RA-18-0131, Technical Requirements Manual, Revision 66: Difference between revisions
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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 | 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) | |||
LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENTS MANUAL Brunswick Unit 2 LOEP-3 Revision No. 66 | LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENTS MANUAL Brunswick Unit 2 LOEP-3 Revision No. 66 | ||
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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 | B 3.13-1 23 APPENDIX A 23 A-1 23 B 3.14-1 65 A-2 23 B 3.14-2 65 A-3 23 B 3.14-3 65 A-4 23 B 3.14-4 65 A-5 23 B 3.14-5 65 A-6 23 B 3.14-6 65 A-7 23 B 3.14-7 65 A-8 23 A-9 27 B 3.15-1 23 A-10 23 A-11 23 B 3.16-1 58 A-12 23 B 3.16-2 58 A-13 23 B 3.16-3 58 A-14 23 A-15 23 B 3.17-1 23 A-16 25 A-17 25 A-18 25 A-19 23 | ||
(continued) | |||
LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENTS MANUAL Brunswick Unit 2 LOEP-4 Revision No. 65 | LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENTS MANUAL Brunswick Unit 2 LOEP-4 Revision No. 65 | ||
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APPENDIX B 23 APPENDIX D 23 B-1 23 D-1 23 B-2 44 D-2 26 B-3 23 D-3 23 B-4 44 D-4 30 B-5 23 D-5 26 B-6 23 D-6 26 B-7 39 D-7 26 B-8 23 D-8 23 B-9 23 D-9 42 B-10 23 D-10 26 B-11 23 D-11 26 B-12 24 D-12 26 B-13 23 D-13 23 B-14 23 D-14 49 B-15 23 D-15 49 B-16 23 D-16 23 B-17 23 D-17 59 B-18 28 D-18 23 B-19 23 D-19 23 B-20 23 D-20 23 B-21 23 D-21 24 B-22 48 B-23 23 APPENDIX E 23 B-24 34 E-1 23 B-25 23 E-2 23 B-26 63 B-27 64 APPENDIX F 23 B-28 23 SFDP-1 23 B-29 23 SFDP-2 23 SFDP-3 23 APPENDIX C 23 SFDP-4 23 C-1 23 SFDP-5 23 C-2 44 SFDP-6 23 C-3 61 SFDP-7 23 C-4 28 SFDP-8 23 C-5 23 SFDP-9 23 C-6 23 SFDP-10 23 C-7 23 SFDP-11 23 C-8 47 SFDP-12 23 C-9 52 SFDP-13 23 C-10 51 SFDP-14 23 C-11 57 SFDP-15 23 | APPENDIX B 23 APPENDIX D 23 B-1 23 D-1 23 B-2 44 D-2 26 B-3 23 D-3 23 B-4 44 D-4 30 B-5 23 D-5 26 B-6 23 D-6 26 B-7 39 D-7 26 B-8 23 D-8 23 B-9 23 D-9 42 B-10 23 D-10 26 B-11 23 D-11 26 B-12 24 D-12 26 B-13 23 D-13 23 B-14 23 D-14 49 B-15 23 D-15 49 B-16 23 D-16 23 B-17 23 D-17 59 B-18 28 D-18 23 B-19 23 D-19 23 B-20 23 D-20 23 B-21 23 D-21 24 B-22 48 B-23 23 APPENDIX E 23 B-24 34 E-1 23 B-25 23 E-2 23 B-26 63 B-27 64 APPENDIX F 23 B-28 23 SFDP-1 23 B-29 23 SFDP-2 23 SFDP-3 23 APPENDIX C 23 SFDP-4 23 C-1 23 SFDP-5 23 C-2 44 SFDP-6 23 C-3 61 SFDP-7 23 C-4 28 SFDP-8 23 C-5 23 SFDP-9 23 C-6 23 SFDP-10 23 C-7 23 SFDP-11 23 C-8 47 SFDP-12 23 C-9 52 SFDP-13 23 C-10 51 SFDP-14 23 C-11 57 SFDP-15 23 | ||
(continued) | |||
LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENTS MANUAL Brunswick Unit 2 LOEP-5 Revision 65 | LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENTS MANUAL Brunswick Unit 2 LOEP-5 Revision 65 | ||
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DEPRESSURIZATION SYSTEM (ADS) INHIBIT SWITCH ...... 3.7-1 3.8 SUPPRESSION CHAMBER WATER TEMPERATURE INSTRUMENTATION ................................................................................ 3.8-1 3.9 SEISMIC MONITORING INSTRUMENTATION ............................................. 3.9-1 3.10 INTAKE CANAL HIGH WATER LEVEL INSTRUMENTATION .................... 3.10-1 3.11 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION .................. 3.11-1 3.12 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM INSTRUMENTATION .............................................................................. 3.12-1 3.13 REACTOR COOLANT SYSTEM (RCS) CHEMISTRY ................................. 3.13-1 3.14 STRUCTURAL INTEGRITY ......................................................................... 3.14-1 3.15 NOT USED ................................................................................................... 3.15-1 3.16 SERVICE WATER SYSTEM OPERABILITY-SHUTDOWN ....................... 3.16-1 3.17 SERVICE WATER SYSTEM-SHUTDOWN OPERATIONS ....................... 3.17-1 | DEPRESSURIZATION SYSTEM (ADS) INHIBIT SWITCH ...... 3.7-1 3.8 SUPPRESSION CHAMBER WATER TEMPERATURE INSTRUMENTATION ................................................................................ 3.8-1 3.9 SEISMIC MONITORING INSTRUMENTATION ............................................. 3.9-1 3.10 INTAKE CANAL HIGH WATER LEVEL INSTRUMENTATION .................... 3.10-1 3.11 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION .................. 3.11-1 3.12 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM INSTRUMENTATION .............................................................................. 3.12-1 3.13 REACTOR COOLANT SYSTEM (RCS) CHEMISTRY ................................. 3.13-1 3.14 STRUCTURAL INTEGRITY ......................................................................... 3.14-1 3.15 NOT USED ................................................................................................... 3.15-1 3.16 SERVICE WATER SYSTEM OPERABILITY-SHUTDOWN ....................... 3.16-1 3.17 SERVICE WATER SYSTEM-SHUTDOWN OPERATIONS ....................... 3.17-1 | ||
(continued) | |||
TABLE OF CONTENTS (continued) | TABLE OF CONTENTS (continued) | ||
Brunswick Unit 2 0.0-5 Revision No. 23 3.18 CONTROL ROOM EMERGENCY VENTILATION (CREV) | Brunswick Unit 2 0.0-5 Revision No. 23 3.18 CONTROL ROOM EMERGENCY VENTILATION (CREV) | ||
Line 241: | Line 241: | ||
may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel | may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel | ||
is tested. | is tested. | ||
(continued) | |||
Definitions | Definitions | ||
Line 255: | Line 255: | ||
The following exceptions are not considered CORE | The following exceptions are not considered CORE | ||
ALTERATIONS: | ALTERATIONS: | ||
: a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore | : a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore | ||
Line 289: | Line 289: | ||
perform its specified safety function(s) are also capable of | perform its specified safety function(s) are also capable of | ||
performing their related support function(s). | performing their related support function(s). | ||
(continued) | |||
Definitions | Definitions | ||
Line 348: | Line 348: | ||
Frequency. | Frequency. | ||
EXAMPLES The following examples illustrate the use of logical connectors. | EXAMPLES The following examples illustrate the use of logical connectors. | ||
(continued) | |||
Logical Connectors | Logical Connectors | ||
Line 361: | Line 361: | ||
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 | 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. | be completed. | ||
(continued) | |||
Logical Connectors | Logical Connectors | ||
Line 441: | Line 441: | ||
inoperable or not within limits, will not result in separate entry into the Condition unless specifically stated. The Required Compensatory | 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. | Measures of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition. | ||
(continued) | |||
Completion Times | Completion Times | ||
Line 453: | Line 453: | ||
Completion Time extension, two criteria must first be met. The | Completion Time extension, two criteria must first be met. The | ||
subsequent inoperability: | 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. | : 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 | The total Completion Time allowed for completing a Required | ||
Line 459: | Line 459: | ||
Compensatory Measure to address the subsequent inoperability shall be | Compensatory Measure to address the subsequent inoperability shall be | ||
limited to the more restrictive of either: | 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 hours; or b. The stated Completion Time as measured from discovery of the subsequent inoperability. | : a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours; 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 | The above Completion Time extension does not apply to those TRMS | ||
Line 487: | Line 487: | ||
Completion Time specified for Condition A and B in Example 1.3-3 may | Completion Time specified for Condition A and B in Example 1.3-3 may | ||
not be extended. | not be extended. | ||
(continued) | |||
Completion Times | Completion Times | ||
Line 529: | Line 529: | ||
If Condition B is entered while in MODE 3, the time allowed for reaching | If Condition B is entered while in MODE 3, the time allowed for reaching | ||
MODE 4 is the next 36 hours. | MODE 4 is the next 36 hours. | ||
(continued) | |||
Completion Times | Completion Times | ||
Line 563: | Line 563: | ||
exited, and therefore, the Required Compensatory Measures of | exited, and therefore, the Required Compensatory Measures of | ||
Condition B may be terminated. | Condition B may be terminated. | ||
(continued) | |||
Completion Times | Completion Times | ||
Line 667: | Line 667: | ||
commencing at the time the TRMS was initially not met, instead of at the | commencing at the time the TRMS was initially not met, instead of at the | ||
time the associated Condition was entered. | time the associated Condition was entered. | ||
(continued) | |||
Completion Times | Completion Times | ||
Line 718: | Line 718: | ||
If the Completion Time of 4 hours (plus the extension) expires while one | If the Completion Time of 4 hours (plus the extension) expires while one | ||
or more valves are still inoperable, Condition B is entered. | or more valves are still inoperable, Condition B is entered. | ||
(continued) | |||
Completion Times | Completion Times | ||
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entered for each valve and separate Completion Times start and are | entered for each valve and separate Completion Times start and are | ||
tracked for each valve. | tracked for each valve. | ||
(continued) | |||
Completion Times | Completion Times | ||
Line 836: | Line 836: | ||
or A.2 is met, Condition B is exited and operation may then continue in | or A.2 is met, Condition B is exited and operation may then continue in | ||
Condition A. | Condition A. | ||
(continued) | |||
Completion Times | Completion Times | ||
Line 956: | Line 956: | ||
Unit 2 1.4-2 Revision No. 23 TRMS 1.4 Frequency | Unit 2 1.4-2 Revision No. 23 TRMS 1.4 Frequency | ||
DESCRIPTION ability to meet the acceptance criteria. TR 3.0.4 restrictions would not (continued) apply if both the following conditions are satisfied: a. The Test is not required to be performed; and | 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. | : 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 | EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the TRMS (TRMS not | ||
Line 988: | Line 988: | ||
Test is not otherwise modified (refer to Examples 1.4-3 and 1.4-4), then | Test is not otherwise modified (refer to Examples 1.4-3 and 1.4-4), then | ||
TR 3.0.3 becomes applicable. | TR 3.0.3 becomes applicable. | ||
(continued) | |||
Frequency | Frequency | ||
Line 1,021: | Line 1,021: | ||
"). This type of Frequency does not qualify for the extension allowed by | "). This type of Frequency does not qualify for the extension allowed by | ||
TR 3.0.2. | TR 3.0.2. | ||
(continued) | |||
Frequency | Frequency | ||
Line 1,060: | Line 1,060: | ||
TR 3.0.4 occurs when changing MODES, even with the 7 day Frequency | TR 3.0.4 occurs when changing MODES, even with the 7 day Frequency | ||
not met, provided operation does not exceed 12 hours with power 25% RTP. | not met, provided operation does not exceed 12 hours with power 25% RTP. | ||
(continued) | |||
Frequency | Frequency | ||
Line 1,207: | Line 1,207: | ||
met, the TRMS must immediately be declared not met, and the applicable | met, the TRMS must immediately be declared not met, and the applicable | ||
Condition(s) must be entered. | Condition(s) must be entered. | ||
(continued) | |||
TR Applicability | TR Applicability | ||
Line 1,294: | Line 1,294: | ||
===3.3 Brunswick=== | ===3.3 Brunswick=== | ||
Unit 2 3.3-2 Revision No. 23 TEST REQUIREMENTS | Unit 2 3.3-2 Revision No. 23 TEST REQUIREMENTS | ||
---------------------------------------------------------- NOTES ---------------------------------------------------------- | ---------------------------------------------------------- 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 | : 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 | ||
Line 1,346: | Line 1,346: | ||
TEST REQUIREMENTS | TEST REQUIREMENTS | ||
ALLOWABLE VALUE | ALLOWABLE VALUE | ||
: 1. Average Power Range Monitors | : 1. Average Power Range Monitors | ||
: a. Upscale (Flow Biased) | : a. Upscale (Flow Biased) | ||
: b. Inoperative | : b. Inoperative | ||
: c. Downscale | : c. Downscale | ||
: d. Upscale (Fixed) | : d. Upscale (Fixed) | ||
Line 1,365: | Line 1,365: | ||
TR 3.3.3 TR 3.3.5 | TR 3.3.3 TR 3.3.5 | ||
0.55W + 55.0%RTP (a) and 109.3% RTP NA 1.1% APRM power 14% RTP | 0.55W + 55.0%RTP (a) and 109.3% RTP NA 1.1% APRM power 14% RTP | ||
: 2. Source Range Monitors | : 2. Source Range Monitors | ||
: a. Detector Not Full In | : a. Detector Not Full In | ||
: b. Upscale | : b. Upscale | ||
: c. Inoperative | : c. Inoperative | ||
: d. Downscale | : d. Downscale | ||
Line 1,380: | Line 1,380: | ||
TR 3.3.1 TR 3.3.1 | TR 3.3.1 TR 3.3.1 | ||
NA 5 x 10 5 cps NA 3 cps | NA 5 x 10 5 cps NA 3 cps | ||
: 3. Intermediate Range Monitors | : 3. Intermediate Range Monitors | ||
: a. Detector Not Full In | : a. Detector Not Full In | ||
: b. Upscale | : b. Upscale | ||
: c. Inoperable | : c. Inoperable | ||
: d. Downscale | : d. Downscale | ||
Line 1,405: | Line 1,405: | ||
1,2,5(f) 1 (g) TR 3.3.2 TR 3.3.3 73 gallons | 1,2,5(f) 1 (g) TR 3.3.2 TR 3.3.3 73 gallons | ||
(a) [0.55(W - W) + 55.0% RTP] when Technical Specification 3.3.1.1, Function 2.b, is reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating." The value of W is defined in plant procedures. (b) Bypassed when detector is reading > 100 cps or Intermediate Range Monitor (IRM) channels are on Range 3 or higher. | (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. | (c) Bypassed when associated IRM channels are on Range 8 or higher. | ||
(d) Deleted. | (d) Deleted. | ||
(e) Bypassed when IRM channels are on Range 1. | (e) Bypassed when IRM channels are on Range 1. | ||
(f) With any control rod withdrawn from a core cell containing one or more fuel assemblies. Not applicable to control rods removed per Technical Specification 3.10.5, "Single Control Rod Drive (CRD) Removal-Refueling," or 3.10.6, "Multiple Control Rod Withdrawal-Refueling." (g) Signal is contained in Channel A logic only. | (f) With any control rod withdrawn from a core cell containing one or more fuel assemblies. Not applicable to control rods removed per Technical Specification 3.10.5, "Single Control Rod Drive (CRD) Removal-Refueling," or 3.10.6, "Multiple Control Rod Withdrawal-Refueling." (g) Signal is contained in Channel A logic only. | ||
Line 1,417: | Line 1,417: | ||
COMPENSATORY MEASURES | COMPENSATORY MEASURES | ||
---------------------------------------------------------- NOTES ---------------------------------------------------------- | ---------------------------------------------------------- NOTES ---------------------------------------------------------- | ||
: 1. TRMS 3.0.4 is not applicable. | : 1. TRMS 3.0.4 is not applicable. | ||
: 2. Separate Condition entry is allowed for each Function. | : 2. Separate Condition entry is allowed for each Function. | ||
------------------------------------------------------------------------------------------------------------------------------- CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. --------------NOTE--------------- | ------------------------------------------------------------------------------------------------------------------------------- CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. --------------NOTE--------------- | ||
Line 1,465: | Line 1,465: | ||
===3.4 Brunswick=== | ===3.4 Brunswick=== | ||
Unit 2 3.4-3 Revision No. 60 Table 3.4-1 (page 1 of 1) | Unit 2 3.4-3 Revision No. 60 Table 3.4-1 (page 1 of 1) | ||
