch. A6-1: E51-TE-N026D and E51-TE-N027D

i. HPCI Equipment Area TemperatureHigh B21-XY-5948A 165°F 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 (continued)

Brunswick Unit 2 B-19 Revision No. 23

TRM TS Instrument List Appendix B TRM Table 3.3.6.1-1 (page 3 of 5)

Primary Containment Isolation Instrumentation TECHNICAL APPLICABLE NOMINAL SPECIFICATION INSTRUMENT TRIP FUNCTION NUMBER(S) SETPOINT

4. Reactor Core Isolation Cooling (RCIC) System Isolation

a. RCIC Steam Line FlowHigh E51-PDTM-N017-1, E51-PDTM-N018-1 220% rated steam flow E51-PDTS-N017-2, E51-PDTS-N018-2

b. RCIC Steam Line FlowHigh Time Delay Relay E51-TDR-K32, E51-TDR-K12 5 seconds

c. RCIC Steam Supply Line PressureLow E51-PS-N019A, B, C, D 70

d. RCIC Turbine Exhaust Diaphragm PressureHigh E51-PS-N012A, B, C, D 5 psig

e. Drywell PressureHigh E11-PT-N011A, B 1.7 psig E11-PTS-N011A-2, B-2

f. RCIC Steam Line Area TemperatureHigh B21-XY-5949A 165°F Ch. A6-4: E51-TE-3487 B21-XY-5949B Ch. A4-4: E51-TE-3320

g. RCIC Steam Line Tunnel Ambient TemperatureHigh B21-XY-5949A Ch. A3-4: E51-TE-3319 165°F Ch. A3-3: E51-TE-N025A 190°F B21-XY-5949B Ch. A3-3: E51-TE-N025B 190°F

h. RCIC Steam Line Tunnel and Area TemperatureHigh Time B21-XY-5949A 27 minutes Delay 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

i. RCIC Steam Line Tunnel Differential TemperatureHigh B21-XY-5949A 47°F Ch. A4-3: E51-TE-N026A and E51-TE-N027A B21-XY-5949B Ch. A4-3: E51-TE-N026B and E51-TE-N027B (continued)

Brunswick Unit 2 B-20 Revision No. 23

TRM TS Instrument List Appendix B TRM Table 3.3.6.1-1 (page 4 of 5)

Primary Containment Isolation Instrumentation TECHNICAL APPLICABLE NOMINAL SPECIFICATION INSTRUMENT TRIP FUNCTION NUMBER(S) SETPOINT

4. RCIC System Isolation (continued)

j. RCIC Equipment Area TemperatureHigh B21-XY-5949A 165°F 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

k. RCIC Equipment Area Differential TemperatureHigh B21-XY-5949A 47°F Ch. A2-3: E51-TE-N021A and E51-TE-N022A B21-XY-5949B Ch. A2-3: E51-TE-N021B and E51-TE-N022B

5. Reactor Water Cleanup (RWCU) System Isolation

a. Differential FlowHigh B21-XY-5949B 43 gpm G31-FT-N012 G31-FT-N041 G31-FT-N036

b. Differential FlowHigh Time Delay B21-XY-5949B 28.5 minutes G31-FT-N012 G31-FT-N041 G31-FT-N036

c. Area TemperatureHigh B21-XY-5949A 140°F 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

d. Area Ventilation Differential TemperatureHigh B21-XY-5949A 47°F 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 (continued)

Brunswick Unit 2 B-21 Revision No. 23

TRM TS Instrument List Appendix B TRM Table 3.3.6.1-1 (page 5 of 5)

Primary Containment Isolation Instrumentation TECHNICAL APPLICABLE NOMINAL SPECIFICATION INSTRUMENT TRIP FUNCTION NUMBER(S) SETPOINT

5. Reactor Water Cleanup (RWCU) System Isolation (continued)

e. Piping Outside RWCU Rooms Area TemperatureHigh B21-XY-5949A 115°F Ch. A1-2: G31-TE-5931 B21-XY-5949B Ch. A1-2: G31-TE-5932

f. SLC System Initiation C41A-S1 NA

g. Reactor Vessel Water LevelLow Level 2 B21-LT-N024A-1, B-1 105 inches B21-LT-N025A-1, B-1 B21-LTM-N024A-1-1, B-1-1 B21-LTM-N025A-1-1, B-1-1

6. RHR Shutdown Cooling System Isolation

a. Reactor Steam Dome PressureHigh B32-PS-N018A-1, B 130.8 psig

b. Reactor Vessel Water Level Low Level 1 B21-LT-N017A-1, B-1, C-1, D-1 166 inches B21-LTM-N017A-1, B-1, C-1, D-1

7. Traversing In-Core Probe Isolation

a. Reactor Vessel Water Level-Low Level 1 B21-LT-N017A-1, B-1 166 inches B21-LTM-N017A-1, B-1

b. Drywell Pressure-High C72-PT-N002A, B 1.7 psig C72-PTM-N002A-1, B-1 Brunswick Unit 2 B-22 Revision No. 48

TRM TS Instrument List Appendix B TRM Table 3.3.6.2-1 (page 1 of 1)

Secondary Containment Isolation Instrumentation TECHNICAL APPLICABLE NOMINAL SPECIFICATION INSTRUMENT TRIP FUNCTION NUMBER(S) SETPOINT

1. Reactor Vessel Water LevelLow Level 2 B21-LT-N024A-1, B-1 105 inches B21-LT-N025A-1, B-1 B21-LTM-N024A-1-1, B-1-1 B21-LTM-N025A-1-1, B-1-1

2. Drywell PressureHigh C72-PT-N002A, B, C, D 1.7 psig C72-PTM-N002A-1, B-1, C-1, D-1

3. Reactor Building Exhaust RadiationHigh D12-RE-N010A, B 4 mR/hr D12-RM-K609A, B Brunswick Unit 2 B-23 Revision No. 23

TRM TS Instrument List Appendix B TRM Table 3.3.7.1-1 (page 1 of 1)

Control Room Emergency Ventilation System Instrumentation TECHNICAL APPLICABLE NOMINAL SPECIFICATION INSTRUMENT TRIP FUNCTION NUMBER(S) SETPOINT

1. Control Building Air Intake RadiationHigh 1-D22-RM-K600-1-2, 1-D22-RE-N001-1-2 7 mR/hr 1-D22-RM-K600-1-3, 1-D22-RE-N001-1-3

2. Unit 2 Secondary Containment Isolation - CREV Auto-Start

a. Reactor Vessel Water LevelLow Level 2 B21-LT-N024A-1, B-1 105 inches B21-LT-N025A-1, B-1 B21-LTM-N024A-1-1, B-1-1 B21-LTM-N025A-1-1, B-1-1

b. Drywell PressureHigh C72-PT-N002A, B, C, D 1.7 psig C72-PTM-N002A-1, B-1, C-1, D-1 Brunswick Unit 2 B-24 Revision No. 34