Accident Monitoring Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS 1. Suppression Chamber Atmosphere Temperature 2. Drywell Radiation | Accident Monitoring Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS 1. Suppression Chamber Atmosphere Temperature 2. Drywell Radiation | ||
: 3. Safety/Relief Valve Position Indication | : 3. Safety/Relief Valve Position Indication | ||
: a. Primary-Sonic | : a. Primary-Sonic | ||
: b. Secondary-Temperature 4. Turbine Building Ventilation Monitor 5. Offgas Stack Ventilation Monitor | : b. Secondary-Temperature 4. Turbine Building Ventilation Monitor 5. Offgas Stack Ventilation Monitor | ||
: 6. Drywell and Suppression Chamber H 2 Analyzer 7. Drywell and Suppression Chamber O 2 Analyzer 1,2 1,2,3 1,2 | : 6. Drywell and Suppression Chamber H 2 Analyzer 7. Drywell and Suppression Chamber O 2 Analyzer 1,2 1,2,3 1,2 | ||
Line 1,519: | Line 1,519: | ||
Discharge (Wide Range or | Discharge (Wide Range or | ||
Narrow Range) | Narrow Range) | ||
: a. Wide Range | : a. Wide Range | ||
: b. Narrow Range 3. Chloride Leak Detector in the Inlet to the Condensate | : b. Narrow Range 3. Chloride Leak Detector in the Inlet to the Condensate | ||
Line 1,733: | Line 1,733: | ||
===3.9 Brunswick=== | ===3.9 Brunswick=== | ||
Unit 2 3.9-3 Revision No. 47 Table 3.9-1 (page 1 of 1) | Unit 2 3.9-3 Revision No. 47 Table 3.9-1 (page 1 of 1) | ||
Seismic Monitoring Instrumentation INSTRUMENTS AND SENSOR LOCATIONS MEASUREMENT RANGE REQUIRED INSTRUMENTS TEST REQUIREMENTS 1. Passive Triaxial Peak Shock Recorders | Seismic Monitoring Instrumentation INSTRUMENTS AND SENSOR LOCATIONS MEASUREMENT RANGE REQUIRED INSTRUMENTS TEST REQUIREMENTS 1. Passive Triaxial Peak Shock Recorders | ||
: a. Reactor Building Basement/Equipment | : a. Reactor Building Basement/Equipment | ||
Line 1,740: | Line 1,740: | ||
(+20' level) c. Reactor Building Refueling Area (+117' | (+20' level) c. Reactor Building Refueling Area (+117' | ||
level) 2-25 Hz 2-25 Hz 2-25 Hz 1 1 1 TR 3.9.3 TR 3.9.3 TR 3.9.3 2. Active Triaxial Accelerometers | level) 2-25 Hz 2-25 Hz 2-25 Hz 1 1 1 TR 3.9.3 TR 3.9.3 TR 3.9.3 2. Active Triaxial Accelerometers | ||
: a. Reactor Building | : a. Reactor Building | ||
(+89'4" level) | (+89'4" level) | ||
: b. Reactor Building | : b. Reactor Building | ||
(-17' level) | (-17' level) | ||
: 3. Active Seismic Recording System | : 3. Active Seismic Recording System | ||
: a. Control Room 0-1.0g 0-1.0g | : a. Control Room 0-1.0g 0-1.0g | ||
Line 1,852: | Line 1,852: | ||
Primary Containment Isolation Instrumentation FUNCTION REQUIRED CHANNELS PER TRIP SYSTEM ALLOWABLE VALUE 1. Main Steam Line Tunnel Temperature-High (except for Main Steam Isolation | Primary Containment Isolation Instrumentation FUNCTION REQUIRED CHANNELS PER TRIP SYSTEM ALLOWABLE VALUE 1. Main Steam Line Tunnel Temperature-High (except for Main Steam Isolation | ||
Valve Pit instruments) 2. Turbine Building Area Temperature-High 2 (a) 4 (b) 197°F 197°F (a) A channel is OPERABLE if 2 of 3 instruments in the channel are OPERABLE. | Valve Pit instruments) 2. Turbine Building Area Temperature-High 2 (a) 4 (b) 197°F 197°F (a) A channel is OPERABLE if 2 of 3 instruments in the channel are OPERABLE. | ||
(b) A channel is OPERABLE if 2 of 4 instruments in the channel are OPERABLE. | (b) A channel is OPERABLE if 2 of 4 instruments in the channel are OPERABLE. | ||
Line 1,917: | Line 1,917: | ||
APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED DETECTORS PER TRIP SYSTEM TEST REQUIREMENTS | APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED DETECTORS PER TRIP SYSTEM TEST REQUIREMENTS | ||
ALLOWABLE VALUE | ALLOWABLE VALUE | ||
: 1. Chlorine Isolation | : 1. Chlorine Isolation | ||
: a. Control Building Air Intake (Local) | : a. Control Building Air Intake (Local) | ||
: b. Chlorine Tank Car Area (Remote) | : b. Chlorine Tank Car Area (Remote) | ||
(a) | |||
(a) | |||
4(b) 4(b) | 4(b) 4(b) | ||
Line 1,933: | Line 1,933: | ||
TR 3.12.3 | TR 3.12.3 | ||
5 ppm 5 ppm | 5 ppm 5 ppm | ||
: 2. Control Room Envelope Smoke Protection | : 2. Control Room Envelope Smoke Protection | ||
: a. Control Building Intake Air Duct Smoke Detectors | : a. Control Building Intake Air Duct Smoke Detectors | ||
Line 2,035: | Line 2,035: | ||
RCS Chemistry Limits CHEMISTRY PARAMETER | RCS Chemistry Limits CHEMISTRY PARAMETER | ||
APPLICABLE MODES OR OTHER SPECIFIED CONDITION LIMIT | APPLICABLE MODES OR OTHER SPECIFIED CONDITION LIMIT | ||
: 1. Chlorides 1 2,3,4,5 < 0.5 ppm | : 1. Chlorides 1 2,3,4,5 < 0.5 ppm | ||
< 0.2 ppm | < 0.2 ppm | ||
: 2. Conductivity 1,2 3,4,5 < 2.0 mhos/cm @ 25 | : 2. Conductivity 1,2 3,4,5 < 2.0 mhos/cm @ 25 | ||
°C < 10.0 mhos/cm @ 25 | °C < 10.0 mhos/cm @ 25 | ||
Line 2,160: | Line 2,160: | ||
Program Brunswick Unit 2 3.15-1 Revision No. 23 3.15 Not used. | Program Brunswick Unit 2 3.15-1 Revision No. 23 3.15 Not used. | ||
Service Water System OPERABILITY-Shutdown 3.16 Brunswick Unit 2 3.16-1 Revision No. 58 3.16 SERVICE WATER SYSTEM OPERABILITY-SHUTDOWN TRMS 3.16 The Service Water System shall be OPERABLE with: a. Three OPERABLE site Nuclear Service Water (NSW) pumps and | Service Water System OPERABILITY-Shutdown 3.16 Brunswick Unit 2 3.16-1 Revision No. 58 3.16 SERVICE WATER SYSTEM OPERABILITY-SHUTDOWN TRMS 3.16 The Service Water System shall be OPERABLE with: a. Three OPERABLE site Nuclear Service Water (NSW) pumps and | ||
: b. Two OPERABLE Service Water (SW) pumps (any combination of NSW or Conventional Service Water (CSW) pumps) powered from | : b. Two OPERABLE Service Water (SW) pumps (any combination of NSW or Conventional Service Water (CSW) pumps) powered from | ||
Line 2,261: | Line 2,261: | ||
24 months Service Water System-Shutdown Operations 3.17 Brunswick Unit 2 3.17-1 Revision No. 23 TEST REQUIREMENTS (continued) 3.17 SERVICE WATER SYSTEM-SHUTDOWN OPERATIONS TRMS 3.17 The conventional service water header may be removed from operation by stopping the service water pumps to permit isolating and draining the | 24 months Service Water System-Shutdown Operations 3.17 Brunswick Unit 2 3.17-1 Revision No. 23 TEST REQUIREMENTS (continued) 3.17 SERVICE WATER SYSTEM-SHUTDOWN OPERATIONS TRMS 3.17 The conventional service water header may be removed from operation by stopping the service water pumps to permit isolating and draining the | ||
nuclear service water header for maintenance provided: | 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 | : 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 | 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 | response to: 1. Any event which requires ECCS actuation, or | ||
: 2. RCS coolant temperature > 180 | : 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. | °F, or 3. A loss of offsite power. APPLICABILITY: MODES 4 and 5 with the nuclear service water header inoperable. | ||
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12 months Sealed Source Contamination 3.22 Brunswick Unit 2 3.22-2 Revision No. 23 TEST REQUIREMENTS | 12 months Sealed Source Contamination 3.22 Brunswick Unit 2 3.22-2 Revision No. 23 TEST REQUIREMENTS | ||
---------------------------------------------------------- NOTES ---------------------------------------------------------- | ---------------------------------------------------------- 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. | : 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. | ||
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Crane and Hoist OPERABILITY 3.25 Brunswick Unit 2 3.25-2 Revision No. 23 TEST REQUIREMENTS TEST FREQUENCY TR 3.25.1 Demonstrate operation of the overload cutoff of each crane or hoist to be used for movement of fuel | Crane and Hoist OPERABILITY 3.25 Brunswick Unit 2 3.25-2 Revision No. 23 TEST REQUIREMENTS TEST FREQUENCY TR 3.25.1 Demonstrate operation of the overload cutoff of each crane or hoist to be used for movement of fuel | ||
assemblies or control rods within the RPV: | assemblies or control rods within the RPV: | ||
: a. When the load is 1600 lbs for the mast fuel gripper; and b. When the load is 1050 lbs for all other cranes and hoists. | : a. When the load is 1600 lbs for the mast fuel gripper; and b. When the load is 1050 lbs for all other cranes and hoists. | ||
Once within | Once within | ||
Line 2,643: | Line 2,643: | ||
days. TR 3.25.2 Demonstrate operation of the loaded interlock of each crane or hoist to be used for movement of fuel | days. TR 3.25.2 Demonstrate operation of the loaded interlock of each crane or hoist to be used for movement of fuel | ||
assemblies or control rods within the RPV: | assemblies or control rods within the RPV: | ||
: a. When the load is 750 lbs for the mast fuel gripper; and b. When the load is 350 lbs for all other cranes and hoists. | : a. When the load is 750 lbs for the mast fuel gripper; and b. When the load is 350 lbs for all other cranes and hoists. | ||
Once within | Once within | ||
Line 2,790: | Line 2,790: | ||
5.5.3 Deleted. | 5.5.3 Deleted. | ||
(continued) | |||
Programs and Manuals | Programs and Manuals | ||
Line 2,846: | Line 2,846: | ||
====5.5.7 Ventilation==== | ====5.5.7 Ventilation==== | ||
Filter Testing Program (VFTP) | Filter Testing Program (VFTP) | ||
(continued) | |||
The program is implemented by the following procedures: | The program is implemented by the following procedures: | ||
Line 2,873: | Line 2,873: | ||
0E&RC-1010, 0E&RC-1142, 0E&RC-1141, 0E&RC-1138, and | 0E&RC-1010, 0E&RC-1142, 0E&RC-1141, 0E&RC-1138, and | ||
0E&RC-1020. | 0E&RC-1020. | ||
(continued) | |||
Programs and Manuals | Programs and Manuals | ||
Line 2,905: | Line 2,905: | ||
0PT-20.3, 0PT-20.3b, 0PT-20.3c, 0PT-20.5, 0PT-20.5.1, 0ENP-16.4, and | 0PT-20.3, 0PT-20.3b, 0PT-20.3c, 0PT-20.5, 0PT-20.5.1, 0ENP-16.4, and | ||
0ENP-16.8. | 0ENP-16.8. | ||
(continued) | |||
Programs and Manuals | Programs and Manuals | ||
Line 2,948: | Line 2,948: | ||
time has been granted (i.e., Technical Specification 3.8.1, Condition B). The | time has been granted (i.e., Technical Specification 3.8.1, Condition B). The | ||
program shall include the following elements: | 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 | : 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. | 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) | (0AP-025) c. Provisions for performing an assessment after entering the LCO Action for unplanned entry into the LCO Action. (0AP-025) | ||
(continued) | |||
Programs and Manuals | Programs and Manuals | ||
Line 2,999: | Line 2,999: | ||
that must be taken within specified Completion Times when the | that must be taken within specified Completion Times when the | ||
requirements of a TRMS are not met. This TRMS establishes that: | 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; | : a. Completion of the Required Compensatory Measures within the specified Completion Times constitutes compliance with a TRMS; | ||
Line 3,103: | Line 3,103: | ||
in that Applicability (e.g., Applicability desired to be entered) when the | in that Applicability (e.g., Applicability desired to be entered) when the | ||
following exist: | 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 | : 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 | ||
Line 3,137: | Line 3,137: | ||
TRMS 3.0.4 shall not prevent changes in MODES or other specified | TRMS 3.0.4 shall not prevent changes in MODES or other specified | ||
conditions in the Applicability that result from any unit shutdown. | conditions in the Applicability that result from any unit shutdown. | ||
(continued) | |||
TRMS Applicability B 3.0 Brunswick Unit 2 B 3.0-4 Revision No. 23 BASES TRMS 3.0.4 Exceptions to TRMS 3.0.4 are stated in the individual Tests. | TRMS Applicability B 3.0 Brunswick Unit 2 B 3.0-4 Revision No. 23 BASES TRMS 3.0.4 Exceptions to TRMS 3.0.4 are stated in the individual Tests. | ||
(continued) Exceptions may apply to all the COMPENSATORY MEASURES or to a specific Required Compensatory Measure of a TRMS. | |||
Tests do not have to be performed on the associated inoperable | Tests do not have to be performed on the associated inoperable | ||
Line 3,167: | Line 3,167: | ||
to not comply with the applicable Required Compensatory Measure(s)) to | to not comply with the applicable Required Compensatory Measure(s)) to | ||
allow the performance of TRs to demonstrate: | allow the performance of TRs to demonstrate: | ||
: a. The OPERABILITY of the equipment being returned to service; or | : a. The OPERABILITY of the equipment being returned to service; or | ||
: b. The OPERABILITY of other equipment. | : b. The OPERABILITY of other equipment. | ||
Line 3,225: | Line 3,225: | ||
construed as implying that systems or components are OPERABLE | construed as implying that systems or components are OPERABLE | ||
when: | 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. | : 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 | Tests do not have to be performed when the unit is in a MODE or other | ||
Line 3,241: | Line 3,241: | ||
Tests have to be met and performed in accordance with TR 3.0.2, prior to | Tests have to be met and performed in accordance with TR 3.0.2, prior to | ||
returning equipment to OPERABLE status. | returning equipment to OPERABLE status. | ||
(continued) | |||
TR Applicability B 3.0 Brunswick Unit 2 B 3.0-7 Revision No. 23 BASES TR 3.0.1 Upon completion of maintenance, appropriate post maintenance testing is (continued) required to declare equipment OPERABLE. This includes ensuring applicable Tests are not failed and their most recent performance is in | TR Applicability B 3.0 Brunswick Unit 2 B 3.0-7 Revision No. 23 BASES TR 3.0.1 Upon completion of maintenance, appropriate post maintenance testing is (continued) required to declare equipment OPERABLE. This includes ensuring applicable Tests are not failed and their most recent performance is in | ||
Line 3,352: | Line 3,352: | ||
applicable as a consequence of MODE changes imposed by Required | applicable as a consequence of MODE changes imposed by Required | ||
Compensatory Measures. | Compensatory Measures. | ||
(continued) | |||
TR Applicability B 3.0 Brunswick Unit 2 B 3.0-9 Revision No. 23 BASES TR 3.0.3 Failure to comply with specified Frequencies for TRs is expected to be an (continued) infrequent occurrence. Use of the delay period established by TR 3.0.3 is a flexibility which is not intended to be used as an operational | TR Applicability B 3.0 Brunswick Unit 2 B 3.0-9 Revision No. 23 BASES TR 3.0.3 Failure to comply with specified Frequencies for TRs is expected to be an (continued) infrequent occurrence. Use of the delay period established by TR 3.0.3 is a flexibility which is not intended to be used as an operational | ||
Line 3,504: | Line 3,504: | ||
One channel of Turbine Building or Stack Ventilation Monitoring consists of all three ranges (low, mid, and high) of the monitoring system. | One channel of Turbine Building or Stack Ventilation Monitoring consists of all three ranges (low, mid, and high) of the monitoring system. | ||
REFERENCES | REFERENCES | ||
: 1. Letter from Cornelius J. Gannon to the U. S. Nuclear Regulatory Commission (Serial: | : 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 | BSEP 04-0098), "Request for License Amendments - Deletion of Hydrogen and Oxygen | ||
Line 3,674: | Line 3,674: | ||
analysis of the plant structures. The central recorder is connected to the | analysis of the plant structures. The central recorder is connected to the | ||
triaxial accelerometers. | triaxial accelerometers. | ||
(continued) | |||
Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-2 Revision No. 47 BASES BACKGROUND When a very low "g" level threshold (0.01 g) has been exceeded at the (continued) reactor building accelerometer (elevation -17 foot), the system alerts the operator by actuating an event indication annunciator in the main control | Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-2 Revision No. 47 BASES BACKGROUND When a very low "g" level threshold (0.01 g) has been exceeded at the (continued) reactor building accelerometer (elevation -17 foot), the system alerts the operator by actuating an event indication annunciator in the main control | ||
Line 3,736: | Line 3,736: | ||
acceleration. SSCs designated Seismic Category I are designed to | acceleration. SSCs designated Seismic Category I are designed to | ||
remain functional following an SSE. | remain functional following an SSE. | ||
(continued) | |||
Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-3 Revision No. 47 BASES APPLICABLE When an earthquake occurs, it may not be known immediately how DESIGN BASES severe the effects of the earthquake are on plant equipment. The triaxial (continued) accelerometers provide time-history data on the seismic input to containment. The passive triaxial peak shock recorders record peak | Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-3 Revision No. 47 BASES APPLICABLE When an earthquake occurs, it may not be known immediately how DESIGN BASES severe the effects of the earthquake are on plant equipment. The triaxial (continued) accelerometers provide time-history data on the seismic input to containment. The passive triaxial peak shock recorders record peak | ||
Line 3,792: | Line 3,792: | ||
Note has been provided that allows separate Condition entry for each | Note has been provided that allows separate Condition entry for each | ||
inoperable seismic monitoring instrument. | inoperable seismic monitoring instrument. | ||
(continued) | |||
Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-4 Revision No. 47 BASES COMPENSATORY A.1 MEASURES (continued) With one or more seismic monitoring instruments inoperable, the ability to monitor vibratory ground motion and determine its effects on safety | Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-4 Revision No. 47 BASES COMPENSATORY A.1 MEASURES (continued) With one or more seismic monitoring instruments inoperable, the ability to monitor vibratory ground motion and determine its effects on safety | ||
Line 3,849: | Line 3,849: | ||
associated aftershocks) to verify that the affected instruments are still | associated aftershocks) to verify that the affected instruments are still | ||
properly calibrated. | properly calibrated. | ||
(continued) | |||
Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-5 Revision No. 47 BASES COMPENSATORY C.1, C.2, and C.3 (continued) | Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-5 Revision No. 47 BASES COMPENSATORY C.1, C.2, and C.3 (continued) | ||
Line 3,914: | Line 3,914: | ||
readability. If an instrument is outside the criteria, it may be an indication | readability. If an instrument is outside the criteria, it may be an indication | ||
that the instrument has drifted outside its limit. | that the instrument has drifted outside its limit. | ||
(continued) | |||
Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-6 Revision No. 47 BASES TEST TR 3.9.1 (continued) | Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-6 Revision No. 47 BASES TEST TR 3.9.1 (continued) | ||
Line 3,967: | Line 3,967: | ||
Reference 3. | Reference 3. | ||
REFERENCES 1. UFSAR Section 3.7.4. 2. 10 CFR 100, Appendix A. | REFERENCES 1. UFSAR Section 3.7.4. 2. 10 CFR 100, Appendix A. | ||
: 3. Regulatory Guide 1.12, "Instrumentation for Earthquakes." | : 3. Regulatory Guide 1.12, "Instrumentation for Earthquakes." | ||
Line 4,073: | Line 4,073: | ||
detection and isolation logic to single failure criteria, with approved exceptions (Reference 3, Section 3.6). | detection and isolation logic to single failure criteria, with approved exceptions (Reference 3, Section 3.6). | ||
(continued) | |||
CREV System Instrumentation B 3.12 Brunswick Unit 2 B 3.12-2 Revision No. 23 BASES (continued) | CREV System Instrumentation B 3.12 Brunswick Unit 2 B 3.12-2 Revision No. 23 BASES (continued) | ||
Line 4,127: | Line 4,127: | ||
the out of service time allowed for loss of redundancy at the system level. | the out of service time allowed for loss of redundancy at the system level. | ||
(continued) | |||
CREV System Instrumentation B 3.12 Brunswick Unit 2 B 3.12-3 Revision No. 57 BASES COMPENSATORY MEASURES (continued) | CREV System Instrumentation B 3.12 Brunswick Unit 2 B 3.12-3 Revision No. 57 BASES COMPENSATORY MEASURES (continued) | ||
Line 4,169: | Line 4,169: | ||
with the testing frequencies performed by other utilities with this type of instrumentation. | with the testing frequencies performed by other utilities with this type of instrumentation. | ||
(continued) | |||
CREV System Instrumentation B 3.12 Brunswick Unit 2 B 3.12-4 Revision No. 23 BASES TEST REQUIREMENTS (continued) | CREV System Instrumentation B 3.12 Brunswick Unit 2 B 3.12-4 Revision No. 23 BASES TEST REQUIREMENTS (continued) | ||
Line 4,200: | Line 4,200: | ||
REFERENCES | REFERENCES | ||
: 1. 10 CFR 50, Appendix A, General Design Criterion 19, Control Room. | : 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. | : 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. | ||
Line 4,247: | Line 4,247: | ||
acceptable level throughout the life of the plant. These programs are in accordance with Section XI of the ASME Boiler and Pressure Vessel | 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) | 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 | (Ref. 1) except where specific written relief has been granted by the | ||
Line 4,277: | Line 4,277: | ||
Chapter 0326, summarizes the NRC accepted methods available for | 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. | evaluating structural integrity of flaws in components including supports, classified as ASME Code Class 1, Class 2, and Class 3 components. | ||
(continued) | |||
Structural Integrity 3.14 Brunswick Unit 2 B 3.14-2 Revision No. 65 BASES TRMS (continued) | Structural Integrity 3.14 Brunswick Unit 2 B 3.14-2 Revision No. 65 BASES TRMS (continued) | ||
Line 4,353: | Line 4,353: | ||
met. The 72 hour Completion Time is deemed appropriate for providing a | met. The 72 hour Completion Time is deemed appropriate for providing a | ||
reasonable amount of time to perform the necessary evaluations. | reasonable amount of time to perform the necessary evaluations. | ||
(continued) | |||
Structural Integrity 3.14 Brunswick Unit 2 B 3.14-4 Revision No. 65 BASES COMPENSATORY A.1 (continued) | Structural Integrity 3.14 Brunswick Unit 2 B 3.14-4 Revision No. 65 BASES COMPENSATORY A.1 (continued) | ||
Line 4,479: | Line 4,479: | ||
standards referenced in the design basis documents, the affected | standards referenced in the design basis documents, the affected | ||
structure is either OPERABLE or functional. | structure is either OPERABLE or functional. | ||
(continued) | |||
Structural Integrity B 3.14 Brunswick Unit 2 B 3.14-6 Revision No. 65 BASES COMPENSATORY D.1, D.2, and D.3 (continued) | Structural Integrity B 3.14 Brunswick Unit 2 B 3.14-6 Revision No. 65 BASES COMPENSATORY D.1, D.2, and D.3 (continued) | ||
Line 4,529: | Line 4,529: | ||
Structural Integrity B 3.14 Brunswick Unit 2 B 3.14-7 Revision No. 65 BASES (continued) | Structural Integrity B 3.14 Brunswick Unit 2 B 3.14-7 Revision No. 65 BASES (continued) | ||
REFERENCES 1. 10 CFR 50.55a(g), Inservice Inspection Requirements. 2. ASME Code, Section XI, 2001 Edition with 2003 Addenda | 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 | : 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 | 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. | : 8. AD-OP-ALL-0105, Operability Determinations and Functionality Assessments. | ||
Line 4,593: | Line 4,593: | ||
water pump available, the conventional servic e water pump must be powered from a separate emergency bus to be considered OPERABLE. | water pump available, the conventional servic e water pump must be powered from a separate emergency bus to be considered OPERABLE. | ||
(continued) | |||
Service Water System OPERABILITY-Shutdown B 3.16 Brunswick Unit 2 B 3.16-2 Revision No. 58 BASES (continued) | Service Water System OPERABILITY-Shutdown B 3.16 Brunswick Unit 2 B 3.16-2 Revision No. 58 BASES (continued) | ||
Line 4,659: | Line 4,659: | ||
water pumps, the applicable decay heat removal systems must be declared inoperable. | water pumps, the applicable decay heat removal systems must be declared inoperable. | ||
(continued) | |||
Service Water System OPERABILITY-Shutdown B 3.16 Brunswick Unit 2 B 3.16-3 Revision No. 58 BASES (continued) | Service Water System OPERABILITY-Shutdown B 3.16 Brunswick Unit 2 B 3.16-3 Revision No. 58 BASES (continued) | ||
Line 4,718: | Line 4,718: | ||
considered OPERABLE when the individual components necessary to control operator | 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, | 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). | : 2. HEPA filter and charcoal adsorbers are not excessively restricting flow and are capable of performing their filtration functions, and 3. Ductwork and dampers are OPERABLE, and when air circulation exists (as required in Reference 3, Section 3.1). | ||
(continued) | |||
CREV System-Smoke Protection Mode B 3.18 Brunswick Unit 2 B 3.18-2 Revision No. 23 BASES TRMS (continued) Two additional OPERABILITY requirements apply to all modes of CREV System operation. The | CREV System-Smoke Protection Mode B 3.18 Brunswick Unit 2 B 3.18-2 Revision No. 23 BASES TRMS (continued) Two additional OPERABILITY requirements apply to all modes of CREV System operation. The | ||
Line 4,761: | Line 4,761: | ||
remaining subsystem to provide the required capabilities. | remaining subsystem to provide the required capabilities. | ||
(continued) | |||
CREV System-Smoke Protection Mode B 3.18 Brunswick Unit 2 B 3.18-3 Revision No. 23 BASES COMPENSATORY MEASURES (continued) | CREV System-Smoke Protection Mode B 3.18 Brunswick Unit 2 B 3.18-3 Revision No. 23 BASES COMPENSATORY MEASURES (continued) | ||
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REFERENCES | REFERENCES | ||
: 1. 10 CFR 50, Appendix A, General Design Criterion 19, Control Room. | : 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. | : 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. | : 5. NLU-83-673, TMI Action Item III.D.3.4-Control Room Habitability, NRC Safety Evaluation dated October 18, 1983. | ||
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exposure are OPERABLE in both subsystems. For the chlorine protection mode, a subsystem | exposure are OPERABLE in both subsystems. For the chlorine protection mode, a subsystem | ||
is considered OPERABLE when: 1. The isolation dampers are OPERABLE, and | 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. | : 2. The logic components necessary to achieve automatic isolation are functional, as described in Reference 3, Section 3.1. | ||
(continued) | |||
CREV System-Chlorine Protection Mode B 3.19 Brunswick Unit 2 B 3.19-2 Revision No. 23 BASES (continued) | CREV System-Chlorine Protection Mode B 3.19 Brunswick Unit 2 B 3.19-2 Revision No. 23 BASES (continued) | ||
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chlorine tank car from the site in an orderly manner. | chlorine tank car from the site in an orderly manner. | ||
(continued) | |||
CREV System-Chlorine Protection Mode B 3.19 Brunswick Unit 2 B 3.19-3 Revision No. 23 BASES COMPENSATORY MEASURES (continued) | CREV System-Chlorine Protection Mode B 3.19 Brunswick Unit 2 B 3.19-3 Revision No. 23 BASES COMPENSATORY MEASURES (continued) | ||
Line 4,904: | Line 4,904: | ||
event. | event. | ||
REFERENCES | REFERENCES | ||
: 1. 10 CFR 50, Appendix A, General Design Criterion 19, Control Room. | : 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. | : 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. | : 5. NLU-83-673, TMI Action Item III.D.3.4-Control Room Habitability, NRC Safety Evaluation dated October 18, 1983. | ||
Line 4,977: | Line 4,977: | ||
support function and due to the availability of the redundant train of the supported system. | support function and due to the availability of the redundant train of the supported system. | ||
(continued) | |||
Snubbers B 3.21 Brunswick Unit 2 B 3.21-2 Revision No. 66 BASES (continued) | Snubbers B 3.21 Brunswick Unit 2 B 3.21-2 Revision No. 66 BASES (continued) | ||
Line 5,003: | Line 5,003: | ||
support function. | support function. | ||
REFERENCES | 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). | : 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). | ||
Line 5,496: | Line 5,496: | ||
Brunswick Unit 2 B-2 Revision No. 44 TRM Table 3.3.1.1-1 (page 1 of 2) Reactor Protection System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-2 Revision No. 44 TRM Table 3.3.1.1-1 (page 1 of 2) Reactor Protection System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
NOMINAL TRIP SETPOINT | NOMINAL TRIP SETPOINT | ||
: 1. Intermediate Range Monitors | : 1. Intermediate Range Monitors | ||
: a. Neutron Flux-High | : a. Neutron Flux-High | ||
Line 5,504: | Line 5,504: | ||
117/125 divisions of full | 117/125 divisions of full | ||
scale | scale | ||
: b. Inop C51-IRM-A, B, C, D, E, F, G, H C72-K14A, B, C, D, E, F, G, H | : b. Inop C51-IRM-A, B, C, D, E, F, G, H C72-K14A, B, C, D, E, F, G, H | ||
NA | NA | ||
: 2. Average Power Range Monitors | : 2. Average Power Range Monitors | ||
: a. Neutron Flux-High (Setdown) | : a. Neutron Flux-High (Setdown) | ||
C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11 | C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11 | ||
15% RTP | 15% RTP | ||
: b. Simulated Thermal Power-High | : b. Simulated Thermal Power-High | ||
Line 5,522: | Line 5,522: | ||
C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11 | C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11 | ||
117.4% RTP | 117.4% RTP | ||
: d. Inop C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11 | : d. Inop C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11 | ||
NA | NA | ||
: e. 2-Out-of-4 Voter | : e. 2-Out-of-4 Voter | ||
C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11 | C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11 | ||
NA | NA | ||
: f. OPRM Upscale C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11 NA(c) 3. Reactor Vessel Steam Dome Pressure-High | : f. OPRM Upscale C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11 NA(c) 3. Reactor Vessel Steam Dome Pressure-High | ||
B21-PT-N023A, B, C, D B21-PTM-N023A-1, B-1, C-1, D-1 C72-K14A, B, C, D, E, F, G, H | B21-PT-N023A, B, C, D B21-PTM-N023A-1, B-1, C-1, D-1 C72-K14A, B, C, D, E, F, G, H | ||
1060 psig | 1060 psig | ||
: 4. Reactor Vessel Water Level-Low Level 1 | : 4. Reactor Vessel Water Level-Low Level 1 | ||
Line 5,542: | Line 5,542: | ||
166 inches | 166 inches | ||
(continued) | |||
(a) [0.55 (W - W) + 61.1% RTP] when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating." The setpoint value of W is defined in plant procedures. | (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. | ||
Line 5,561: | Line 5,561: | ||
C72-PT-N002A, B, C, D C72-PTM-N002A-1, B-1, C-1, D-1 C72-K14A, B, C, D, E, F, G, H | C72-PT-N002A, B, C, D C72-PTM-N002A-1, B-1, C-1, D-1 C72-K14A, B, C, D, E, F, G, H | ||
1.7 psig | 1.7 psig | ||
: 7. Scram Discharge Volume Water Level-High | : 7. Scram Discharge Volume Water Level-High | ||
C12-LSH-N013A, B, C, D C12-LSH-4516A, B, C, D C72-K14A, B, C, D, E, F, G, H | C12-LSH-N013A, B, C, D C12-LSH-4516A, B, C, D C72-K14A, B, C, D, E, F, G, H | ||
104 gallons | 104 gallons | ||
: 8. Turbine Stop Valve-Closure | : 8. Turbine Stop Valve-Closure | ||
Line 5,575: | Line 5,575: | ||
EHC-PSL-1756, 1757, 1758, 1759 C72-K14A, B, C, D, E, F, G, H | EHC-PSL-1756, 1757, 1758, 1759 C72-K14A, B, C, D, E, F, G, H | ||
600 psig | 600 psig | ||
: 10. Reactor Mode Switch-Shutdown Position | : 10. Reactor Mode Switch-Shutdown Position | ||
C72-CS-S1 | C72-CS-S1 | ||
NA | NA | ||
: 11. Manual Scram | : 11. Manual Scram | ||
Line 5,591: | Line 5,591: | ||
TRM TS Instrument List Appendix B | TRM TS Instrument List Appendix B | ||
Brunswick Unit 2 B-4 Revision No. 44 TRM Table 3.3.1.2-1 (page 1 of 1) Source Range Monitor Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-4 Revision No. 44 TRM Table 3.3.1.2-1 (page 1 of 1) Source Range Monitor Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