TRM TS Instrument List Appendix B TRM Table 3.3.7.2-1 (page 1 of 1)

Condenser Vacuum Pump Isolation Instrumentation TECHNICAL APPLICABLE NOMINAL SPECIFICATION INSTRUMENT TRIP FUNCTION NUMBER(S) SETPOINT

1. Main Steam Line RadiationHigh D12-RM-K603A, B, C, D 2.8 times background radiation (mR/hr)

Brunswick Unit 2 B-25 Revision No. 23

TRM TS Instrument List Appendix B TRM Table 3.3.8.1-1 (page 1 of 1)

Loss of Power Instrumentation TECHNICAL APPLICABLE NOMINAL SPECIFICATION INSTRUMENT TRIP FUNCTION NUMBER(S) SETPOINT

1. 4.16 kV Emergency Bus Undervoltage (Loss of Voltage)

a. Bus Undervoltage Relay Type - IAV53K 3255 V(a)

Device Number - 27/59E 93 V(b)(c)

b. Time Delay Relay Type - IAV53K 1.15 seconds(e)

Device Number - 27/59E

2. 4.16 kV Emergency Bus Undervoltage (Degraded Voltage)

a. Bus Undervoltage Device Number - 27/DV 3732 V(a)

(b)(d) 106.64 V

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.

Brunswick Unit 2 B-26 Revision No. 63

TRM TS Instrument List Appendix B TRM Table 3.3.8.2-1 (page 1 of 1)

Reactor Protection System (RPS) Electric Power Monitoring TECHNICAL APPLICABLE NOMINAL SPECIFICATION INSTRUMENT TRIP FUNCTION NUMBER(S) 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 Brunswick Unit 2 B-27 Revision No. 64

TRM TS Instrument List Appendix B TRM Table 3.4.4-1 (page 1 of 1)

Reactor Coolant System Operational LEAKAGE TECHNICAL APPLICABLE SPECIFICATION INSTRUMENT FUNCTION 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 Brunswick Unit 2 B-28 Revision No. 23

TRM TS Instrument List Appendix B TRM Table 3.4.5-1 (page 1 of 1)

Reactor Coolant System Leakage Detection Instrumentation TECHNICAL APPLICABLE SPECIFICATION INSTRUMENT FUNCTION 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 B-29 Revision No. 23

APPENDIX C TECHNICAL REQUIREMENTS MANUAL (TRM) INSTRUMENT LIST Brunswick Unit 2 Revision No. 23

TRM TRM Instrument List Appendix C 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.

Brunswick Unit 2 C-1 Revision No. 23

TRM TRM Instrument List Appendix C TRM Table 3.3-2 (page 1 of 1)

Control Rod Block Instrumentation TRM APPLICABLE TRIP FUNCTION INSTRUMENT SETPOINT NUMBER(S)

1. Average Power Range Monitors

a. Simulated Thermal Power - High C51-APRM1-AR51 0.55W + 53.5% RTP (a)

C51-APRM2-AR31 and 108.0% RTP C51-APRM3-AR41 C51-APRM4-AR11

b. Inoperative C51-APRM1-AR51 NA C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11

c. Downscale C51-APRM1-AR51 2.4% RTP C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11

d. Simulated Thermal Power - High (Setdown) C51-APRM1-AR51 12.0% RTP C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11

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 105 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 NA C51-IRM-E, F, G, H

b. Upscale C51-IRM-A, B, C, D 108/125 of full scale C51-IRM-E, F, G, H

c. Inoperative C51-IRM-A, B, C, D NA C51-IRM-E, F, G, H

d. Downscale C51-IRM-A, B, C, D 3/125 of full scale C51-IRM-E, F, G, H

4. Scram Discharge Volume Water LevelHigh 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.

Brunswick Unit 2 C-2 Revision No. 44

TRM TRM Instrument List Appendix C TRM Table 3.4-2 (page 1 of 1)

Accident Monitoring Instrumentation TRM APPLICABLE FUNCTION 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. PrimarySonic B21-FY-4157 Thru 4167

b. SecondaryTemperature B21-TR-R614 Points 1 Thru 11 (d)

4. Turbine Building Ventilation Monitor D12-RE-4563, D12-RR-4548-3 D12-RE-4562, D12-RR-4548-2 D12-RE-4561, D12-RR-4548-1 (d)

5. Offgas Stack Ventilation Monitor 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 CAC-AT-4409-38, CAC-AR-4409-41/42 (e)

H2 Analyzer (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 CAC-AT-4409-37, CAC-AR-4409-41/42 (e)

O2 Analyzer (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.

Brunswick Unit 2 C-3 Revision No. 61

TRM TRM Instrument List Appendix C TRM Table 3.5-2 (page 1 of 1)

Chloride Intrusion Monitors TRM APPLICABLE TRIP FUNCTION INSTRUMENT SETPOINT NUMBER(S)

1. Chloride Leak Detectors in the Condenser Hotwell Outlet Headers CO-CR-24 1.0 mhos/cm CO-CIT-24A, CO-CIT-24B CO-CE-24-1, CO-CE-24-2, CO-CE-24-3, CO-CE-24-4

2. Chloride Leak Detector in the Condensate Pump Discharge

a. Wide Range Monitor CO-CIS-3075-1 2.0 mhos/cm

b. Narrow Range Monitor TS-CIT-863-3 0.3 mhos/cm

3. Chloride Leak Detector in the Inlet to the Condensate Filter CFD-CIT-1 0.3 mhos/cm Demineralizer

4. Chloride Leak Detector in the Inlet to the Deep Bed Demineralizer CDD-CIT-1 0.3 mhos/cm Brunswick Unit 2 C-4 Revision No. 28

TRM TRM Instrument List Appendix C TRM Table 3.6-2 (page 1 of 1)

Bus Power Monitors TRM APPLICABLE FUNCTION 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 Brunswick Unit 2 C-5 Revision No. 23

TRM TRM Instrument List Appendix C TRM Table 3.7-1 (page 1 of 1)

Automatic Depressurization System (ADS) Inhibit Switch TRM APPLICABLE FUNCTION INSTRUMENT NUMBER(S)

1. ADS Inhibit Switch A B21-CS-S5A

2. ADS Inhibit Switch B B21-CS-S5B Brunswick Unit 2 C-6 Revision No. 23

TRM TRM Instrument List Appendix C TRM Table 3.8-1 (page 1 of 1)

Suppression Chamber Water Temperature Instrumentation TRM APPLICABLE TRIP FUNCTION INSTRUMENT SETPOINT NUMBER(S)

1. Suppression Chamber Water Temperature CAC-TE-4426-2 Thru 13, 95°F CAC-TY-4426-1, CAC-TR-4426-1A CAC-TE-4426-15 Thru 26, CAC-TY-4426-2, CAC-TR-4426-2A Brunswick Unit 2 C-7 Revision No. 23

TRM TRM Instrument List Appendix C TRM Table 3.9-2 (page 1 of 1)