: 1. Source Range Monitor | : 1. Source Range Monitor | ||
Line 5,599: | Line 5,599: | ||
Brunswick Unit 2 B-5 Revision No. 23 TRM Table 3.3.2.1-1 (page 1 of 1) Control Rod Block Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-5 Revision No. 23 TRM Table 3.3.2.1-1 (page 1 of 1) Control Rod Block Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
NOMINAL TRIP SETPOINT | NOMINAL TRIP SETPOINT | ||
: 1. Rod Block Monitor | : 1. Rod Block Monitor | ||
: a. Low Power Range-Upscale | : a. Low Power Range-Upscale | ||
C51-RBMA-AR21 C51-RBMB-AR22 | C51-RBMA-AR21 C51-RBMB-AR22 | ||
(a) | (a) | ||
: b. Intermediate Power Range-Upscale | : b. Intermediate Power Range-Upscale | ||
C51-RBMA-AR21 C51-RBMB-AR22 | C51-RBMA-AR21 C51-RBMB-AR22 | ||
(a) | |||
: c. High Power Range-Upscale | : c. High Power Range-Upscale | ||
C51-RBMA-AR21 C51-RBMB-AR22 | C51-RBMA-AR21 C51-RBMB-AR22 | ||
(a) | |||
: d. Inop C51-RBMA-AR21 C51-RBMB-AR22 | : d. Inop C51-RBMA-AR21 C51-RBMB-AR22 | ||
NA | NA | ||
: 2. Rod Worth Minimizer | : 2. Rod Worth Minimizer | ||
2-C12-CNV-5516 19.1% rated steam flow | 2-C12-CNV-5516 19.1% rated steam flow | ||
: 3. Reactor Mode Switch-Shutdown Position | : 3. Reactor Mode Switch-Shutdown Position | ||
Line 5,629: | Line 5,629: | ||
Brunswick Unit 2 B-6 Revision No. 23 TRM Table 3.3.2.2-1 (page 1 of 1) Feedwater and Main Turbine High Water Level Trip Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-6 Revision No. 23 TRM Table 3.3.2.2-1 (page 1 of 1) Feedwater and Main Turbine High Water Level Trip Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
NOMINAL TRIP SETPOINT | NOMINAL TRIP SETPOINT | ||
: 1. Feedwater Pumps | : 1. Feedwater Pumps | ||
: a. Reactor Vessel Water Level-High | : a. Reactor Vessel Water Level-High | ||
C32-LT-N0O4A, B, C C32-LY-K602A - A1, B1, A4 C32-LY-K602C - A1, B1, A4 C32-LY-K602E - A1, B1, A4 C32-LC-R602A, B | C32-LT-N0O4A, B, C C32-LY-K602A - A1, B1, A4 C32-LY-K602C - A1, B1, A4 C32-LY-K602E - A1, B1, A4 C32-LC-R602A, B | ||
206 inches | 206 inches | ||
: 2. Main Turbine | : 2. Main Turbine | ||
: a. Reactor Vessel Water Level-High | : a. Reactor Vessel Water Level-High | ||
Line 5,645: | Line 5,645: | ||
TRM TS Instrument List Appendix B | TRM TS Instrument List Appendix B | ||
Brunswick Unit 2 B-7 Revision No. 39 TRM Table 3.3.3.1-1 (page 1 of 1) Post Accident Monitoring Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-7 Revision No. 39 TRM Table 3.3.3.1-1 (page 1 of 1) Post Accident Monitoring Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
: 1. Reactor Vessel Pressure | : 1. Reactor Vessel Pressure | ||
: 2. Reactor Vessel Water Level | : 2. Reactor Vessel Water Level | ||
: a. -150 inches to +150 inches | : a. -150 inches to +150 inches | ||
: b. 0 inches to +210 inches | : b. 0 inches to +210 inches | ||
: c. +150 inches to +550 inches | : c. +150 inches to +550 inches | ||
: 3. Suppression Chamber Water Level | : 3. Suppression Chamber Water Level | ||
: 4. Suppression Chamber Water Temperature | : 4. Suppression Chamber Water Temperature | ||
: 5. Suppression Chamber Pressure | : 5. Suppression Chamber Pressure | ||
: 6. Drywell Pressure | : 6. Drywell Pressure | ||
: 7. Drywell Temperature | : 7. Drywell Temperature | ||
: 8. PCIV Position | : 8. PCIV Position | ||
: 9. (Not Used.) | : 9. (Not Used.) | ||
: 10. Drywell Area Radiation | : 10. Drywell Area Radiation | ||
Line 5,724: | Line 5,724: | ||
GAS SAMPLE RETURN OUTBOARD ISOLATION XU-79 TRM TS Instrument List Appendix B | GAS SAMPLE RETURN OUTBOARD ISOLATION XU-79 TRM TS Instrument List Appendix B | ||
Brunswick Unit 2 B-13 Revision No. 23 TRM Table 3.3.3.2-1 (page 1 of 1) Remote Shutdown Monitoring Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-13 Revision No. 23 TRM Table 3.3.3.2-1 (page 1 of 1) Remote Shutdown Monitoring Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
: 1. Reactor Vessel Pressure | : 1. Reactor Vessel Pressure | ||
: 2. Reactor Vessel Water Level | : 2. Reactor Vessel Water Level | ||
: 3. Suppression Chamber Water Level | : 3. Suppression Chamber Water Level | ||
: 4. Suppression Chamber Water Temperature | : 4. Suppression Chamber Water Temperature | ||
: 5. Drywell Pressure | : 5. Drywell Pressure | ||
: 6. Drywell Temperature | : 6. Drywell Temperature | ||
: 7. Residual Heat Removal System Flow | : 7. Residual Heat Removal System Flow | ||
Line 5,750: | Line 5,750: | ||
Brunswick Unit 2 B-14 Revision No. 23 TRM Table 3.3.4.1-1 (page 1 of 1) Anticipated Transient Without Scram Recirculation Pump Trip Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-14 Revision No. 23 TRM Table 3.3.4.1-1 (page 1 of 1) Anticipated Transient Without Scram Recirculation Pump Trip Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
NOMINAL TRIP SETPOINT | NOMINAL TRIP SETPOINT | ||
: 1. Reactor Vessel Water Level-Low Level 2 | : 1. Reactor Vessel Water Level-Low Level 2 | ||
B21-LT-N024A-2, B-2 B21-LT-N025A-2, B-2 B21-LTM-N024A-2, B-2 B21-LTM-N025A-2, B-2 | B21-LT-N024A-2, B-2 B21-LT-N025A-2, B-2 B21-LTM-N024A-2, B-2 B21-LTM-N025A-2, B-2 | ||
105 inches | 105 inches | ||
: 2. Reactor Vessel Steam Dome Pressure-High | : 2. Reactor Vessel Steam Dome Pressure-High | ||
Line 5,765: | Line 5,765: | ||
Brunswick Unit 2 B-15 Revision No. 23 TRM Table 3.3.5.1-1 (page 1 of 2) Emergency Core Cooling System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-15 Revision No. 23 TRM Table 3.3.5.1-1 (page 1 of 2) Emergency Core Cooling System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
NOMINAL TRIP SETPOINT | NOMINAL TRIP SETPOINT | ||
: 1. Core Spray System | : 1. Core Spray System | ||
: a. Reactor Vessel Water Level-Low Level 3 | : a. Reactor Vessel Water Level-Low Level 3 | ||
B21-LT-N031A, B, C, D B21-LTS-N031A-4, B-4, C-4, D-4 | B21-LT-N031A, B, C, D B21-LTS-N031A-4, B-4, C-4, D-4 | ||
45 inches | 45 inches | ||
: b. Drywell Pressure-High | : b. Drywell Pressure-High | ||
E11-PT-N011A, B, C, D E11-PTS-N011A-2, B-2, C-2, D-2 | E11-PT-N011A, B, C, D E11-PTS-N011A-2, B-2, C-2, D-2 | ||
1.7 psig | 1.7 psig | ||
: c. Reactor Steam Dome Pressure-Low | : c. Reactor Steam Dome Pressure-Low | ||
B21-PT-N021A, B, C, D, B21-PTS-N021A-2, B-2, C-2, D-2 | B21-PT-N021A, B, C, D, B21-PTS-N021A-2, B-2, C-2, D-2 | ||
410 psig | 410 psig | ||
: d. Core Spray Pump Start-Time Delay Relay | : d. Core Spray Pump Start-Time Delay Relay | ||
E21-K16A, B STR/2A-1, STR/2A-2 STR/2B-1, STR/2B-2 | E21-K16A, B STR/2A-1, STR/2A-2 STR/2B-1, STR/2B-2 | ||
15 seconds | 15 seconds | ||
: 2. Low Pressure Coolant Injection (LPCI) System | : 2. Low Pressure Coolant Injection (LPCI) System | ||
: a. Reactor Vessel Water Level-Low Level 3 | : a. Reactor Vessel Water Level-Low Level 3 | ||
B21-LT-N031A, B, C, D B21-LTS-N031A-4, B-4, C-4, D-4 | B21-LT-N031A, B, C, D B21-LTS-N031A-4, B-4, C-4, D-4 | ||
45 inches | 45 inches | ||
: b. Drywell Pressure-High | : b. Drywell Pressure-High | ||
E11-PT-N011A, B, C, D E11-PTM-N011A-1, B-1, C-1, D-1 | E11-PT-N011A, B, C, D E11-PTM-N011A-1, B-1, C-1, D-1 | ||
1.7 psig | 1.7 psig | ||
: c. Reactor Steam Dome Pressure-Low | : c. Reactor Steam Dome Pressure-Low | ||
B21-PT-N021A, B, C, D B21-PTS-N021A-2, B-2, C-2, D-2 | B21-PT-N021A, B, C, D B21-PTS-N021A-2, B-2, C-2, D-2 | ||
410 psig | 410 psig | ||
: d. Reactor Steam Dome Pressure-Low (Recirculation Pump Discharge Valve Permissive) | : d. Reactor Steam Dome Pressure-Low (Recirculation Pump Discharge Valve Permissive) | ||
B21-PT-N021A, B, C, D B21-PTM-N021A-1, B-1, C-1, D-1 | B21-PT-N021A, B, C, D B21-PTM-N021A-1, B-1, C-1, D-1 | ||
310 psig | 310 psig | ||
: e. Reactor Vessel Shroud Level | : e. Reactor Vessel Shroud Level | ||
B21-LT-N036, B21-LT-N037 B21-LTM-N036-1, B21-LTM-N037-1 | B21-LT-N036, B21-LT-N037 B21-LTM-N036-1, B21-LTM-N037-1 | ||
-47.4 inches | -47.4 inches | ||
: f. RHR Pump Start-Time Delay Relay | : f. RHR Pump Start-Time Delay Relay | ||
STR/2A-1, STR/2A-2, STR/2B-1, STR/2B-2, STR/1A-3, STR/1A-4, STR/1B-3, STR/1B-4 | STR/2A-1, STR/2A-2, STR/2B-1, STR/2B-2, STR/1A-3, STR/1A-4, STR/1B-3, STR/1B-4 | ||
10 seconds | 10 seconds | ||
: 3. High Pressure Coolant Injection (HPCI) System | : 3. High Pressure Coolant Injection (HPCI) System | ||
: a. Reactor Vessel Water Level-Low Level 2 | : a. Reactor Vessel Water Level-Low Level 2 | ||
B21-LT-N031A, B, C, D B21-LTS-N031A-2, B-2, C-2, D-2 | B21-LT-N031A, B, C, D B21-LTS-N031A-2, B-2, C-2, D-2 | ||
105 inches | 105 inches | ||
: b. Drywell Pressure-High | : b. Drywell Pressure-High | ||
Line 5,829: | Line 5,829: | ||
1.7 psig | 1.7 psig | ||
(continued) | |||
TRM TS Instrument List Appendix B | TRM TS Instrument List Appendix B | ||
Brunswick Unit 2 B-16 Revision No. 23 TRM Table 3.3.5.1-1 (page 2 of 2) Emergency Core Cooling System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-16 Revision No. 23 TRM Table 3.3.5.1-1 (page 2 of 2) Emergency Core Cooling System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
NOMINAL TRIP SETPOINT | NOMINAL TRIP SETPOINT | ||
: 3. High Pressure Coolant Injection (HPCI) System (continued) | : 3. High Pressure Coolant Injection (HPCI) System (continued) | ||
: c. Reactor Vessel Water Level-High | : c. Reactor Vessel Water Level-High | ||
B21-LT-N017 B-2, D-2 B21-LTM-N017 B-2, D-2 | B21-LT-N017 B-2, D-2 B21-LTM-N017 B-2, D-2 | ||
206 inches | 206 inches | ||
: d. Condensate Storage Tank Level-Low | : d. Condensate Storage Tank Level-Low | ||
E41-LS-N0O2, E41-LS-N003 | E41-LS-N0O2, E41-LS-N003 | ||
23 feet 5 inches | 23 feet 5 inches | ||
: e. Suppression Chamber Water Level-High | : e. Suppression Chamber Water Level-High | ||
E41-LSH-N015A, B | E41-LSH-N015A, B | ||
-25 inches | -25 inches | ||
: 4. Automatic Depressurization System (ADS) Trip System A | : 4. Automatic Depressurization System (ADS) Trip System A | ||
: a. Reactor Vessel Water Level-Low Level 3 | : a. Reactor Vessel Water Level-Low Level 3 | ||
B21-LT-N031B, D B21-LTS-N031B-3, D-3 | B21-LT-N031B, D B21-LTS-N031B-3, D-3 | ||
45 inches | 45 inches | ||
: b. ADS Timer | : b. ADS Timer | ||
B21-TDPU-K5A | B21-TDPU-K5A | ||
83 seconds | 83 seconds | ||
: c. Reactor Vessel Water Level-Low Level 1 | : c. Reactor Vessel Water Level-Low Level 1 | ||
B21-LT-N042B B21-LTM-N042B-1 | B21-LT-N042B B21-LTM-N042B-1 | ||
166 inches | 166 inches | ||
: d. Core Spray Pump Discharge Pressure-High | : d. Core Spray Pump Discharge Pressure-High | ||
E21-PS-N008B E21-PS-N009B | E21-PS-N008B E21-PS-N009B | ||
115 psig | 115 psig | ||
: e. RHR (LPCI Mode) Pump Discharge Pressure-High | : e. RHR (LPCI Mode) Pump Discharge Pressure-High | ||
E11-PS-N016B, D E11-PS-N020B, D | E11-PS-N016B, D E11-PS-N020B, D | ||
115 psig | 115 psig | ||
: 5. ADS Trip System B | : 5. ADS Trip System B | ||
: a. Reactor Vessel Water Level-Low Level 3 | : a. Reactor Vessel Water Level-Low Level 3 | ||
B21-LT-N031A, C B21-LTS-N031A-3, C-3 | B21-LT-N031A, C B21-LTS-N031A-3, C-3 | ||
45 inches | 45 inches | ||
: b. ADS Timer | : b. ADS Timer | ||
B21-TDPU-K5B | B21-TDPU-K5B | ||
83 seconds | 83 seconds | ||
: c. Reactor Vessel Water Level-Low Level 1 | : c. Reactor Vessel Water Level-Low Level 1 | ||
B21-LT-N042A B21-LTM-N042A-1 | B21-LT-N042A B21-LTM-N042A-1 | ||
166 inches | 166 inches | ||
: d. Core Spray Pump Discharge Pressure-High | : d. Core Spray Pump Discharge Pressure-High | ||
E21-PS-N008A E21-PS-N009A | E21-PS-N008A E21-PS-N009A | ||
115 psig | 115 psig | ||
: e. RHR (LPCI Mode) Pump Discharge Pressure-High E11-PS-N016A, C E11-PS-N020A, C | : e. RHR (LPCI Mode) Pump Discharge Pressure-High E11-PS-N016A, C E11-PS-N020A, C | ||
Line 5,904: | Line 5,904: | ||
Brunswick Unit 2 B-17 Revision No. 23 TRM Table 3.3.5.2-1 (page 1 of 1) Reactor Core Isolation Cooling System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-17 Revision No. 23 TRM Table 3.3.5.2-1 (page 1 of 1) Reactor Core Isolation Cooling System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
NOMINAL TRIP SETPOINT | NOMINAL TRIP SETPOINT | ||
: 1. Reactor Vessel Water Level-Low Level 2 | : 1. Reactor Vessel Water Level-Low Level 2 | ||
B21-LT-N031A, B, C, D B21-LTM-N031A-1, B-1, C-1, D-1 | B21-LT-N031A, B, C, D B21-LTM-N031A-1, B-1, C-1, D-1 | ||
105 inches | 105 inches | ||
: 2. Reactor Vessel Water Level-High | : 2. Reactor Vessel Water Level-High | ||
B21-LT-N017A-2, C-2 B21-LTM-N017A-2, C-2 | B21-LT-N017A-2, C-2 B21-LTM-N017A-2, C-2 | ||
206 inches | 206 inches | ||
: 3. Condensate Storage Tank Level-Low | : 3. Condensate Storage Tank Level-Low | ||
Line 5,924: | Line 5,924: | ||
Brunswick Unit 2 B-18 Revision No. 28 TRM Table 3.3.6.1-1 (page 1 of 5) Primary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-18 Revision No. 28 TRM Table 3.3.6.1-1 (page 1 of 5) Primary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
NOMINAL TRIP SETPOINT | NOMINAL TRIP SETPOINT | ||
: 1. Main Steam Line Isolation | : 1. Main Steam Line Isolation | ||
: a. Reactor Vessel Water Level-Low Level 3 | : a. Reactor Vessel Water Level-Low Level 3 | ||
B21-LT-N024A-1, B-1 B21-LT-N025A-1, B-1 B21-LTS-N024A-1-2, B-1-2 B21-LTS-N025A-1-2, B-1-2 | B21-LT-N024A-1, B-1 B21-LT-N025A-1, B-1 B21-LTS-N024A-1-2, B-1-2 B21-LTS-N025A-1-2, B-1-2 | ||
45 inches | 45 inches | ||
: b. Main Steam Line Pressure-Low | : b. Main Steam Line Pressure-Low | ||
Line 5,939: | Line 5,939: | ||
B21-PDT-N006A, B, C, D B21-PDT-N007A, B, C, D B21-PDT-N008A, B, C, D B21-PDT-N009A, B, C, D B21-PDTM-N006A-1, B-1, C-1, D-1 B21-PDTM-N007A-1, B-1, C-1, D-1 B21-PDTM-N008A-1, B-1, C-1, D-1 B21-PDTM-N009A-1, B-1, C-1, D-1 | B21-PDT-N006A, B, C, D B21-PDT-N007A, B, C, D B21-PDT-N008A, B, C, D B21-PDT-N009A, B, C, D B21-PDTM-N006A-1, B-1, C-1, D-1 B21-PDTM-N007A-1, B-1, C-1, D-1 B21-PDTM-N008A-1, B-1, C-1, D-1 B21-PDTM-N009A-1, B-1, C-1, D-1 | ||
137% rated steam flow | 137% rated steam flow | ||
: d. Condenser Vacuum-Low | : d. Condenser Vacuum-Low | ||
B21-PT-N056A, B, C, D B21-PTM-N056A-1, B-1, C-1, D-1 | B21-PT-N056A, B, C, D B21-PTM-N056A-1, B-1, C-1, D-1 | ||
10 inches Hg vacuum | 10 inches Hg vacuum | ||
: e. Main Steam Isolation Valve Pit Temperature-High | : e. Main Steam Isolation Valve Pit Temperature-High | ||
Line 5,953: | Line 5,953: | ||
B21-PDTS-N006A-2 B21-PDTS-N007B-2 B21-PDTS-N008C-2 B21-PDTS-N009D-2 | B21-PDTS-N006A-2 B21-PDTS-N007B-2 B21-PDTS-N008C-2 B21-PDTS-N009D-2 | ||
30% rated steam flow 2. Primary Containment Isolation | 30% rated steam flow 2. Primary Containment Isolation | ||
: a. Reactor Vessel Water Level-Low Level 1 | : a. Reactor Vessel Water Level-Low Level 1 | ||
B21-LT-N017A-1, B-1, C-1, D-1 B21-LTM-N017A-1, B-1, C-1, D-1 | B21-LT-N017A-1, B-1, C-1, D-1 B21-LTM-N017A-1, B-1, C-1, D-1 | ||
166 inches | 166 inches | ||
: b. Drywell Pressure-High | : b. Drywell Pressure-High | ||
C72-PT-N002A, B, C, D C72-PTM-N002A-1, B-1, C-1, D-1 E11-PT-N011A, B, C, D E11-PTS-N011A-2, B-2, C-2, D-2 | C72-PT-N002A, B, C, D C72-PTM-N002A-1, B-1, C-1, D-1 E11-PT-N011A, B, C, D E11-PTS-N011A-2, B-2, C-2, D-2 | ||
1.7 psig | 1.7 psig | ||
: c. Main Stack Radiation-High | : c. Main Stack Radiation-High | ||
2-D12-RM-80S | 2-D12-RM-80S | ||
(a) | |||
: d. Reactor Building Exhaust Radiation-High | : d. Reactor Building Exhaust Radiation-High | ||
D12-RM-K609A, B D12-RE-N010A, B | D12-RM-K609A, B D12-RE-N010A, B | ||
4 mR/hr (continued) | 4 mR/hr (continued) | ||
(a) Nominal Trip Setpoint established in accordance with the methodology in the Offsite Dose Calculation Manual. | |||
TRM TS Instrument List Appendix B | TRM TS Instrument List Appendix B | ||
Brunswick Unit 2 B-19 Revision No. 23 TRM Table 3.3.6.1-1 (page 2 of 5) Primary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-19 Revision No. 23 TRM Table 3.3.6.1-1 (page 2 of 5) Primary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
NOMINAL TRIP SETPOINT | NOMINAL TRIP SETPOINT | ||
: 3. High Pressure Coolant Injection (HPCI) System Isolation | : 3. High Pressure Coolant Injection (HPCI) System Isolation | ||
: a. HPCI Steam Line Flow-High | : a. HPCI Steam Line Flow-High | ||
E41-PDTM-N004-1, E41-PDTM-N005-1 E41-PDTS-N004-2, E41-PDTS-N005-2 | E41-PDTM-N004-1, E41-PDTM-N005-1 E41-PDTS-N004-2, E41-PDTS-N005-2 | ||
220% rated steam flow | 220% rated steam flow | ||
: b. HPCI Steam Line Flow-High Time Delay Relay | : b. HPCI Steam Line Flow-High Time Delay Relay | ||
E41-TDR-K33, E41-TDR-K43 5 seconds | E41-TDR-K33, E41-TDR-K43 5 seconds | ||
: c. HPCI Steam Supply Line Pressure-Low | : c. HPCI Steam Supply Line Pressure-Low | ||
E41-PSL-N001A, B, C, D | E41-PSL-N001A, B, C, D | ||
115 psig | 115 psig | ||
: d. HPCI Turbine Exhaust Diaphragm Pressure-High | : d. HPCI Turbine Exhaust Diaphragm Pressure-High | ||
E41-PSH-N012A, B, C, D | E41-PSH-N012A, B, C, D | ||
7 psig | 7 psig | ||
: e. Drywell Pressure-High | : e. Drywell Pressure-High | ||
E11-PT-N011C, D E11-PTS-N011C-2, D-2 | E11-PT-N011C, D E11-PTS-N011C-2, D-2 | ||
1.7 psig | 1.7 psig | ||
: f. HPCI Steam Line Area Temperature-High B21-XY-5948A Ch. A5-2: E41-TE-3488 B21-XY-5948B Ch. A5-2: E41-TE-3489 | : f. HPCI Steam Line Area Temperature-High B21-XY-5948A Ch. A5-2: E41-TE-3488 B21-XY-5948B Ch. A5-2: E41-TE-3489 | ||
Line 6,010: | Line 6,010: | ||
B21-XY-5948A Ch. A2-2: E41-TE-3314 Ch. A5-1: E51-TE-N025C B21-XY-5948B Ch. A5-1: E51-TE-N025D | B21-XY-5948A Ch. A2-2: E41-TE-3314 Ch. A5-1: E51-TE-N025C B21-XY-5948B Ch. A5-1: E51-TE-N025D | ||
165°F 190°F 190°F | 165°F 190°F 190°F | ||
: h. HPCI Steam Line Tunnel Differential Temperature-High | : h. HPCI Steam Line Tunnel Differential Temperature-High | ||
B21-XY-5948A Ch. A6-1: E51-TE-N026C and E51-TE-N027C B21-XY-5948B Ch. A6-1: E51-TE-N026D and E51-TE-N027D | B21-XY-5948A Ch. A6-1: E51-TE-N026C and E51-TE-N027C B21-XY-5948B Ch. A6-1: E51-TE-N026D and E51-TE-N027D | ||
47°F | 47°F | ||
: i. HPCI Equipment Area Temperature-High | : i. HPCI Equipment Area Temperature-High | ||
Line 6,025: | Line 6,025: | ||
Brunswick Unit 2 B-20 Revision No. 23 TRM Table 3.3.6.1-1 (page 3 of 5) Primary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-20 Revision No. 23 TRM Table 3.3.6.1-1 (page 3 of 5) Primary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
NOMINAL TRIP SETPOINT | NOMINAL TRIP SETPOINT | ||
: 4. Reactor Core Isolation Cooling (RCIC) System Isolation | : 4. Reactor Core Isolation Cooling (RCIC) System Isolation | ||
: a. RCIC Steam Line Flow-High | : a. RCIC Steam Line Flow-High | ||
E51-PDTM-N017-1, E51-PDTM-N018-1 E51-PDTS-N017-2, E51-PDTS-N018-2 | E51-PDTM-N017-1, E51-PDTM-N018-1 E51-PDTS-N017-2, E51-PDTS-N018-2 | ||
220% rated steam flow | 220% rated steam flow | ||
: b. RCIC Steam Line Flow-High Time Delay Relay | : b. RCIC Steam Line Flow-High Time Delay Relay | ||
E51-TDR-K32, E51-TDR-K12 | E51-TDR-K32, E51-TDR-K12 | ||
5 seconds | 5 seconds | ||
: c. RCIC Steam Supply Line Pressure-Low | : c. RCIC Steam Supply Line Pressure-Low | ||
E51-PS-N019A, B, C, D | E51-PS-N019A, B, C, D | ||
70 | 70 | ||
: d. RCIC Turbine Exhaust Diaphragm Pressure-High | : d. RCIC Turbine Exhaust Diaphragm Pressure-High | ||
E51-PS-N012A, B, C, D | E51-PS-N012A, B, C, D | ||
5 psig | 5 psig | ||
: e. Drywell Pressure-High | : e. Drywell Pressure-High | ||
E11-PT-N011A, B E11-PTS-N011A-2, B-2 | E11-PT-N011A, B E11-PTS-N011A-2, B-2 | ||
1.7 psig | 1.7 psig | ||
: f. RCIC Steam Line Area Temperature-High | : f. RCIC Steam Line Area Temperature-High | ||
Line 6,060: | Line 6,060: | ||
B21-XY-5949A Ch. A3-4: E51-TE-3319 Ch. A3-3: E51-TE-N025A B21-XY-5949B Ch. A3-3: E51-TE-N025B | B21-XY-5949A Ch. A3-4: E51-TE-3319 Ch. A3-3: E51-TE-N025A B21-XY-5949B Ch. A3-3: E51-TE-N025B | ||
165°F 190°F 190°F | 165°F 190°F 190°F | ||
: h. RCIC Steam Line Tunnel and Area Temperature-High Time Delay B21-XY-5949A Ch. A3-3: E51-TE-N025A Ch. A3-4: E51-TE-3319 Ch. A4-3: E51-TE-N026A and E51-TE-N027A Ch. A6-4: E51-TE-3487 B21-XY-5949B Ch. A3-3: E51-TE-N025B Ch. A4-3: E51-TE-N026B and E51-TE-N027B Ch. A4-4: E51-TE-3320 | : h. RCIC Steam Line Tunnel and Area Temperature-High Time Delay B21-XY-5949A Ch. A3-3: E51-TE-N025A Ch. A3-4: E51-TE-3319 Ch. A4-3: E51-TE-N026A and E51-TE-N027A Ch. A6-4: E51-TE-3487 B21-XY-5949B Ch. A3-3: E51-TE-N025B Ch. A4-3: E51-TE-N026B and E51-TE-N027B Ch. A4-4: E51-TE-3320 | ||
27 minutes | 27 minutes | ||
: i. RCIC Steam Line Tunnel Differential Temperature-High | : i. RCIC Steam Line Tunnel Differential Temperature-High | ||
Line 6,070: | Line 6,070: | ||
47°F | 47°F | ||
(continued) | |||
TRM TS Instrument List Appendix B | TRM TS Instrument List Appendix B | ||
Brunswick Unit 2 B-21 Revision No. 23 TRM Table 3.3.6.1-1 (page 4 of 5) Primary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-21 Revision No. 23 TRM Table 3.3.6.1-1 (page 4 of 5) Primary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
NOMINAL TRIP SETPOINT | NOMINAL TRIP SETPOINT | ||
: 4. RCIC System Isolation (continued) | : 4. RCIC System Isolation (continued) | ||
: j. RCIC Equipment Area Temperature-High | : j. RCIC Equipment Area Temperature-High | ||
Line 6,085: | Line 6,085: | ||
B21-XY-5949A Ch. A2-3: E51-TE-N021A and E51-TE-N022A B21-XY-5949B Ch. A2-3: E51-TE-N021B and E51-TE-N022B | B21-XY-5949A Ch. A2-3: E51-TE-N021A and E51-TE-N022A B21-XY-5949B Ch. A2-3: E51-TE-N021B and E51-TE-N022B | ||
47°F | 47°F | ||
: 5. Reactor Water Cleanup (RWCU) System Isolation | : 5. Reactor Water Cleanup (RWCU) System Isolation | ||
: a. Differential Flow-High | : a. Differential Flow-High | ||
B21-XY-5949B G31-FT-N012 G31-FT-N041 G31-FT-N036 | B21-XY-5949B G31-FT-N012 G31-FT-N041 G31-FT-N036 | ||
43 gpm | 43 gpm | ||
: b. Differential Flow-High Time Delay | : b. Differential Flow-High Time Delay | ||
B21-XY-5949B G31-FT-N012 G31-FT-N041 G31-FT-N036 | B21-XY-5949B G31-FT-N012 G31-FT-N041 G31-FT-N036 | ||
28.5 minutes | 28.5 minutes | ||
: c. Area Temperature-High | : c. Area Temperature-High | ||
Line 6,107: | Line 6,107: | ||
47°F | 47°F | ||
(continued) | |||
TRM TS Instrument List Appendix B | TRM TS Instrument List Appendix B | ||
Brunswick Unit 2 B-22 Revision No. 48 TRM Table 3.3.6.1-1 (page 5 of 5) Primary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-22 Revision No. 48 TRM Table 3.3.6.1-1 (page 5 of 5) Primary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
NOMINAL TRIP SETPOINT | NOMINAL TRIP SETPOINT | ||
: 5. Reactor Water Cleanup (RWCU) System Isolation (continued) | : 5. Reactor Water Cleanup (RWCU) System Isolation (continued) | ||
: e. Piping Outside RWCU Rooms Area Temperature-High | : e. Piping Outside RWCU Rooms Area Temperature-High | ||
Line 6,120: | Line 6,120: | ||
115°F f. SLC System Initiation | 115°F f. SLC System Initiation | ||
C41A-S1 NA | C41A-S1 NA | ||
: g. Reactor Vessel Water Level-Low Level 2 | : g. Reactor Vessel Water Level-Low Level 2 | ||
B21-LT-N024A-1, B-1 B21-LT-N025A-1, B-1 B21-LTM-N024A-1-1, B-1-1 B21-LTM-N025A-1-1, B-1-1 | B21-LT-N024A-1, B-1 B21-LT-N025A-1, B-1 B21-LTM-N024A-1-1, B-1-1 B21-LTM-N025A-1-1, B-1-1 | ||
105 inches | 105 inches | ||
: 6. RHR Shutdown Cooling System Isolation | : 6. RHR Shutdown Cooling System Isolation | ||
: a. Reactor Steam Dome Pressure-High | : a. Reactor Steam Dome Pressure-High | ||
B32-PS-N018A-1, B | B32-PS-N018A-1, B | ||
130.8 psig | 130.8 psig | ||
: b. Reactor Vessel Water Level- Low Level 1 | : b. Reactor Vessel Water Level- Low Level 1 | ||
: 7. Traversing In-Core Probe Isolation | : 7. Traversing In-Core Probe Isolation | ||
: a. Reactor Vessel Water Level-Low Level 1 | : a. Reactor Vessel Water Level-Low Level 1 | ||
: b. Drywell Pressure-High | : b. Drywell Pressure-High | ||
Line 6,148: | Line 6,148: | ||
Brunswick Unit 2 B-23 Revision No. 23 TRM Table 3.3.6.2-1 (page 1 of 1) Secondary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-23 Revision No. 23 TRM Table 3.3.6.2-1 (page 1 of 1) Secondary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
NOMINAL TRIP SETPOINT | NOMINAL TRIP SETPOINT | ||
: 1. Reactor Vessel Water Level-Low Level 2 | : 1. Reactor Vessel Water Level-Low Level 2 | ||
B21-LT-N024A-1, B-1 B21-LT-N025A-1, B-1 B21-LTM-N024A-1-1, B-1-1 B21-LTM-N025A-1-1, B-1-1 | B21-LT-N024A-1, B-1 B21-LT-N025A-1, B-1 B21-LTM-N024A-1-1, B-1-1 B21-LTM-N025A-1-1, B-1-1 | ||
105 inches | 105 inches | ||
: 2. Drywell Pressure-High | : 2. Drywell Pressure-High | ||
C72-PT-N002A, B, C, D C72-PTM-N002A-1, B-1, C-1, D-1 | C72-PT-N002A, B, C, D C72-PTM-N002A-1, B-1, C-1, D-1 | ||
1.7 psig | 1.7 psig | ||
: 3. Reactor Building Exhaust Radiation-High | : 3. Reactor Building Exhaust Radiation-High | ||
Line 6,168: | Line 6,168: | ||
Brunswick Unit 2 B-24 Revision No. 34 TRM Table 3.3.7.1-1 (page 1 of 1) Control Room Emergency Ventilation System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-24 Revision No. 34 TRM Table 3.3.7.1-1 (page 1 of 1) Control Room Emergency Ventilation System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
NOMINAL TRIP SETPOINT | NOMINAL TRIP SETPOINT | ||
: 1. Control Building Air Intake Radiation-High | : 1. Control Building Air Intake Radiation-High | ||
1-D22-RM-K600-1-2, 1-D22-RE-N001-1-2 1-D22-RM-K600-1-3, 1-D22-RE-N001-1-3 | 1-D22-RM-K600-1-2, 1-D22-RE-N001-1-2 1-D22-RM-K600-1-3, 1-D22-RE-N001-1-3 | ||
7 mR/hr 2. Unit 2 Secondary Containment Isolation - CREV Auto-Start | 7 mR/hr 2. Unit 2 Secondary Containment Isolation - CREV Auto-Start | ||
: a. Reactor Vessel Water Level-Low Level 2 | : a. Reactor Vessel Water Level-Low Level 2 | ||
: b. Drywell Pressure-High | : b. Drywell Pressure-High | ||
Line 6,186: | Line 6,186: | ||
Brunswick Unit 2 B-25 Revision No. 23 TRM Table 3.3.7.2-1 (page 1 of 1) Condenser Vacuum Pump Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-25 Revision No. 23 TRM Table 3.3.7.2-1 (page 1 of 1) Condenser Vacuum Pump Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
NOMINAL TRIP SETPOINT | NOMINAL TRIP SETPOINT | ||
: 1. Main Steam Line Radiation-High | : 1. Main Steam Line Radiation-High | ||
Line 6,197: | Line 6,197: | ||
Brunswick Unit 2 B-26 Revision No. 63 TRM Table 3.3.8.1-1 (page 1 of 1) Loss of Power Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-26 Revision No. 63 TRM Table 3.3.8.1-1 (page 1 of 1) Loss of Power Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
NOMINAL TRIP SETPOINT | NOMINAL TRIP SETPOINT | ||
: 1. 4.16 kV Emergency Bus Undervoltage (Loss of Voltage) | : 1. 4.16 kV Emergency Bus Undervoltage (Loss of Voltage) | ||
: a. Bus Undervoltage | : a. Bus Undervoltage | ||
Line 6,207: | Line 6,207: | ||
Relay Type - IAV53K Device Number - 27/59E | Relay Type - IAV53K Device Number - 27/59E | ||
1.15 seconds (e) 2. 4.16 kV Emergency Bus Undervoltage (Degraded Voltage) | 1.15 seconds (e) 2. 4.16 kV Emergency Bus Undervoltage (Degraded Voltage) | ||
: a. Bus Undervoltage | : a. Bus Undervoltage | ||
Line 6,218: | Line 6,218: | ||
10 seconds | 10 seconds | ||
(a) Based on 4.16 kV bus voltage. | |||
(b) Based on 120 V bus voltage. | (b) Based on 120 V bus voltage. | ||
Line 6,230: | Line 6,230: | ||
Brunswick Unit 2 B-27 Revision No. 64 TRM Table 3.3.8.2-1 (page 1 of 1) Reactor Protection System (RPS) Electric Power Monitoring TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-27 Revision No. 64 TRM Table 3.3.8.2-1 (page 1 of 1) Reactor Protection System (RPS) Electric Power Monitoring TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
NOMINAL TRIP SETPOINT | NOMINAL TRIP SETPOINT | ||
: 1. RPS Motor Generator Set Electric Power Monitoring Assembly a. Overvoltage | : 1. RPS Motor Generator Set Electric Power Monitoring Assembly a. Overvoltage | ||
Line 6,237: | Line 6,237: | ||
125 V b. Undervoltage | 125 V b. Undervoltage | ||
2-C72-EPA1, 2, 3, 4 109 V | 2-C72-EPA1, 2, 3, 4 109 V | ||
: c. Underfrequency | : c. Underfrequency | ||
2-C72-EPA1, 2, 3, 4 57.7 Hz | 2-C72-EPA1, 2, 3, 4 57.7 Hz | ||
: 2. RPS Alternate Power Supply Electric Power Monitoring Assembly | : 2. RPS Alternate Power Supply Electric Power Monitoring Assembly | ||
: a. Overvoltage | : a. Overvoltage | ||
Line 6,248: | Line 6,248: | ||
125 V b. Undervoltage | 125 V b. Undervoltage | ||
2-C72-EPA5, 6 109 V | 2-C72-EPA5, 6 109 V | ||
: c. Underfrequency | : c. Underfrequency | ||
Line 6,255: | Line 6,255: | ||
TRM TS Instrument List Appendix B | TRM TS Instrument List Appendix B | ||
Brunswick Unit 2 B-28 Revision No. 23 TRM Table 3.4.4-1 (page 1 of 1) Reactor Coolant System Operational LEAKAGE TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-28 Revision No. 23 TRM Table 3.4.4-1 (page 1 of 1) Reactor Coolant System Operational LEAKAGE TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
: 1. Drywell Floor Drain Sump Flow Monitor | : 1. Drywell Floor Drain Sump Flow Monitor | ||
G16-FQ-K601, G16-FYQ-K601, G16-FT-N003 | G16-FQ-K601, G16-FYQ-K601, G16-FT-N003 | ||
: 2. Drywell Equipment Drain Sump Flow Monitor | : 2. Drywell Equipment Drain Sump Flow Monitor | ||
Line 6,265: | Line 6,265: | ||
TRM TS Instrument List Appendix B | TRM TS Instrument List Appendix B | ||
Brunswick Unit 2 B-29 Revision No. 23 TRM Table 3.4.5-1 (page 1 of 1) Reactor Coolant System Leakage Detection Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 B-29 Revision No. 23 TRM Table 3.4.5-1 (page 1 of 1) Reactor Coolant System Leakage Detection Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
: 1. Drywell Floor Drain Sump Flow Monitor | : 1. Drywell Floor Drain Sump Flow Monitor | ||
G16-FQ-K601, G16-FYQ-K601, G16-FT-N003 | G16-FQ-K601, G16-FYQ-K601, G16-FT-N003 | ||
: 2. Primary Containment Atmosphere Particulate Monitor | : 2. Primary Containment Atmosphere Particulate Monitor | ||
CAC-AQH-1260-1 CAC-AQH-1262-1 | CAC-AQH-1260-1 CAC-AQH-1262-1 | ||
: 3. Atmosphere Gaseous Radioactivity Monitor CAC-AQH-1260-3 CAC-AQH-1262-3 | : 3. Atmosphere Gaseous Radioactivity Monitor CAC-AQH-1260-3 CAC-AQH-1262-3 | ||
Line 6,309: | Line 6,309: | ||
Brunswick Unit 2 C-2 Revision No. 44 TRM Table 3.3-2 (page 1 of 1) Control Rod Block Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 C-2 Revision No. 44 TRM Table 3.3-2 (page 1 of 1) Control Rod Block Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
TRIP SETPOINT | TRIP SETPOINT | ||
: 1. Average Power Range Monitors | : 1. Average Power Range Monitors | ||
: a. Simulated Thermal Power - High | : a. Simulated Thermal Power - High | ||
C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11 | C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11 | ||
0.55W + 53.5% RTP (a) and 108.0% RTP | 0.55W + 53.5% RTP (a) and 108.0% RTP | ||
: b. Inoperative | : b. Inoperative | ||
C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11 | C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11 | ||
NA | NA | ||
: c. Downscale | : c. Downscale | ||
C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11 | C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11 | ||
2.4% RTP | 2.4% RTP | ||
: d. Simulated Thermal Power - High (Setdown) | : d. Simulated Thermal Power - High (Setdown) | ||
C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11 | C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11 | ||
12.0% RTP | 12.0% RTP | ||
: 2. Source Range Monitors | : 2. Source Range Monitors | ||
: a. Detector Not Full In | : a. Detector Not Full In | ||
C51-SRM-A, B, C, D | C51-SRM-A, B, C, D | ||
NA | NA | ||
: b. Upscale | : b. Upscale | ||
Line 6,345: | Line 6,345: | ||
C51-SRM-A, B, C, D | C51-SRM-A, B, C, D | ||
NA | NA | ||
: d. Downscale | : d. Downscale | ||
C51-SRM-A, B, C, D | C51-SRM-A, B, C, D | ||
3 cps | 3 cps | ||
: 3. Intermediate Range Monitors | : 3. Intermediate Range Monitors | ||
: a. Detector Not Full In | : a. Detector Not Full In | ||
C51-IRM-A, B, C, D C51-IRM-E, F, G, H | C51-IRM-A, B, C, D C51-IRM-E, F, G, H | ||
NA | NA | ||
: b. Upscale | : b. Upscale | ||
C51-IRM-A, B, C, D C51-IRM-E, F, G, H | C51-IRM-A, B, C, D C51-IRM-E, F, G, H | ||
108/125 of full scale | 108/125 of full scale | ||
: c. Inoperative | : c. Inoperative | ||
C51-IRM-A, B, C, D C51-IRM-E, F, G, H | C51-IRM-A, B, C, D C51-IRM-E, F, G, H | ||
NA | NA | ||
: d. Downscale | : d. Downscale | ||
C51-IRM-A, B, C, D C51-IRM-E, F, G, H | C51-IRM-A, B, C, D C51-IRM-E, F, G, H | ||
3/125 of full scale | 3/125 of full scale | ||
: 4. Scram Discharge Volume Water Level-High | : 4. Scram Discharge Volume Water Level-High | ||
Line 6,383: | Line 6,383: | ||