Seismic Monitoring Instrumentation TRM APPLICABLE FUNCTION 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) 2-ENV-XRH-823-2

c. Reactor Building Refueling Area (+117' level) 2-ENV-XRH-823-3

2. Active Triaxial Accelerometers

a. Reactor Building (+89' 4" level) 2-ENV-XT-823-2

b. Reactor Building (-17' level) 2-ENV-XT-823-1

3. Active Seismic Recording System

a. Control Room 2-ENV-XT-823 Brunswick Unit 2 C-8 Revision No. 47

TRM TRM Instrument List Appendix C TRM Table 3.10-1 (page 1 of 1)

Intake Canal High Water Level Instrumentation TRM APPLICABLE FUNCTION 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 Brunswick Unit 2 C-9 Revision No. 52

TRM TRM Instrument List Appendix C TRM Table 3.11-2 (page 1 of 1)

Primary Containment Isolation Instrumentation TRM APPLICABLE TRIP FUNCTION INSTRUMENT SETPOINT NUMBER(S)

1. Main Steam Line Tunnel TemperatureHigh B21-TE-N011A, B, C, D 190°F B21-TE-N012A, B, C, D B21-TE-N013A, B, C, D

2. Turbine Building Area TemperatureHigh B21-TE-3225A, B, C, D 190°F 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 Brunswick Unit 2 C-10 Revision No. 51

TRM TRM Instrument List Appendix C TRM Table 3.12-2 (page 1 of 1)

Control Room Emergency Ventilation System Instrumentation TRM APPLICABLE TRIP FUNCTION INSTRUMENT SETPOINT NUMBER(S)

1. Chlorine Isolation

a. Control Building Air Intake (Local) 1-X-AT-2977 5 ppm 2-X-AT-2977 1-X-AT-2977-1 2-X-AT-2977-1

b. Chlorine Tank Car Area (Remote) 1-X-AT-2979 5 ppm 2-X-AT-2979 1-X-AT-2979-1 2-X-AT-2979-1

2. Control Room Envelope Smoke Protection

a. Control Building Intake Air Duct Smoke Detectors 2-FP-CB-4-22 NA 2-FP-CB-4-23 Brunswick Unit 2 C-11 Revision No. 57

APPENDIX D PRIMARY CONTAINMENT ISOLATION VALVE (PCIV) LIST Brunswick Unit 2 Revision No. 23

TRM PCIV List Appendix D 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 Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges," provides 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 Requirements. 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.

Brunswick Unit 2 D-1 Revision No. 23

TRM PCIV List Appendix D 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 DESCRIPTION APPLICABLE TS SURVEILLANCE NUMBER CONDITION(S) 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)

Brunswick Unit 2 D-2 Revision No. 26

TRM PCIV List Appendix D 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 DESCRIPTION APPLICABLE TS SURVEILLANCE FLANGE NUMBER CONDITION(S) 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)

Brunswick Unit 2 D-3 Revision No. 23

TRM PCIV List Appendix D 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 DESCRIPTION APPLICABLE TS SURVEILLANCE NUMBER CONDITION(S) 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)

Brunswick Unit 2 D-4 Revision No. 30

TRM PCIV List Appendix D 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 DESCRIPTION APPLICABLE TS SURVEILLANCE FLANGE NUMBER CONDITION(S) 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 C NA ISOLATION VALVE 2-CAC-IV-1476 CAC-LG-4336 SUPPRESSION POOL LEVEL SIGHT GLASS LINE UPPER C NA ISOLATION VALVE 2-CAC-IV-1481 SURGE VOLUME RESERVOIR LEVEL GAUGE CAC-LG-5121 UPPER C NA ISOLATION VALVE 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)

Brunswick Unit 2 D-5 Revision No. 26

TRM PCIV List Appendix D 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 DESCRIPTION APPLICABLE TS SURVEILLANCE FLANGE NUMBER CONDITION(S) 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 C NA ISOLATION VALVE 2-CAC-IV-2118 SURGE VOLUME RESERVOIR LEVEL GAUGE CAC-LG-5121 LOWER C NA ISOLATION VALVE 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)

Brunswick Unit 2 D-6 Revision No. 26

TRM PCIV List Appendix D 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 DESCRIPTION APPLICABLE TS SURVEILLANCE FLANGE NUMBER CONDITION(S) REQUIREMENTS 2-CAC-V186 SURGE VOLUME RESERVOIR LEVEL GAUGE CAC-LG-5776 ISOLATION C NA VALVE 2-C12-F101 HCU INSERT HEADER VENT VALVE C SR 3.6.1.3.1 (XX-XX) 2-C12-F102 HCU WITHDRAW HEADER VENT VALVE C SR 3.6.1.3.1 (XX-XX) 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 RELIEF VALVE BLANK FLANGE C NA 2-E11-F055B RHR HEAT EXCHANGER 2B RELIEF 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)

Brunswick Unit 2 D-7 Revision No. 26

TRM PCIV List Appendix D 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 DESCRIPTION APPLICABLE TS SURVEILLANCE NUMBER CONDITION(S) 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)

Brunswick Unit 2 D-8 Revision No. 23

TRM PCIV List Appendix D 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 DESCRIPTION APPLICABLE TS SURVEILLANCE FLANGE NUMBER CONDITION(S) 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)

Brunswick Unit 2 D-9 Revision No. 42

TRM PCIV List Appendix D 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 DESCRIPTION APPLICABLE TS SURVEILLANCE FLANGE NUMBER CONDITION(S) 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)

Brunswick Unit 2 D-10 Revision No. 26

TRM PCIV List Appendix D 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 DESCRIPTION APPLICABLE TS SURVEILLANCE FLANGE NUMBER CONDITION(S) 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)

Brunswick Unit 2 D-11 Revision No. 26

TRM PCIV List Appendix D 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 DESCRIPTION APPLICABLE TS SURVEILLANCE FLANGE NUMBER CONDITION(S) 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 A, B NA VALVE 2-RNA-V351 DIV I NON-INTERRUPTIBLE INSTRUMENT AIR SUPPLY INBOARD CHECK A, B NA VALVE 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 Brunswick Unit 2 D-12 Revision No. 26

TRM PCIV List Appendix D TRM Table 3.6.1.3-2 (Page 1 of 9)

Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS SURVEILLANCE ALLOWABLE AUTOMATIC CONDITION(S) REQUIREMENTS ISOLATION TIME ISOLATION (in seconds) GROUP 2-B21-F016 MAIN STEAM LINE DRAIN INBOARD A, B SR 3.6.1.3.4 30 1 ISOLATION SR 3.6.1.3.6 2-B21-F019 MAIN STEAM LINE DRAIN OUTBOARD A, B SR 3.6.1.3.4 30 1 ISOLATION SR 3.6.1.3.6 2-B21-F022A INBOARD MSIV A A, B, D SR 3.6.1.3.5 3 and 5 1 SR 3.6.1.3.6 SR 3.6.1.3.9 2-B21-F022B INBOARD MSIV B A, B, D SR 3.6.1.3.5 3 and 5 1 SR 3.6.1.3.6 SR 3.6.1.3.9 2-B21-F022C INBOARD MSIV C A, B, D SR 3.6.1.3.5 3 and 5 1 SR 3.6.1.3.6 SR 3.6.1.3.9 2-B21-F022D INBOARD MSIV D A, B, D SR 3.6.1.3.5 3 and 5 1 SR 3.6.1.3.6 SR 3.6.1.3.9 2-B21-F028A OUTBOARD MSIV A A, B, D SR 3.6.1.3.5 3 and 5 1 SR 3.6.1.3.6 SR 3.6.1.3.9 2-B21-F028B OUTBOARD MSIV B A, B, D SR 3.6.1.3.5 3 and 5 1 SR 3.6.1.3.6 SR 3.6.1.3.9 2-B21-F028C OUTBOARD MSIV C A, B, D SR 3.6.1.3.5 3 and 5 1 SR 3.6.1.3.6 SR 3.6.1.3.9 2-B21-F028D OUTBOARD MSIV D A, B, D SR 3.6.1.3.5 3 and 5 1 SR 3.6.1.3.6 SR 3.6.1.3.9 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 5 1 SR 3.6.1.3.6 2-B32-F020 SAMPLE LINE OUTBOARD ISOLATION A, B SR 3.6.1.3.4 5 1 SR 3.6.1.3.6 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 15 6 SR 3.6.1.3.6 (continued)

(a) Allowable Isolation Time specified in the Inservice Testing Program.

Brunswick Unit 2 D-13 Revision No. 23

TRM PCIV List Appendix D TRM Table 3.6.1.3-2 (Page 2 of 9)

Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS SURVEILLANCE ALLOWABLE AUTOMATIC CONDITION(S) REQUIREMENTS ISOLATION TIME ISOLATION (in seconds) GROUP 2-CAC-SV-1205E CAC-AT-4409 PRIMARY CONTAINMENT A, B SR 3.6.1.3.4 15 6(b)

INBOARD SAMPLE SR 3.6.1.3.6 2-CAC-SV-1209A CAC-AT-4409 PRIMARY CONTAINMENT A, B SR 3.6.1.3.4 15 6(b)

INBOARD SAMPLE SR 3.6.1.3.6 2-CAC-SV-1209B CAC-AT-4409 PRIMARY CONTAINMENT A, B SR 3.6.1.3.4 15 6(b)

INBOARD SAMPLE SR 3.6.1.3.6 2-CAC-SV-1211E CAC-AT-1262 INBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-SV-1211F CAC-AT-1262 INBOARD SAMPLE INLET A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-SV-1213A CAC-AT-4409 TORUS INBOARD SAMPLE A, B SR 3.6.1.3.4 15 6(b)

SR 3.6.1.3.6 (b) 2-CAC-SV-1215E CAC-AT-4409 INBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-SV-1218A CAC-AT-4410 TORUS INBOARD SAMPLE A, B SR 3.6.1.3.4 15 6(b)

SR 3.6.1.3.6 2-CAC-SV-1225B COMMON INBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-SV-1227A CAC-AT-4410 PRIMARY CONTAINMENT A, B SR 3.6.1.3.4 15 6(b)

INBOARD SAMPLE SR 3.6.1.3.6 2-CAC-SV-1227B CAC-AT-4410 PRIMARY CONTAINMENT A, B SR 3.6.1.3.4 15 6(b)

INBOARD SAMPLE SR 3.6.1.3.6 2-CAC-SV-1227C CAC-AT-1260 INBOARD SAMPLE INLET A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-SV-1227E CAC-AT-4410 PRIMARY CONTAINMENT A, B SR 3.6.1.3.4 15 6(b)

INBOARD SAMPLE SR 3.6.1.3.6 (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.

Brunswick Unit 2 D-14 Revision No. 49

TRM PCIV List Appendix D TRM Table 3.6.1.3-2 (Page 3 of 9)

Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS SURVEILLANCE ALLOWABLE AUTOMATIC CONDITION(S) REQUIREMENTS ISOLATION TIME ISOLATION (in seconds) GROUP 2-CAC-SV-1231B CAC-AT-4410 INBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 15 6(b)

SR 3.6.1.3.6 2-CAC-SV-1260 CAC-AT-1260 OUTBOARD SAMPLE INLET A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-SV-1261 CAC-AT-1261 OUTBOARD SAMPLE INLET A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-SV-1262 CAC-AT-1262 OUTBOARD SAMPLE INLET A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-SV-3439 CAC-AT-1262 OUTBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-SV-3440 COMMON OUTBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-SV-4409-1 CAC-AT-4409 TORUS OUTBOARD SAMPLE A, B SR 3.6.1.3.4 15 6(b)

SR 3.6.1.3.6 2-CAC-SV-4409-2 CAC-AT-4409 PRIMARY CONTAINMENT A, B SR 3.6.1.3.4 15 6(b)

OUTBOARD SAMPLE SR 3.6.1.3.6 2-CAC-SV-4409-3 CAC-AT-4409 PRIMARY CONTAINMENT A, B SR 3.6.1.3.4 15 6(b)

OUTBOARD SAMPLE SR 3.6.1.3.6 2-CAC-SV-4409-4 CAC-AT-4409 PRIMARY CONTAINMENT A, B SR 3.6.1.3.4 15 6(b)

OUTBOARD SAMPLE SR 3.6.1.3.6 2-CAC-SV-4410-1 CAC-AT-4410 TORUS OUTBOARD SAMPLE A, B SR 3.6.1.3.4 15 6(b)

SR 3.6.1.3.6 2-CAC-SV-4410-2 CAC-AT-4410 PRIMARY CONTAINMENT A, B SR 3.6.1.3.4 15 6(b)

OUTBOARD SAMPLE SR 3.6.1.3.6 2-CAC-SV-4410-3 CAC-AT-4410 PRIMARY CONTAINMENT A, B SR 3.6.1.3.4 15 6(b)

OUTBOARD SAMPLE SR 3.6.1.3.6 (b) 2-CAC-SV-4410-4 CAC-AT-4410 PRIMARY CONTAINMENT A, B SR 3.6.1.3.4 15 6 OUTBOARD SAMPLE SR 3.6.1.3.6 2-CAC-SV-4540 CAC-AT-4409 OUTBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 15 6(b)

SR 3.6.1.3.6 2-CAC-SV-4541 CAC-AT-4410 OUTBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 15 6(b)

SR 3.6.1.3.6 (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.