Brunswick Unit 2 C-3 Revision No. 61 TRM Table 3.4-2 (page 1 of 1) | Brunswick Unit 2 C-3 Revision No. 61 TRM Table 3.4-2 (page 1 of 1) | ||
Accident Monitoring Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Accident Monitoring Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
: 1. Suppression Chamber Atmosphere Temperature(b) | : 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 | 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) | : 2. Drywell Radiation (c) | ||
CAC-AR-1260 | CAC-AR-1260 | ||
Line 6,394: | Line 6,394: | ||
CAC-AR-1262 | CAC-AR-1262 | ||
CAC-AQH-1262-1, 2, 3 | CAC-AQH-1262-1, 2, 3 | ||
: 3. Safety/Relief Valve Position Indication | : 3. Safety/Relief Valve Position Indication | ||
: a. Primary-Sonic | : a. Primary-Sonic | ||
: b. Secondary-Temperature | : b. Secondary-Temperature | ||
B21-FY-4157 Thru 4167 | B21-FY-4157 Thru 4167 | ||
B21-TR-R614 Points 1 Thru 11 | B21-TR-R614 Points 1 Thru 11 | ||
: 4. Turbine Building Ventilation Monitor(d) | : 4. Turbine Building Ventilation Monitor(d) | ||
D12-RE-4563, D12-RR-4548-3 | D12-RE-4563, D12-RR-4548-3 | ||
Line 6,418: | Line 6,418: | ||
Brunswick Unit 2 C-4 Revision No. 28 TRM Table 3.5-2 (page 1 of 1) Chloride Intrusion Monitors TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 C-4 Revision No. 28 TRM Table 3.5-2 (page 1 of 1) Chloride Intrusion Monitors TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
TRIP SETPOINT | TRIP SETPOINT | ||
: 1. Chloride Leak Detectors in the Condenser Hotwell Outlet Headers | : 1. Chloride Leak Detectors in the Condenser Hotwell Outlet Headers | ||
CO-CR-24 CO-CIT-24A, CO-CIT-24B CO-CE-24-1, CO-CE-24-2, CO-CE-24-3, CO-CE-24-4 | CO-CR-24 CO-CIT-24A, CO-CIT-24B CO-CE-24-1, CO-CE-24-2, CO-CE-24-3, CO-CE-24-4 | ||
1.0 mhos/cm 2. Chloride Leak Detector in the Condensate Pump Discharge | 1.0 mhos/cm 2. Chloride Leak Detector in the Condensate Pump Discharge | ||
: a. Wide Range Monitor | : a. Wide Range Monitor | ||
: b. Narrow Range Monitor | : b. Narrow Range Monitor | ||
Line 6,441: | Line 6,441: | ||
0.3 mhos/cm TRM TRM Instrument List Appendix C | 0.3 mhos/cm TRM TRM Instrument List Appendix C | ||
Brunswick Unit 2 C-5 Revision No. 23 TRM Table 3.6-2 (page 1 of 1) Bus Power Monitors TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 C-5 Revision No. 23 TRM Table 3.6-2 (page 1 of 1) Bus Power Monitors TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
: 1. Core Spray System Bus Power Monitor | : 1. Core Spray System Bus Power Monitor | ||
E21-K1A, E21-K1B | E21-K1A, E21-K1B | ||
: 2. Low Pressure Coolant Injection (Residual Heat Removal System) Bus Power Monitor | : 2. Low Pressure Coolant Injection (Residual Heat Removal System) Bus Power Monitor | ||
E11-K106A, E11-K106B | E11-K106A, E11-K106B | ||
: 3. High Pressure Coolant Injection System Bus Power Monitor | : 3. High Pressure Coolant Injection System Bus Power Monitor | ||
E41-K55, E41-K56 | E41-K55, E41-K56 | ||
: 4. Automatic Depressurization System Bus Power Monitor | : 4. Automatic Depressurization System Bus Power Monitor | ||
B21-K1A, B21-K1B | B21-K1A, B21-K1B | ||
: 5. RCIC System Bus Power Monitor | : 5. RCIC System Bus Power Monitor | ||
Line 6,460: | Line 6,460: | ||
TRM TRM Instrument List Appendix C | TRM TRM Instrument List Appendix C | ||
Brunswick Unit 2 C-6 Revision No. 23 TRM Table 3.7-1 (page 1 of 1) Automatic Depressurization System (ADS) Inhibit Switch TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 C-6 Revision No. 23 TRM Table 3.7-1 (page 1 of 1) Automatic Depressurization System (ADS) Inhibit Switch TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
: 1. ADS Inhibit Switch A | : 1. ADS Inhibit Switch A | ||
B21-CS-S5A | B21-CS-S5A | ||
: 2. ADS Inhibit Switch B | : 2. ADS Inhibit Switch B | ||
Line 6,471: | Line 6,471: | ||
Brunswick Unit 2 C-7 Revision No. 23 TRM Table 3.8-1 (page 1 of 1) Suppression Chamber Water Temperature Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 C-7 Revision No. 23 TRM Table 3.8-1 (page 1 of 1) Suppression Chamber Water Temperature Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
TRIP SETPOINT | TRIP SETPOINT | ||
: 1. Suppression Chamber Water Temperature | : 1. Suppression Chamber Water Temperature | ||
Line 6,480: | Line 6,480: | ||
TRM TRM Instrument List Appendix C | TRM TRM Instrument List Appendix C | ||
Brunswick Unit 2 C-8 Revision No. 47 TRM Table 3.9-2 (page 1 of 1) Seismic Monitoring Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 C-8 Revision No. 47 TRM Table 3.9-2 (page 1 of 1) Seismic Monitoring Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
: 1. Passive Triaxial Peak Shock Recorders | : 1. Passive Triaxial Peak Shock Recorders | ||
: a. Reactor Building Basement/Equipment Drain Tank (-17' level) | : 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-823-1 b. Reactor Building RHR Heat Exchanger Support (+20' level) | ||
: c. Reactor Building Refueling Area (+117' level) | : c. Reactor Building Refueling Area (+117' level) | ||
2-ENV-XRH-823-2 | 2-ENV-XRH-823-2 | ||
2-ENV-XRH-823-3 2. Active Triaxial Accelerometers | 2-ENV-XRH-823-3 2. Active Triaxial Accelerometers | ||
: a. Reactor Building (+89' 4" level) | : a. Reactor Building (+89' 4" level) | ||
: b. Reactor Building (-17' level) | : b. Reactor Building (-17' level) | ||
2-ENV-XT-823-2 | 2-ENV-XT-823-2 | ||
2-ENV-XT-823-1 | 2-ENV-XT-823-1 | ||
: 3. Active Seismic Recording System | : 3. Active Seismic Recording System | ||
: a. Control Room | : a. Control Room | ||
Line 6,503: | Line 6,503: | ||
TRM TRM Instrument List Appendix C | TRM TRM Instrument List Appendix C | ||
Brunswick Unit 2 C-9 Revision No. 52 TRM Table 3.10-1 (page 1 of 1) Intake Canal High Water Level Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 C-9 Revision No. 52 TRM Table 3.10-1 (page 1 of 1) Intake Canal High Water Level Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
: 1. Intake Canal High Water Level(a) 2-SCW-LT-285 2-SCW-LI-285 2-SCW-LR-285 2-SCW-LRA-285-1 | : 1. Intake Canal High Water Level(a) 2-SCW-LT-285 2-SCW-LI-285 2-SCW-LR-285 2-SCW-LRA-285-1 | ||
Line 6,511: | Line 6,511: | ||
Brunswick Unit 2 C-10 Revision No. 51 TRM Table 3.11-2 (page 1 of 1) Primary Containment Isolation Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Brunswick Unit 2 C-10 Revision No. 51 TRM Table 3.11-2 (page 1 of 1) Primary Containment Isolation Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
TRIP SETPOINT | TRIP SETPOINT | ||
: 1. Main Steam Line Tunnel Temperature-High | : 1. Main Steam Line Tunnel Temperature-High | ||
Line 6,524: | Line 6,524: | ||
Brunswick Unit 2 C-11 Revision No. 57 TRM Table 3.12-2 (page 1 of 1) | Brunswick Unit 2 C-11 Revision No. 57 TRM Table 3.12-2 (page 1 of 1) | ||
Control Room Emergency Ventila tion System Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | Control Room Emergency Ventila tion System Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S) | ||
TRIP SETPOINT | TRIP SETPOINT | ||
: 1. Chlorine Isolation | : 1. Chlorine Isolation | ||
: a. Control Building Air Intake (Local) | : a. Control Building Air Intake (Local) | ||
Line 6,536: | Line 6,536: | ||
2-X-AT-2977-1 | 2-X-AT-2977-1 | ||
5 ppm | 5 ppm | ||
: b. Chlorine Tank Car Area (Remote) | : b. Chlorine Tank Car Area (Remote) | ||
Line 6,547: | Line 6,547: | ||
2-X-AT-2979-1 | 2-X-AT-2979-1 | ||
5 ppm | 5 ppm | ||
: 2. Control Room Envelope Smoke Protection | : 2. Control Room Envelope Smoke Protection | ||
: a. Control Building Intake Air Duct Smoke Detectors | : a. Control Building Intake Air Duct Smoke Detectors | ||
Line 6,645: | Line 6,645: | ||
Brunswick Unit 2 D-13 Revision No. 23 TRM Table 3.6.1.3-2 (Page 1 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S) | Brunswick Unit 2 D-13 Revision No. 23 TRM Table 3.6.1.3-2 (Page 1 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S) | ||
SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds) | SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds) | ||
AUTOMATIC ISOLATION GROUP 2-B21-F016 MAIN STEAM LINE DRAIN INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 1 2-B21-F019 MAIN STEAM LINE DRAIN OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 1 2-B21-F022A INBOARD MSIV A A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F022B INBOARD MSIV B A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F022C INBOARD MSIV C A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F022D INBOARD MSIV D A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F028A OUTBOARD MSIV A A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F028B OUTBOARD MSIV B A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F028C OUTBOARD MSIV C A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F028D OUTBOARD MSIV D A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F032A FEEDWATER SUPPLY LINE A ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-B21-F032B FEEDWATER SUPPLY LINE B ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-B32-F019 SAMPLE LINE INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 5 1 2-B32-F020 SAMPLE LINE OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 5 1 2-B32-V22 RECIRC PUMP 2A SEAL INJECTION A, B SR 3.6.1.3.4 (a) NA 2-B32-V30 RECIRC PUMP 2B SEAL INJECTION A, B SR 3.6.1.3.4 (a) NA 2-CAC-SV-1200B CAC-AT-1261 INBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (continued) | AUTOMATIC ISOLATION GROUP 2-B21-F016 MAIN STEAM LINE DRAIN INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 1 2-B21-F019 MAIN STEAM LINE DRAIN OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 1 2-B21-F022A INBOARD MSIV A A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F022B INBOARD MSIV B A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F022C INBOARD MSIV C A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F022D INBOARD MSIV D A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F028A OUTBOARD MSIV A A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F028B OUTBOARD MSIV B A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F028C OUTBOARD MSIV C A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F028D OUTBOARD MSIV D A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F032A FEEDWATER SUPPLY LINE A ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-B21-F032B FEEDWATER SUPPLY LINE B ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-B32-F019 SAMPLE LINE INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 5 1 2-B32-F020 SAMPLE LINE OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 5 1 2-B32-V22 RECIRC PUMP 2A SEAL INJECTION A, B SR 3.6.1.3.4 (a) NA 2-B32-V30 RECIRC PUMP 2B SEAL INJECTION A, B SR 3.6.1.3.4 (a) NA 2-CAC-SV-1200B CAC-AT-1261 INBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (continued) | ||
(a) Allowable Isolation Time specified in the Inservice Testing Program. | |||
TRM PCIV List Appendix D | TRM PCIV List Appendix D | ||
Line 6,654: | Line 6,654: | ||
AUTOMATIC ISOLATION GROUP 2-CAC-SV-1205E CAC-AT-4409 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1209A CAC-AT-4409 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1209B CAC-AT-4409 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1211E CAC-AT-1262 INBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1211F CAC-AT-1262 INBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1213A CAC-AT-4409 TORUS INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1215E CAC-AT-4409 INBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1218A CAC-AT-4410 TORUS INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1225B COMMON INBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1227A CAC-AT-4410 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1227B CAC-AT-4410 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1227C CAC-AT-1260 INBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1227E CAC-AT-4410 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 | AUTOMATIC ISOLATION GROUP 2-CAC-SV-1205E CAC-AT-4409 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1209A CAC-AT-4409 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1209B CAC-AT-4409 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1211E CAC-AT-1262 INBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1211F CAC-AT-1262 INBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1213A CAC-AT-4409 TORUS INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1215E CAC-AT-4409 INBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1218A CAC-AT-4410 TORUS INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1225B COMMON INBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1227A CAC-AT-4410 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1227B CAC-AT-4410 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1227C CAC-AT-1260 INBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1227E CAC-AT-4410 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 | ||
15 6 (b) (continued) | 15 6 (b) (continued) | ||
(a) Allowable Isolation Time specified in the Inservice Testing Program. | |||
(b) The PCIV receives a Group 6 isolation signal for instrument protection. The PCIV is considered OPERABLE if it is capable of closing from the control room within the specified Allowable Isolation Time. | (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. | ||
Line 6,663: | Line 6,663: | ||
Brunswick Unit 2 D-15 Revision No. 49 TRM Table 3.6.1.3-2 (Page 3 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S) | Brunswick Unit 2 D-15 Revision No. 49 TRM Table 3.6.1.3-2 (Page 3 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S) | ||
SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds) | SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds) | ||
AUTOMATIC ISOLATION GROUP 2-CAC-SV-1231B CAC-AT-4410 INBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1260 CAC-AT-1260 OUTBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1261 CAC-AT-1261 OUTBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1262 CAC-AT-1262 OUTBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-3439 CAC-AT-1262 OUTBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-3440 COMMON OUTBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-4409-1 CAC-AT-4409 TORUS OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4409-2 CAC-AT-4409 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4409-3 CAC-AT-4409 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4409-4 CAC-AT-4409 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4410-1 CAC-AT-4410 TORUS OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4410-2 CAC-AT-4410 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4410-3 CAC-AT-4410 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4410-4 CAC-AT-4410 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4540 CAC-AT-4409 OUTBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4541 CAC-AT-4410 OUTBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) (continued) | AUTOMATIC ISOLATION GROUP 2-CAC-SV-1231B CAC-AT-4410 INBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1260 CAC-AT-1260 OUTBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1261 CAC-AT-1261 OUTBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1262 CAC-AT-1262 OUTBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-3439 CAC-AT-1262 OUTBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-3440 COMMON OUTBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-4409-1 CAC-AT-4409 TORUS OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4409-2 CAC-AT-4409 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4409-3 CAC-AT-4409 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4409-4 CAC-AT-4409 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4410-1 CAC-AT-4410 TORUS OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4410-2 CAC-AT-4410 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4410-3 CAC-AT-4410 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4410-4 CAC-AT-4410 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4540 CAC-AT-4409 OUTBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4541 CAC-AT-4410 OUTBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) (continued) | ||
(a) Allowable Isolation Time specified in the Inservice Testing Program. | |||
(b) The PCIV receives a Group 6 isolation signal for instrument protection. The PCIV is considered OPERABLE if it is capable of closing from the control room within the specified Allowable Isolation Time. | (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. | ||
Line 6,680: | Line 6,680: | ||
Brunswick Unit 2 D-17 Revision No. 59 TRM Table 3.6.1.3-2 (Page 5 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S) | Brunswick Unit 2 D-17 Revision No. 59 TRM Table 3.6.1.3-2 (Page 5 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S) | ||
SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds) | SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds) | ||
AUTOMATIC ISOLATION GROUP 2-C51-J004A A TIP BALL VALVE AND SHEAR VALVE ASSEMBLY A, B SR 3.6.1.3.3 SR 3.6.1.3.4 SR 3.6.1.3.6 SR 3.6.1.3.8 (a) 2 2-C51-J004B B TIP BALL VALVE AND SHEAR VALVE ASSEMBLY A, B SR 3.6.1.3.3 SR 3.6.1.3.4 SR 3.6.1.3.6 SR 3.6.1.3.8 (a) 2 2-C51-J004C C TIP BALL VALVE AND SHEAR VALVE ASSEMBLY A, B SR 3.6.1.3.3 SR 3.6.1.3.4 SR 3.6.1.3.6 SR 3.6.1.3.8 (a) 2 2-C51-J004D D TIP BALL VALVE AND SHEAR VALVE ASSEMBLY A, B SR 3.6.1.3.3 SR 3.6.1.3.4 SR 3.6.1.3.6 SR 3.6.1.3.8 (a) 2 2-E11-F007A MINIMUM FLOW BYPASS VALVE A TO SUPPRESSION POOL C SR 3.6.1.3.4 (a) NA 2-E11-F007B MINIMUM FLOW BYPASS VALVE B TO SUPPRESSION POOL C SR 3.6.1.3.4 (a) NA 2-E11-F008 SHUTDOWN COOLING OUTBOARD SUCTION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 43 8(c) 2-E11-F009 SHUTDOWN COOLING INBOARD SUCTION THROTTLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 8(c) 2-E11-F011A RHR HEAT EXCHANGER 2A DRAIN TO SUPPRESSION POOL C SR 3.6.1.3.4 (a) NA 2-E11-F011B RHR HEAT EXCHANGER 2B DRAIN TO SUPPRESSION POOL C SR 3.6.1.3.4 (a) NA 2-E11-F015A LPCI A INBOARD INJECTION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 8(c) 2-E11-F015B LPCI B INBOARD INJECTION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 8(c) 2-E11-F016A DRYWELL SPRAY A OUTBOARD ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F016B DRYWELL SPRAY B OUTBOARD ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F017A LPCI A OUTBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E11-F017B LPCI B OUTBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E11-F020A RHR PUMP 2A AND 2C TORUS SUCTION C SR 3.6.1.3.4 (a) NA (continued) | AUTOMATIC ISOLATION GROUP 2-C51-J004A A TIP BALL VALVE AND SHEAR VALVE ASSEMBLY A, B SR 3.6.1.3.3 SR 3.6.1.3.4 SR 3.6.1.3.6 SR 3.6.1.3.8 (a) 2 2-C51-J004B B TIP BALL VALVE AND SHEAR VALVE ASSEMBLY A, B SR 3.6.1.3.3 SR 3.6.1.3.4 SR 3.6.1.3.6 SR 3.6.1.3.8 (a) 2 2-C51-J004C C TIP BALL VALVE AND SHEAR VALVE ASSEMBLY A, B SR 3.6.1.3.3 SR 3.6.1.3.4 SR 3.6.1.3.6 SR 3.6.1.3.8 (a) 2 2-C51-J004D D TIP BALL VALVE AND SHEAR VALVE ASSEMBLY A, B SR 3.6.1.3.3 SR 3.6.1.3.4 SR 3.6.1.3.6 SR 3.6.1.3.8 (a) 2 2-E11-F007A MINIMUM FLOW BYPASS VALVE A TO SUPPRESSION POOL C SR 3.6.1.3.4 (a) NA 2-E11-F007B MINIMUM FLOW BYPASS VALVE B TO SUPPRESSION POOL C SR 3.6.1.3.4 (a) NA 2-E11-F008 SHUTDOWN COOLING OUTBOARD SUCTION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 43 8(c) 2-E11-F009 SHUTDOWN COOLING INBOARD SUCTION THROTTLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 8(c) 2-E11-F011A RHR HEAT EXCHANGER 2A DRAIN TO SUPPRESSION POOL C SR 3.6.1.3.4 (a) NA 2-E11-F011B RHR HEAT EXCHANGER 2B DRAIN TO SUPPRESSION POOL C SR 3.6.1.3.4 (a) NA 2-E11-F015A LPCI A INBOARD INJECTION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 8(c) 2-E11-F015B LPCI B INBOARD INJECTION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 8(c) 2-E11-F016A DRYWELL SPRAY A OUTBOARD ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F016B DRYWELL SPRAY B OUTBOARD ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F017A LPCI A OUTBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E11-F017B LPCI B OUTBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E11-F020A RHR PUMP 2A AND 2C TORUS SUCTION C SR 3.6.1.3.4 (a) NA (continued) | ||
(a) Allowable Isolation Time specified in the Inservice Testing Program. | |||
(c) Except as noted in TS Table 3.3.6.1-1 (Note (d)), these PCIVs are also required to be OPERABLE in MODES 4 and 5 to support the OPERABILITY of Function 6.b of TS Table 3.3.6.1-1. | (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. | ||
Line 6,689: | Line 6,689: | ||
Brunswick Unit 2 D-18 Revision No. 23 TRM Table 3.6.1.3-2 (Page 6 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S) | Brunswick Unit 2 D-18 Revision No. 23 TRM Table 3.6.1.3-2 (Page 6 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S) | ||
SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds) | SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds) | ||
AUTOMATIC ISOLATION GROUP 2-E11-F020B RHR PUMP 2B AND 2D TORUS SUCTION C SR 3.6.1.3.4 (a) NA 2-E11-F021A DRYWELL SPRAY A INBOARD ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F021B DRYWELL SPRAY B INBOARD ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F024A SUPPRESSION POOL COOLING A ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F024B SUPPRESSION POOL COOLING B ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F027A SUPPRESSION POOL SPRAY A ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F027B SUPPRESSION POOL SPRAY B ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F028A SUPPRESSION POOL SPRAY A ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F028B SUPPRESSION POOL SPRAY B ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F103A RHR HEAT EXCHANGER 2A OUTBOARD VENT C SR 3.6.1.3.4 (a) NA 2-E11-F103B RHR HEAT EXCHANGER 2B OUTBOARD VENT C SR 3.6.1.3.4 (a) NA (continued) | AUTOMATIC ISOLATION GROUP 2-E11-F020B RHR PUMP 2B AND 2D TORUS SUCTION C SR 3.6.1.3.4 (a) NA 2-E11-F021A DRYWELL SPRAY A INBOARD ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F021B DRYWELL SPRAY B INBOARD ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F024A SUPPRESSION POOL COOLING A ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F024B SUPPRESSION POOL COOLING B ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F027A SUPPRESSION POOL SPRAY A ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F027B SUPPRESSION POOL SPRAY B ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F028A SUPPRESSION POOL SPRAY A ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F028B SUPPRESSION POOL SPRAY B ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F103A RHR HEAT EXCHANGER 2A OUTBOARD VENT C SR 3.6.1.3.4 (a) NA 2-E11-F103B RHR HEAT EXCHANGER 2B OUTBOARD VENT C SR 3.6.1.3.4 (a) NA (continued) | ||
(a) Allowable Isolation Time specified in the Inservice Testing Program. | |||
TRM PCIV List Appendix D | TRM PCIV List Appendix D | ||
Line 6,698: | Line 6,698: | ||
AUTOMATIC ISOLATION GROUP 2-E21-F001A SUPPRESSION POOL A SUCTION C SR 3.6.1.3.4 (a) NA 2-E21-F001B SUPPRESSION POOL B SUCTION C SR 3.6.1.3.4 (a) NA 2-E21-F004A CORE SPRAY PUMP 2A OUTBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E21-F004B CORE SPRAY PUMP 2B OUTBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E21-F005A CORE SPRAY PUMP 2A INBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E21-F005B CORE SPRAY PUMP 2B INBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E21-F015A CORE SPRAY FULL FLOW TEST BYPASS C SR 3.6.1.3.4 (a) NA 2-E21-F015B CORE SPRAY FULL FLOW TEST BYPASS C SR 3.6.1.3.4 (a) NA 2-E21-F031A CORE SPRAY MINIMUM FLOW BYPASS C SR 3.6.1.3.4 (a) NA 2-E21-F031B CORE SPRAY MINIMUM FLOW BYPASS C SR 3.6.1.3.4 (a) NA 2-E41-F002 HPCI STEAM SUPPLY INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 50 4 2-E41-F003 HPCI STEAM SUPPLY OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 50 4 2-E41-F006 HPCI INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E41-F012 HPCI MINIMUM FLOW BYPASS TO SUPPRESSION POOL C SR 3.6.1.3.4 20 NA 2-E41-F042 HPCI SUPPRESSION POOL SUCTION C SR 3.6.1.3.4 SR 3.6.1.3.6 | AUTOMATIC ISOLATION GROUP 2-E21-F001A SUPPRESSION POOL A SUCTION C SR 3.6.1.3.4 (a) NA 2-E21-F001B SUPPRESSION POOL B SUCTION C SR 3.6.1.3.4 (a) NA 2-E21-F004A CORE SPRAY PUMP 2A OUTBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E21-F004B CORE SPRAY PUMP 2B OUTBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E21-F005A CORE SPRAY PUMP 2A INBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E21-F005B CORE SPRAY PUMP 2B INBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E21-F015A CORE SPRAY FULL FLOW TEST BYPASS C SR 3.6.1.3.4 (a) NA 2-E21-F015B CORE SPRAY FULL FLOW TEST BYPASS C SR 3.6.1.3.4 (a) NA 2-E21-F031A CORE SPRAY MINIMUM FLOW BYPASS C SR 3.6.1.3.4 (a) NA 2-E21-F031B CORE SPRAY MINIMUM FLOW BYPASS C SR 3.6.1.3.4 (a) NA 2-E41-F002 HPCI STEAM SUPPLY INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 50 4 2-E41-F003 HPCI STEAM SUPPLY OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 50 4 2-E41-F006 HPCI INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E41-F012 HPCI MINIMUM FLOW BYPASS TO SUPPRESSION POOL C SR 3.6.1.3.4 20 NA 2-E41-F042 HPCI SUPPRESSION POOL SUCTION C SR 3.6.1.3.4 SR 3.6.1.3.6 | ||
80 4 (continued) | 80 4 (continued) | ||
(a) Allowable Isolation Time specified in the Inservice Testing Program. | |||
TRM PCIV List Appendix D | TRM PCIV List Appendix D | ||
Line 6,705: | Line 6,705: | ||
Brunswick Unit 2 D-20 Revision No. 23 TRM Table 3.6.1.3-2 (Page 8 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S) | Brunswick Unit 2 D-20 Revision No. 23 TRM Table 3.6.1.3-2 (Page 8 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S) | ||
SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds) | SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds) | ||
AUTOMATIC ISOLATION GROUP 2-E41-F075 HPCI TURBINE EXHAUST VACUUM BREAKER A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 7 2-E41-F079 HPCI TURBINE EXHAUST VACUUM BREAKER A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 7 2-E51-F007 RCIC STEAM SUPPLY INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 5 2-E51-F008 RCIC STEAM SUPPLY OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 5 2-E51-F013 RCIC INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E51-F019 RCIC MINIMUM FLOW BYPASS TO SUPPRESSION POOL C SR 3.6.1.3.4 (a) NA 2-E51-F031 RCIC SUPPRESSION POOL SUCTION C SR 3.6.1.3.4 SR 3.6.1.3.6 80 5 2-E51-F062 RCIC TURBINE EXHAUST VACUUM BREAKER A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 9 2-E51-F066 RCIC TURBINE EXHAUST VACUUM BREAKER A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 9 2-G16-F003 DRYWELL FLOOR DRAIN INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 20 2 2-G16-F004 DRYWELL FLOOR DRAIN OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 20 2 2-G16-F019 DRYWELL EQUIPMENT DRAIN INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 20 2 2-G16-F020 DRYWELL EQUIPMENT DRAIN OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 20 2 2-G31-F001 RWCU INLET INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 35 3 (e) 2-G31-F004 RWCU INLET OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 35 3 2-G31-F042 RWCU RETURN TO REACTOR A, B SR 3.6.1.3.4 (a) NA 2-RCC-SV-1222B RECIRC PUMP 2A COOLER OUTLET SAMPLE C SR 3.6.1.3.4 (a) NA (continued) | AUTOMATIC ISOLATION GROUP 2-E41-F075 HPCI TURBINE EXHAUST VACUUM BREAKER A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 7 2-E41-F079 HPCI TURBINE EXHAUST VACUUM BREAKER A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 7 2-E51-F007 RCIC STEAM SUPPLY INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 5 2-E51-F008 RCIC STEAM SUPPLY OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 5 2-E51-F013 RCIC INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E51-F019 RCIC MINIMUM FLOW BYPASS TO SUPPRESSION POOL C SR 3.6.1.3.4 (a) NA 2-E51-F031 RCIC SUPPRESSION POOL SUCTION C SR 3.6.1.3.4 SR 3.6.1.3.6 80 5 2-E51-F062 RCIC TURBINE EXHAUST VACUUM BREAKER A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 9 2-E51-F066 RCIC TURBINE EXHAUST VACUUM BREAKER A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 9 2-G16-F003 DRYWELL FLOOR DRAIN INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 20 2 2-G16-F004 DRYWELL FLOOR DRAIN OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 20 2 2-G16-F019 DRYWELL EQUIPMENT DRAIN INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 20 2 2-G16-F020 DRYWELL EQUIPMENT DRAIN OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 20 2 2-G31-F001 RWCU INLET INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 35 3 (e) 2-G31-F004 RWCU INLET OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 35 3 2-G31-F042 RWCU RETURN TO REACTOR A, B SR 3.6.1.3.4 (a) NA 2-RCC-SV-1222B RECIRC PUMP 2A COOLER OUTLET SAMPLE C SR 3.6.1.3.4 (a) NA (continued) | ||
(a) Allowable Isolation Time specified in the Inservice Testing Program. | |||
(e) Valve does not automatically close on an isolation signal associated with Function 5.f of TS Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation." | (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." | ||
Line 6,734: | Line 6,734: | ||
TRM SCID List Appendix E | TRM SCID List Appendix E | ||
Brunswick Unit 2 E-2 Revision No. 23 TRM Table 3.6.4.2-1 (Page 1 of 1) Secondary Containment Automatic Isolation Dampers DAMPER NUMBER DAMPER DESCRIPTION SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds) 2-VA-2A-BFIV-RB Reactor Building Ventilation Supply Inboard Isolation SR 3.6.4.2.1 SR 3.6.4.2.2 4 2-VA-2B-BFIV-RB Reactor Building Ventilation Supply Outboard Isolation SR 3.6.4.2.1 SR 3.6.4.2.2 4 2-VA-2C-BFIV-RB Reactor Building Ventilation Exhaust Inboard Isolation SR 3.6.4.2.1 SR 3.6.4.2.2 4 2-VA-2D-BFIV-RB Reactor Building Ventilation Exhaust Outboard Isolation SR 3.6.4.2.1 SR 3.6.4.2.2 4 2-VA-2A-BFV-RB Purge System Exhaust Outlet Valve SR 3.6.4.2.1 SR 3.6.4.2.2 (a) 2-VA-2I-BFV-RB Purge System Inlet Valve SR 3.6.4.2.1 SR 3.6.4.2.2 (a) | Brunswick Unit 2 E-2 Revision No. 23 TRM Table 3.6.4.2-1 (Page 1 of 1) Secondary Containment Automatic Isolation Dampers DAMPER NUMBER DAMPER DESCRIPTION SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds) 2-VA-2A-BFIV-RB Reactor Building Ventilation Supply Inboard Isolation SR 3.6.4.2.1 SR 3.6.4.2.2 4 2-VA-2B-BFIV-RB Reactor Building Ventilation Supply Outboard Isolation SR 3.6.4.2.1 SR 3.6.4.2.2 4 2-VA-2C-BFIV-RB Reactor Building Ventilation Exhaust Inboard Isolation SR 3.6.4.2.1 SR 3.6.4.2.2 4 2-VA-2D-BFIV-RB Reactor Building Ventilation Exhaust Outboard Isolation SR 3.6.4.2.1 SR 3.6.4.2.2 4 2-VA-2A-BFV-RB Purge System Exhaust Outlet Valve SR 3.6.4.2.1 SR 3.6.4.2.2 (a) 2-VA-2I-BFV-RB Purge System Inlet Valve SR 3.6.4.2.1 SR 3.6.4.2.2 (a) | ||
(a) Allowable Isolation Time specified in the Inservice Testing Program. | |||
Brunswick Unit 2 Revision No. 23 APPENDIX F SAFETY FUNCTION DETERMINATION PROGRAM (SFDP) | Brunswick Unit 2 Revision No. 23 APPENDIX F SAFETY FUNCTION DETERMINATION PROGRAM (SFDP) | ||
Line 6,809: | Line 6,809: | ||
Trip Systems for Selected Instruments," may be used as an | Trip Systems for Selected Instruments," may be used as an | ||
aid in the OPERABILITY Determinations. | aid in the OPERABILITY Determinations. | ||
(continued) | |||
TRM SFDP Appendix F Cascading Requirements Brunswick Unit 2 SFDP-3 Revision No. 23 | TRM SFDP Appendix F Cascading Requirements Brunswick Unit 2 SFDP-3 Revision No. 23 | ||
Line 6,852: | Line 6,852: | ||
performing a SFD. Refer to the SFDP Bases for SFD evaluation | performing a SFD. Refer to the SFDP Bases for SFD evaluation | ||
examples. | examples. | ||
(continued) | |||
TRM SFDP Appendix F Cascading Requirements Brunswick Unit 2 SFDP-4 Revision No. 23 | TRM SFDP Appendix F Cascading Requirements Brunswick Unit 2 SFDP-4 Revision No. 23 | ||
Line 6,944: | Line 6,944: | ||
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) | RHR Suppression Pool Cooling 3.8.1 AC Sources - Operating 3.8.7 Distribution Systems - Operating (AC portion only) 3.8.2 AC Sources - Shutdown 3.8.8 Distribution Systems - Shutdown (AC portion only) 3.8.4 DC Sources - Operating 3.8.7 Distribution Systems - Operating (DC portion only) 3.8.5 DC Sources - Shutdown 3.8.8 Distribution Systems - Shutdown (DC portion only) | ||