Brunswick Unit 2 D-15 Revision No. 49

TRM PCIV List Appendix D TRM Table 3.6.1.3-2 (Page 4 of 9)

Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS SURVEILLANCE ALLOWABLE AUTOMATIC CONDITION(S) REQUIREMENTS ISOLATION TIME ISOLATION (in seconds) GROUP 2-CAC-V4 INBOARD PRIMARY CONTAINMENT N2 A, B SR 3.6.1.3.4 15 6 INERTING INLET SR 3.6.1.3.6 2-CAC-V5 SUPPRESSION POOL N2 INLET A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-V6 DRYWELL N2 INLET A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-V7 INBOARD SUPPRESSION POOL PURGE A, B SR 3.6.1.3.4 15 6 EXHAUST SR 3.6.1.3.6 2-CAC-V8 OUTBOARD SUPPRESSION POOL PURGE A, B SR 3.6.1.3.4 15 6 EXHAUST SR 3.6.1.3.6 2-CAC-V9 INBOARD DRYWELL PURGE EXHAUST A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-V10 OUTBOARD DRYWELL PURGE EXHAUST A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-V15 PRIMARY CONTAINMENT PURGE AIR INLET A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-V22 SUPPRESSION POOL 2" EXHAUST A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-V23 DRYWELL 2" EXHAUST A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-V49 DRYWELL HEAD INBOARD PURGE A, B SR 3.6.1.3.4 15 6 EXHAUST SR 3.6.1.3.6 2-CAC-V50 DRYWELL HEAD OUTBOARD PURGE A, B SR 3.6.1.3.4 15 6 EXHAUST SR 3.6.1.3.6 2-CAC-V55 DRYWELL CAD N2 INJECTION SOLENOID A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-V56 DRYWELL CAD N2 INJECTION SOLENOID A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-V160 SUPPRESSION POOL CAD N2 INJECTION A, B SR 3.6.1.3.4 15 6 INLET SR 3.6.1.3.6 2-CAC-V161 DRYWELL CAD N2 INJECTION INLET A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-V162 SUPPRESSION POOL CAD N2 INJECTION A, B SR 3.6.1.3.4 15 6 INLET SR 3.6.1.3.6 2-CAC-V163 DRYWELL CAD N2 INJECTION INLET A, B SR 3.6.1.3.4 15 6 SR 3.6.1.3.6 2-CAC-V172 SUPPRESSION POOL PURGE EXHAUST A, B SR 3.6.1.3.4 15 6 SOLENOID SR 3.6.1.3.6 2-CAC-V216 HARDENED WETWELL VENT OUTBOARD A, B SR 3.6.1.3.4 15 6 ISOLATION SR 3.6.1.3.6 (continued)

Brunswick Unit 2 D-16 Revision No. 23

TRM PCIV List Appendix D TRM Table 3.6.1.3-2 (Page 5 of 9)

Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS SURVEILLANCE ALLOWABLE AUTOMATIC CONDITION(S) REQUIREMENTS ISOLATION ISOLATION TIME GROUP (in seconds) 2-C51-J004A A TIP BALL VALVE AND SHEAR VALVE A, B SR 3.6.1.3.3 (a) 2 ASSEMBLY SR 3.6.1.3.4 SR 3.6.1.3.6 SR 3.6.1.3.8 2-C51-J004B B TIP BALL VALVE AND SHEAR VALVE A, B SR 3.6.1.3.3 (a) 2 ASSEMBLY SR 3.6.1.3.4 SR 3.6.1.3.6 SR 3.6.1.3.8 2-C51-J004C C TIP BALL VALVE AND SHEAR VALVE A, B SR 3.6.1.3.3 (a) 2 ASSEMBLY SR 3.6.1.3.4 SR 3.6.1.3.6 SR 3.6.1.3.8 2-C51-J004D D TIP BALL VALVE AND SHEAR VALVE A, B SR 3.6.1.3.3 (a) 2 ASSEMBLY SR 3.6.1.3.4 SR 3.6.1.3.6 SR 3.6.1.3.8 2-E11-F007A MINIMUM FLOW BYPASS VALVE A TO C SR 3.6.1.3.4 (a) NA SUPPRESSION POOL 2-E11-F007B MINIMUM FLOW BYPASS VALVE B TO C SR 3.6.1.3.4 (a) NA SUPPRESSION POOL 2-E11-F008 SHUTDOWN COOLING OUTBOARD A, B SR 3.6.1.3.4 43 8(c)

SUCTION SR 3.6.1.3.6 2-E11-F009 SHUTDOWN COOLING INBOARD SUCTION A, B SR 3.6.1.3.4 30 8(c)

THROTTLE SR 3.6.1.3.6 2-E11-F011A RHR HEAT EXCHANGER 2A DRAIN TO C SR 3.6.1.3.4 (a) NA SUPPRESSION POOL 2-E11-F011B RHR HEAT EXCHANGER 2B DRAIN TO C SR 3.6.1.3.4 (a) NA SUPPRESSION POOL 2-E11-F015A LPCI A INBOARD INJECTION A, B SR 3.6.1.3.4 30 8(c)

SR 3.6.1.3.6 2-E11-F015B LPCI B INBOARD INJECTION A, B SR 3.6.1.3.4 30 8(c)

SR 3.6.1.3.6 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.

Brunswick Unit 2 D-17 Revision No. 59

TRM PCIV List Appendix D TRM Table 3.6.1.3-2 (Page 6 of 9)

Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS SURVEILLANCE ALLOWABLE AUTOMATIC CONDITION(S) REQUIREMENTS ISOLATION TIME ISOLATION (in seconds) 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 A, B SR 3.6.1.3.4 (a) NA ISOLATION 2-E11-F024B SUPPRESSION POOL COOLING B A, B SR 3.6.1.3.4 (a) NA ISOLATION 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 C SR 3.6.1.3.4 (a) NA VENT 2-E11-F103B RHR HEAT EXCHANGER 2B OUTBOARD C SR 3.6.1.3.4 (a) NA VENT (continued)

(a) Allowable Isolation Time specified in the Inservice Testing Program.

Brunswick Unit 2 D-18 Revision No. 23

TRM PCIV List Appendix D TRM Table 3.6.1.3-2 (Page 7 of 9)

Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS SURVEILLANCE ALLOWABLE AUTOMATIC CONDITION(S) REQUIREMENTS ISOLATION ISOLATION TIME GROUP (in seconds) 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 A, B SR 3.6.1.3.4 (a) NA INJECTION 2-E21-F004B CORE SPRAY PUMP 2B OUTBOARD A, B SR 3.6.1.3.4 (a) NA INJECTION 2-E21-F005A CORE SPRAY PUMP 2A INBOARD A, B SR 3.6.1.3.4 (a) NA INJECTION 2-E21-F005B CORE SPRAY PUMP 2B INBOARD A, B SR 3.6.1.3.4 (a) NA INJECTION 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 50 4 SR 3.6.1.3.6 2-E41-F003 HPCI STEAM SUPPLY OUTBOARD A, B SR 3.6.1.3.4 50 4 ISOLATION SR 3.6.1.3.6 2-E41-F006 HPCI INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E41-F012 HPCI MINIMUM FLOW BYPASS TO C SR 3.6.1.3.4 20 NA SUPPRESSION POOL 2-E41-F042 HPCI SUPPRESSION POOL SUCTION C SR 3.6.1.3.4 80 4 SR 3.6.1.3.6 (continued)

(a) Allowable Isolation Time specified in the Inservice Testing Program.

Brunswick Unit 2 D-19 Revision No. 23

TRM PCIV List Appendix D TRM Table 3.6.1.3-2 (Page 8 of 9)

Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS SURVEILLANCE ALLOWABLE AUTOMATIC CONDITION(S) REQUIREMENTS ISOLATION ISOLATION TIME GROUP (in seconds) 2-E41-F075 HPCI TURBINE EXHAUST VACUUM A, B SR 3.6.1.3.4 30 7 BREAKER SR 3.6.1.3.6 2-E41-F079 HPCI TURBINE EXHAUST VACUUM A, B SR 3.6.1.3.4 30 7 BREAKER SR 3.6.1.3.6 2-E51-F007 RCIC STEAM SUPPLY INBOARD ISOLATION A, B SR 3.6.1.3.4 30 5 SR 3.6.1.3.6 2-E51-F008 RCIC STEAM SUPPLY OUTBOARD A, B SR 3.6.1.3.4 30 5 ISOLATION SR 3.6.1.3.6 2-E51-F013 RCIC INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E51-F019 RCIC MINIMUM FLOW BYPASS TO C SR 3.6.1.3.4 (a) NA SUPPRESSION POOL 2-E51-F031 RCIC SUPPRESSION POOL SUCTION C SR 3.6.1.3.4 80 5 SR 3.6.1.3.6 2-E51-F062 RCIC TURBINE EXHAUST VACUUM A, B SR 3.6.1.3.4 30 9 BREAKER SR 3.6.1.3.6 2-E51-F066 RCIC TURBINE EXHAUST VACUUM A, B SR 3.6.1.3.4 30 9 BREAKER SR 3.6.1.3.6 2-G16-F003 DRYWELL FLOOR DRAIN INBOARD A, B SR 3.6.1.3.4 20 2 ISOLATION SR 3.6.1.3.6 2-G16-F004 DRYWELL FLOOR DRAIN OUTBOARD A, B SR 3.6.1.3.4 20 2 ISOLATION SR 3.6.1.3.6 2-G16-F019 DRYWELL EQUIPMENT DRAIN INBOARD A, B SR 3.6.1.3.4 20 2 ISOLATION SR 3.6.1.3.6 2-G16-F020 DRYWELL EQUIPMENT DRAIN OUTBOARD A, B SR 3.6.1.3.4 20 2 ISOLATION SR 3.6.1.3.6 (e) 2-G31-F001 RWCU INLET INBOARD ISOLATION A, B SR 3.6.1.3.4 35 3 SR 3.6.1.3.6 2-G31-F004 RWCU INLET OUTBOARD ISOLATION A, B SR 3.6.1.3.4 35 3 SR 3.6.1.3.6 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 C SR 3.6.1.3.4 (a) NA SAMPLE (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."

Brunswick Unit 2 D-20 Revision No. 23

TRM PCIV List Appendix D TRM Table 3.6.1.3-2 (Page 9 of 9)

Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS SURVEILLANCE ALLOWABLE AUTOMATIC CONDITION(S) REQUIREMENTS ISOLATION ISOLATION TIME GROUP (in seconds) 2-RCC-SV-1222C RECIRC PUMP 2B COOLER OUTLET C SR 3.6.1.3.4 (a) NA SAMPLE 2-RCC-V28 RBCCW DRYWELL DISCHARGE HEADER C SR 3.6.1.3.4 (a) NA ISOLATION 2-RCC-V52 RBCCW DRYWELL SUPPLY HEADER C SR 3.6.1.3.4 (a) NA ISOLATION 2-RNA-SV-5251 BACKUP NITROGEN SUPPLY TO DRYWELL C SR 3.6.1.3.4 (a) NA ISOLATION VALVE - DIVISION II 2-RNA-SV-5253 BACKUP NITROGEN SUPPLY TO DRYWELL C SR 3.6.1.3.4 (a) NA ISOLATION VALVE - DIVISION I 2-RNA-SV-5261 NON-INTERRUPTIBLE REACTOR A, B SR 3.6.1.3.4 (a) 10 INSTRUMENT AIR SOLENOID SR 3.6.1.3.6 2-RNA-SV-5262 NON-INTERRUPTIBLE REACTOR A, B SR 3.6.1.3.4 (a) 10 INSTRUMENT AIR SOLENOID SR 3.6.1.3.6 2-RXS-SV-4186 LIQUID SAMPLE RETURN INBOARD A, B SR 3.6.1.3.4 15 6 ISOLATION SR 3.6.1.3.6 2-RXS-SV-4187 LIQUID SAMPLE RETURN OUTBOARD A, B SR 3.6.1.3.4 15 6 ISOLATION SR 3.6.1.3.6 2-RXS-SV-4188 GAS SAMPLE RETURN INBOARD A, B SR 3.6.1.3.4 15 6 ISOLATION SR 3.6.1.3.6 2-RXS-SV-4189 GAS SAMPLE RETURN OUTBOARD A, B SR 3.6.1.3.4 15 6 ISOLATION SR 3.6.1.3.6 (a) Allowable Isolation Time specified in the Inservice Testing Program.

Brunswick Unit 2 D-21 Revision No. 24

APPENDIX E SECONDARY CONTAINMENT ISOLATION DAMPER (SCID) LIST Brunswick Unit 2 Revision No. 23

TRM SCID List Appendix E 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.

Brunswick Unit 2 E-1 Revision No. 23

TRM SCID List Appendix E TRM Table 3.6.4.2-1 (Page 1 of 1)

Secondary Containment Automatic Isolation Dampers DAMPER NUMBER DAMPER DESCRIPTION SURVEILLANCE ALLOWABLE REQUIREMENTS ISOLATION TIME (in seconds) 2-VA-2A-BFIV-RB Reactor Building Ventilation Supply Inboard Isolation SR 3.6.4.2.1 4 SR 3.6.4.2.2 2-VA-2B-BFIV-RB Reactor Building Ventilation Supply Outboard Isolation SR 3.6.4.2.1 4 SR 3.6.4.2.2 2-VA-2C-BFIV-RB Reactor Building Ventilation Exhaust Inboard Isolation SR 3.6.4.2.1 4 SR 3.6.4.2.2 2-VA-2D-BFIV-RB Reactor Building Ventilation Exhaust Outboard Isolation SR 3.6.4.2.1 4 SR 3.6.4.2.2 2-VA-2A-BFV-RB Purge System Exhaust Outlet Valve SR 3.6.4.2.1 (a)

SR 3.6.4.2.2 2-VA-2I-BFV-RB Purge System Inlet Valve SR 3.6.4.2.1 (a)

SR 3.6.4.2.2 (a) Allowable Isolation Time specified in the Inservice Testing Program.

Brunswick Unit 2 E-2 Revision No. 23

APPENDIX F SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)

Brunswick Unit 2 Revision No. 23

TRM SFDP Appendix F SFDP Definitions 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),

Attachment 4 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 system to perform its required Safety Function.

Supported Feature A TS system/subsystem/component that performs a specific Safety Function.

Brunswick Unit 2 SFDP-1 Revision No. 23

TRM SFDP Appendix F Cascading Requirements 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.

Attachment 1 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)

Brunswick Unit 2 SFDP-2 Revision No. 23

TRM SFDP Appendix F Cascading Requirements 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)

Brunswick Unit 2 SFDP-3 Revision No. 23

TRM SFDP Appendix F Cascading Requirements 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.

Brunswick Unit 2 SFDP-4 Revision No. 23

TRM SFDP Appendix F Cascading Requirements Figure 2-1 (page 1 of 1)

Safety Function Determination Program Flowchart Brunswick Unit 2 SFDP-5 Revision No. 23

TRM SFDP Appendix F Maximum Completion Time 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.

Brunswick Unit 2 SFDP-6 Revision No. 23

TRM SFDP Appendix F SFD Review 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.

Brunswick Unit 2 SFDP-7 Revision No. 23

TRM SFDP Appendix F Attachment 1 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)

Support Feature/Supported Feature TS Cross Reference - Attachment 1 Support Support System Supported Supported System System TS System TS Number Number 3.3.5.1 ECCS Instrumentation 3.5.1 ECCS - Operating 3.5.2 ECCS - Shutdown 3.6.2.3 RHR Suppression Pool Cooling 3.8.1 AC Sources - Operating 3.8.2 AC Sources - Shutdown 3.3.5.2 RCIC Instrumentation 3.5.3 RCIC System 3.3.6.1 Primary Containment 3.1.7 SLC System Isolation Instrumentation 3.6.1.3 PCIVs 3.6.1.5 Reactor Building-to-Suppression Chamber Vacuum Breakers 3.3.6.2 Secondary Containment 3.6.4.2 SCIDs Isolation Instrumentation 3.6.4.3 SGT System 3.3.7.1 CREV System 3.7.3 CREV System Instrumentation 3.3.8.1 LOP Instrumentation 3.3.5.1 ECCS Instrumentation 3.7.2 SW System and UHS 3.8.1 AC Sources - Operating 3.8.2 AC Sources - Shutdown 3.6.1.5 Reactor Building-to- 3.6.1.1 Primary Containment Suppression Chamber Vacuum Breakers 3.6.1.6 Suppression Chamber-to- 3.6.1.1 Primary Containment Drywell Vacuum Breakers (continued)

Brunswick Unit 2 SFDP-8 Revision No. 23

TRM SFDP Appendix F Attachment 1 (continued)

Support Support System Supported Supported System System TS System TS Number Number 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 RHR SDC System - Hot Shutdown 3.6.2.3 RHR Suppression Pool Cooling 3.7.2 SW System and UHS 3.5.1 ECCS - Operating 3.4.7 RHR SDC System - Hot Shutdown 3.6.2.3 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)

Brunswick Unit 2 SFDP-9 Revision No. 23

TRM SFDP Appendix F Attachment 1 (continued)

Support Support System Supported Supported System System TS System TS Number Number 3.8.7 Distribution Systems - 3.1.7 SLC System Operating (AC portion (AC only) 3.3.3.1 PAM Instrumentation only) 3.3.3.2 Remote Shutdown Monitoring Attachment 2 provides a Instrumentation listing of equipment supported by AC 3.3.6.1 Primary Containment Isolation distribution. Instrumentation Attachment 3 provides a 3.4.5 RCS Leakage Detection listing of electrical power Instrumentation supplies supporting 3.4.7 RHR SDC System - Hot Shutdown PCIVs.

3.5.1 ECCS - Operating 3.5.3 RCIC System 3.6.1.3 PCIVs 3.6.2.3 RHR Suppression Pool Cooling 3.6.4.2 SCIDs 3.6.4.3 SGT System 3.7.1 RHRSW System 3.7.2 SW System and UHS 3.7.3 CREV System 3.7.4 Control Building AC System 3.8.1 AC Sources - Operating 3.8.3 Diesel Fuel Oil 3.8.4 DC Sources - Operating (continued)

Brunswick Unit 2 SFDP-10 Revision No. 23

TRM SFDP Appendix F Attachment 1 (continued)

Support Support System Supported Supported System System TS System TS Number Number 3.8.7 Distribution Systems - Operating 3.3.3.1 PAM Instrumentation (DC portion only)

(DC only) 3.3.3.2 Remote Shutdown System Attachment 3 provides a listing of 3.3.5.1 ECCS Instrumentation electrical power supplies supporting PCIVs. 3.3.5.2 RCIC System Instrumentation 3.3.6.1 Primary Containment Isolation Instrumentation 3.3.8.1 LOP Instrumentation 3.4.7 RHR SDC System - Hot Shutdown 3.5.1 ECCS - Operating 3.5.3 RCIC System 3.6.1.3 PCIVs 3.6.2.3 RHR Suppression Pool Cooling 3.7.1 RHRSW System 3.7.2 SW System and UHS 3.8.1 AC Sources - Operating (continued)

Brunswick Unit 2 SFDP-11 Revision No. 23

TRM SFDP Appendix F Attachment 1 (continued)

Support Support System Supported Supported System System TS System TS Number Number 3.8.8 Distribution Systems - Shutdown 3.3.6.1 Primary Containment (AC portion only) Isolation Instrumentation (AC only)

Attachment 2 provides a listing of 3.4.8 RHR SDC System - Cold equipment supported by AC Shutdown distribution.

3.5.2 ECCS - Shutdown Attachment 3 provides a listing of 3.6.1.3 PCIVs electrical power supplies supporting PCIVs. 3.6.4.2 SCIDs 3.6.4.3 SGT System 3.7.3 CREV System 3.7.4 Control Building AC System 3.8.2 AC Sources - Shutdown 3.8.3 Diesel Fuel Oil 3.8.5 DC Sources - Shutdown 3.9.7 RHR - High Water Level 3.9.8 RHR - Low Water Level (continued)

Brunswick Unit 2 SFDP-12 Revision No. 23

TRM SFDP Appendix F Attachment 1 (continued)

Support Support System Supported Supported System System TS System TS Number Number 3.8.8 Distribution Systems - Shutdown 3.3.5.1 ECCS Instrumentation (DC portion only)

(DC only) 3.3.6.1 Primary Containment Attachment 3 provides a listing of Isolation Instrumentation electrical power supplies 3.3.8.1 LOP Instrumentation supporting PCIVs.

3.4.8 RHR SDC System - Cold Shutdown 3.5.2 ECCS - Shutdown 3.6.1.3 PCIVs 3.8.2 AC Sources - Shutdown 3.9.7 RHR - High Water Level 3.9.8 RHR - Low Water Level Brunswick Unit 2 SFDP-13 Revision No. 23

TRM SFDP Appendix F Attachment 2 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) X1 X1 2B PAM INST. (FUNC. 1) X1 X1 2A PAM INST. (FUNC. 2) X 2B PAM INST. (FUNC. 2) X1 2A PAM INST. (FUNC. 3-7,9,10) X 2B PAM INST. (FUNC. 3-7,9,10) X 3

PAM PCIV POSITION (FUNC. 8) 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 X2 X 3.9.7, 3.9.8 2B RHR SDC X2 X 2C RHR SDC X X2 2D RHR SDC X1 X 3.5.1, 3.5.3 U2 HPCI X1 X1 1

U2 RCIC X 2A RECIRC. DISC. VALVE X 2B RECIRC. DISC. VALVE X 3.5.1, 3.5.2 2A LPCI SUBSYSTEM X X2 2A LPCI PUMP X 2C LPCI PUMP X 2B LPCI SUBSYSTEM X X2 2B LPCI PUMP X 2D LPCI PUMP X 2A CORE SPRAY SUBSYSTEM X 2B CORE SPRAY SUBSYSTEM X 3

3.6.1.3 U2 PCIVs (MOVs) 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)

Brunswick Unit 2 SFDP-14 Revision No. 23

TRM SFDP Appendix F Attachment 2 (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 DG 1 X 3.8.3 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 Brunswick Unit 2 SFDP-15 Revision No. 23

TRM SFDP Appendix F Attachment 3 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 E-5 E-6 E-7 E-8 DIV I DIV II OPERATED FW 2-B21-F032A X 2-B21-F032B X MAIN 2-B21-F016 X STEAM 2-B21-F019 X RESIDUAL 2-E11-F007A X HEAT 2-E11-F007B X REMOVAL 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)

Brunswick Unit 2 SFDP-16 Revision No. 23

TRM SFDP Appendix F Attachment 3 (continued)

SUPPORT SYSTEM ELECTRICAL POWER DISTRIBUTION SYSTEM LCO 3.8.7, 3.8.8 AC 480 VAC EMERGENCY BUSES 250 VDC SYSTEM PCIV - MOTOR E-5 E-6 E-7 E-8 DIV I DIV II OPERATED RESIDUAL 2-E11-F103A X HEAT 2-E11-F103B X REMOVAL RWCU 2-G31-F001 X 2-G31-F004 X 2-G31-F042 X REACTOR 2-B32-V22 X RECIRC. 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 2-E21-F001A X SPRAY 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)

Brunswick Unit 2 SFDP-17 Revision No. 23

TRM SFDP Appendix F Attachment 3 (continued)

SUPPORT SYSTEM ELECTRICAL POWER DISTRIBUTION SYSTEM LCO 3.8.7, 3.8.8 AC 480 VAC EMERGENCY BUSES 250 VDC SYSTEM PCIV - MOTOR E-5 E-6 E-7 E-8 DIV I DIV II OPERATED 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 Brunswick Unit 2 SFDP-18 Revision No. 23

TRM SFDP Appendix F Attachment 4 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)

Brunswick Unit 2 SFDP-19 Revision No. 23

TRM SFDP Appendix F Attachment 4 (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 SystemHot 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 SystemCold Shutdown Both required SDC subsystems inoperable, Recirc. pumps not in operation, and no alternate method of decay heat removal.

3.5.1 ECCSOperating

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)

Brunswick Unit 2 SFDP-20 Revision No. 23

TRM SFDP Appendix F Attachment 4 (continued) 3.5.2 ECCSShutdown 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)

Brunswick Unit 2 SFDP-21 Revision No. 23

TRM SFDP Appendix F Attachment 4 (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)

Brunswick Unit 2 SFDP-22 Revision No. 23

TRM SFDP Appendix F Attachment 4 (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 SourcesOperating

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 SourcesShutdown All offsite circuits and the DG associated with a 4.16 kV emergency bus required by LCO 3.8.8 are inoperable.

(continued)

Brunswick Unit 2 SFDP-23 Revision No. 23

TRM SFDP Appendix F Attachment 4 (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 SourcesOperating Two or more DC divisions (Unit 1 and 2) inoperable.

3.8.5 DC SourcesShutdown A DC subsystem (Unit 1 or 2) required to support the shutdown unit is inoperable.

(continued)

Brunswick Unit 2 SFDP-24 Revision No. 23

TRM SFDP Appendix F Attachment 4 (continued)

3.8.7 Distribution SystemsOperating

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)

Brunswick Unit 2 SFDP-25 Revision No. 23

TRM SFDP Appendix F Attachment 4 (continued)

3.8.8 Distribution SystemsShutdown

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.

Brunswick Unit 2 SFDP-26 Revision No. 23

TRM SFDP Appendix F Bases 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 subsystems 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)

Brunswick Unit 2 B SFDP-1 Revision No. 23

TRM SFDP Appendix F Bases 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)

Brunswick Unit 2 B SFDP-2 Revision No. 23

TRM SFDP Appendix F Bases 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)

Brunswick Unit 2 B SFDP-3 Revision No. 23

TRM SFDP Appendix F Bases 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)

Brunswick Unit 2 B SFDP-4 Revision No. 23

TRM SFDP Appendix F Bases 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 Supported Feature's TS LCO. This "Maximum Completion Time" philosophy is similar to that of TS Section 1.3, Completion Times.

(continued)

Brunswick Unit 2 B SFDP-5 Revision No. 23

TRM SFDP Appendix F Bases Program Use and Application MAXIMUM COMPLETION EXAMPLE 3.1-1 TIME (continued)

Day 1 Day 3 System A Day 3 Day 10 System C Day 3 Day 10 System B 3 days 7 days 3 days + 7 days = 10 days Maximum Completion Time 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)

Brunswick Unit 2 B SFDP-6 Revision No. 23

TRM SFDP Appendix F Bases 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), then 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.

Brunswick Unit 2 B SFDP-7 Revision No. 23

TRM SFDP Appendix F Bases 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)

Brunswick Unit 2 B SFDP-8 Revision No. 23

TRM SFDP Appendix F Bases 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)

Brunswick Unit 2 B SFDP-9 Revision No. 23

TRM SFDP Appendix F Bases 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)

Brunswick Unit 2 B SFDP-10 Revision No. 23

TRM SFDP Appendix F Bases 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)

Brunswick Unit 2 B SFDP-11 Revision No. 23

TRM SFDP Appendix F Bases 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)

Brunswick Unit 2 B SFDP-12 Revision No. 23

TRM SFDP Appendix F Bases 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).

Brunswick Unit 2 B SFDP-13 Revision No. 23

TRM SFDP Appendix F Bases 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 Attachment 1 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 Attachment 2. 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)

Brunswick Unit 2 B SFDP-14 Revision No. 23

TRM SFDP Appendix F Bases 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.

Brunswick Unit 2 B SFDP-15 Revision No. 23

RA-18-0131, Technical Requirements Manual, Revision 66

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