(continued) | |||
TRM SFDP Appendix F Attachment 1 Brunswick Unit 2 SFDP-10 Revision No. 23 (continued) | TRM SFDP Appendix F Attachment 1 Brunswick Unit 2 SFDP-10 Revision No. 23 (continued) | ||
Line 7,066: | Line 7,066: | ||
AC Sources - Operating | AC Sources - Operating | ||
(continued) | |||
TRM SFDP Appendix F Attachment 1 Brunswick Unit 2 SFDP-12 Revision No. 23 (continued) | TRM SFDP Appendix F Attachment 1 Brunswick Unit 2 SFDP-12 Revision No. 23 (continued) | ||
Line 7,118: | Line 7,118: | ||
RHR - Low Water Level | RHR - Low Water Level | ||
(continued) | |||
TRM SFDP Appendix F Attachment 1 Brunswick Unit 2 SFDP-13 Revision No. 23 (continued) | TRM SFDP Appendix F Attachment 1 Brunswick Unit 2 SFDP-13 Revision No. 23 (continued) | ||
Line 7,171: | Line 7,171: | ||
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. | 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. | 3 See Attachment 3 for specific valves and indication affected. | ||
(continued) | |||
TRM SFDP Appendix F Attachment 2 Brunswick Unit 2 SFDP-15 Revision No. 23 (continued) | TRM SFDP Appendix F Attachment 2 Brunswick Unit 2 SFDP-15 Revision No. 23 (continued) | ||
Line 7,209: | Line 7,209: | ||
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 | 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. | or more required channels. *3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation 1. For Function 1, a loss of initiation capability as a result of a loss of two or more required channels. 2. For Function 2, a loss of one required channel. 3. For Function 3, a loss of both required channels. *3.3.6.1 Primary Containment Isolation Instrumentation For each Function, loss of all required channels in a trip system such that the associated Function cannot be accomplished. | ||
(continued) | |||
TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-20 Revision No. 23 (continued) | TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-20 Revision No. 23 (continued) | ||
Line 7,219: | Line 7,219: | ||
Atmospheric Gaseous Monitoring System. 3.4.7 RHR Shutdown Cooling System-Hot Shutdown Both required SDC subsystems inoperable, Recirc. pumps not in operation, and no alternate method of decay heat removal. 3.4.8 RHR Shutdown Cooling System-Cold Shutdown Both required SDC subsystems inoperable, Recirc. pumps not in operation, and no alternate method of decay heat removal. | Atmospheric Gaseous Monitoring System. 3.4.7 RHR Shutdown Cooling System-Hot Shutdown Both required SDC subsystems inoperable, Recirc. pumps not in operation, and no alternate method of decay heat removal. 3.4.8 RHR Shutdown Cooling System-Cold Shutdown Both required SDC subsystems inoperable, Recirc. pumps not in operation, and no alternate method of decay heat removal. | ||
3.5.1 ECCS-Operating 1. Two or more required ADS valves inoperable. OR | 3.5.1 ECCS-Operating 1. Two or more required ADS valves inoperable. OR | ||
: 2. HPCI and RCIC inoperable. | : 2. HPCI and RCIC inoperable. | ||
OR | OR | ||
: 3. HPCI and two or more required ADS valves 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 | : 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: | : 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. | : 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). | : c. Two LPCI subsystems (except one inoperable LPCI pump in each subsystem). | ||
(continued) | |||
TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-21 Revision No. 23 (continued) | TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-21 Revision No. 23 (continued) | ||
Line 7,233: | Line 7,233: | ||
3.5.2 ECCS-Shutdown Both required low pressure ECCS injection/spray subsystems inoperable. 3.5.3 RCIC System RCIC and HPCI inoperable. 3.6.1.1 Primary Containment 1. Determination that a breach in Primary Containment exists such that leakage exceeds the limit specified in the Primary | 3.5.2 ECCS-Shutdown Both required low pressure ECCS injection/spray subsystems inoperable. 3.5.3 RCIC System RCIC and HPCI inoperable. 3.6.1.1 Primary Containment 1. Determination that a breach in Primary Containment exists such that leakage exceeds the limit specified in the Primary | ||
Containment Leakage Rate Testing Program. OR | Containment Leakage Rate Testing Program. OR | ||
: 2. Drywell to suppression chamber differential pressure decreases | : 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 | > 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) | : 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 | 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. | : 2. Both SGT subsystems inoperable such that neither subsystem can draw and maintain 0.25" vacuum on Secondary Containment in accordance with SR 3.6.4.1.3. | ||
(continued) | |||
TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-22 Revision No. 23 (continued) | TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-22 Revision No. 23 (continued) | ||
Line 7,247: | Line 7,247: | ||
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. | 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 | OR | ||
: 2. Both RHRSW subsystems inoperable. | : 2. Both RHRSW subsystems inoperable. | ||
OR | 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 | : 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 | : 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 | : 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 | : 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 | : 5. SW System inoperable such that SW cannot be provided to the B vital header and the A RHRSW header. OR | ||
: 6. UHS > 92 | : 6. UHS > 92 | ||
°F or level less than -6 ft. mean sea level. | °F or level less than -6 ft. mean sea level. | ||
(continued) | |||
TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-23 Revision No. 23 (continued) | TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-23 Revision No. 23 (continued) | ||
====3.7.3 Control==== | ====3.7.3 Control==== | ||
Room Emergency Ventilation (CREV) System 1. Two CREV subsystems inoperable for reasons other than CREV System instrumentation. OR | 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 | : 2. Two CREV subsystems inoperable due to CREV System instrumentation and no CREV subsystems operating in the | ||
radiation protection mode. *3.7.4 Control Room Air Conditioning (AC) System Three Control Room AC subsystems inoperable. *3.8.1 AC Sources-Operating 1. Two or more DGs inoperable. | radiation protection mode. *3.7.4 Control Room Air Conditioning (AC) System Three Control Room AC subsystems inoperable. *3.8.1 AC Sources-Operating 1. Two or more DGs inoperable. | ||
OR | OR | ||
: 2. Two offsite circuits inoperable to two or more 4.16 kV emergency buses. 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 | : 3. One DG inoperable and two or more 4.16 kV offsite circuits inoperable. OR | ||
: 4. Two or more DGs inoperable and one or more 4.16 kV offsite circuits inoperable. *3.8.2 AC Sources-Shutdown All offsite circuits and the DG associated with a 4.16 kV emergency bus | : 4. Two or more DGs inoperable and one or more 4.16 kV offsite circuits inoperable. *3.8.2 AC Sources-Shutdown All offsite circuits and the DG associated with a 4.16 kV emergency bus | ||
required by LCO 3.8.8 are inoperable. | required by LCO 3.8.8 are inoperable. | ||
(continued) | |||
TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-24 Revision No. 23 (continued) | TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-24 Revision No. 23 (continued) | ||
*3.8.3 Diesel Fuel Oil 1. One or more DGs with day fuel oil tank level < 22,650 gal. and main fuel oil storage tank level < 20,850 gal. per DG. OR | *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. | : 2. One or more DGs with day fuel oil tank level < 17,000 gal. | ||
OR | OR | ||
: 3. One or more DGs with main fuel oil storage tank level < 13,900 gal. per DG. *3.8.4 DC Sources-Operating Two or more DC divisions (Unit 1 and 2) inoperable. *3.8.5 DC Sources-Shutdown A DC subsystem (Unit 1 or 2) required to support the shutdown unit is inoperable. | : 3. One or more DGs with main fuel oil storage tank level < 13,900 gal. per DG. *3.8.4 DC Sources-Operating Two or more DC divisions (Unit 1 and 2) inoperable. *3.8.5 DC Sources-Shutdown A DC subsystem (Unit 1 or 2) required to support the shutdown unit is inoperable. | ||
(continued) | |||
TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-25 Revision No. 23 (continued) | TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-25 Revision No. 23 (continued) | ||
*3.8.7 Distribution Systems-Operating 1. Two or more 4.16 kV emergency buses are inoperable. | *3.8.7 Distribution Systems-Operating 1. Two or more 4.16 kV emergency buses are inoperable. | ||
OR | OR | ||
: 2. A Division I 480 VAC emergency bus is inoperable concurrent with a Division II 4.16 kV emergency bus inoperability. 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 | : 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. | : 4. Two or more DC divisions (Unit 1 and 2) inoperable. | ||
OR | 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) | : 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 | inoperability such that one of the following occurs on the subject | ||
unit: | unit: | ||
: a. Loss of SDC capability when no recirc pumps are running. | : a. Loss of SDC capability when no recirc pumps are running. | ||
: b. Two or more ECCS subsystems are inoperable. | : b. Two or more ECCS subsystems are inoperable. | ||
: c. Two or more RHR SPC subsystems are inoperable. | : c. Two or more RHR SPC subsystems are inoperable. | ||
: d. Both SGT subsystems are inoperable. | : d. Both SGT subsystems are inoperable. | ||
: e. Both RHRSW subsystems are inoperable. | : e. Both RHRSW subsystems are inoperable. | ||
: f. Two or more DGs 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. | : 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. | : i. Three Control Room AC subsystems inoperable. | ||
(continued) | |||
TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-26 Revision No. 23 (continued) | TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-26 Revision No. 23 (continued) | ||
*3.8.8 Distribution Systems-Shutdown 1. Any 4.16 kV emergency bus that is required to support the shutdown unit is inoperable. OR | *3.8.8 Distribution Systems-Shutdown 1. Any 4.16 kV emergency bus that is required to support the shutdown unit is inoperable. OR | ||
: 2. Any 480 VAC emergency bus that is required to support the shutdown unit is inoperable. OR | : 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. | : 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. | ||
Line 7,327: | Line 7,327: | ||
included in the SFDP. | included in the SFDP. | ||
The purpose of the SFDP is to ensure that SFD evaluations: | The purpose of the SFDP is to ensure that SFD evaluations: | ||
: 1. are performed when required; | : 1. are performed when required; | ||
: 2. include the required provisions in order to detect a LOSF; | : 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. | : 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 | One example of the Support/Supported Feature relationship is the HPCI | ||
Line 7,471: | Line 7,471: | ||
Feature TS ACTIONS require cascading. If cascading is required, a SFD | Feature TS ACTIONS require cascading. If cascading is required, a SFD | ||
is not required. | is not required. | ||
(continued) | |||
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-4 Revision No. 23 Program Use and Application | TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-4 Revision No. 23 Program Use and Application | ||
Line 7,523: | Line 7,523: | ||
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. | 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. | This Maximum Completion Time requirement includes restoring all Support Features to OPERABLE status. | ||
(continued) | |||
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-5 Revision No. 23 Program Use and Application | TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-5 Revision No. 23 Program Use and Application | ||
MAXIMUM The Maximum Completion Time establishes a limit on the maximum COMPLETION time allowed for any combination of Support Features and Supported TIME Features being inoperable during a single contiguous occurrence of (continued) failing to meet the Suppor ted Feature's TS LCO. This "Maximum Completion Time" philosophy is similar to that of TS Section 1.3, Completion Times. | MAXIMUM The Maximum Completion Time establishes a limit on the maximum COMPLETION time allowed for any combination of Support Features and Supported TIME Features being inoperable during a single contiguous occurrence of (continued) failing to meet the Suppor ted Feature's TS LCO. This "Maximum Completion Time" philosophy is similar to that of TS Section 1.3, Completion Times. | ||
(continued) | |||
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-6 Revision No. 23 Program Use and Application | TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-6 Revision No. 23 Program Use and Application | ||
Line 7,541: | Line 7,541: | ||
the maximum Completion Time for restoring System C to OPERABLE | the maximum Completion Time for restoring System C to OPERABLE | ||
status is 10 days (3 days plus 7 days). | status is 10 days (3 days plus 7 days). | ||
(continued) | |||
Maximum Com p letion Time 3 da y s 7 da y s 3 da y s + 7 da y s = 10 da y sSystem A Da y 1 Da y 3 S y stem C Da y 10 Da y 3 S y stem B Da y 3 Da y 10 TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-7 Revision No. 23 Program Use and Application | Maximum Com p letion Time 3 da y s 7 da y s 3 da y s + 7 da y s = 10 da y sSystem A Da y 1 Da y 3 S y stem C Da y 10 Da y 3 S y stem B Da y 3 Da y 10 TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-7 Revision No. 23 Program Use and Application | ||
Line 7,624: | Line 7,624: | ||
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 | 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. | entered immediately upon discovery of the LOSF. | ||
(continued) | |||
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-9 Revision No. 23 SFD Evaluation Examples | TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-9 Revision No. 23 SFD Evaluation Examples | ||
Line 7,665: | Line 7,665: | ||
Required Action E.1 requires declaring the RCIC System | Required Action E.1 requires declaring the RCIC System | ||
inoperable and TS 3.5.3 Condition A must be entered. | inoperable and TS 3.5.3 Condition A must be entered. | ||
(continued) | |||
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-10 Revision No. 23 SFD Evaluation Examples | TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-10 Revision No. 23 SFD Evaluation Examples | ||
Line 7,713: | Line 7,713: | ||
Therefore, DGs 2,3, and 4 will start if required and are still | Therefore, DGs 2,3, and 4 will start if required and are still | ||
considered OPERABLE and a LOSF has not occurred. | considered OPERABLE and a LOSF has not occurred. | ||
(continued) | |||
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-11 Revision No. 23 SFD Evaluation Examples | TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-11 Revision No. 23 SFD Evaluation Examples | ||
Line 7,758: | Line 7,758: | ||
subsystem to OPERABLE status following subsequent contiguous | subsystem to OPERABLE status following subsequent contiguous | ||
inoperabilities (including all Support Features) is 1500 on 10/12/98; 24 hours (TS 3.3.5.1 Required Action C.2) plus 7 days (TS 3.5.1 Required Action A.1). | inoperabilities (including all Support Features) is 1500 on 10/12/98; 24 hours (TS 3.3.5.1 Required Action C.2) plus 7 days (TS 3.5.1 Required Action A.1). | ||
(continued) | |||
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-12 Revision No. 23 SFD Evaluation Examples (continued) | TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-12 Revision No. 23 SFD Evaluation Examples (continued) | ||
Line 7,813: | Line 7,813: | ||
Conclusion:== | Conclusion:== | ||
TS 3.6.4.3 Conditions A and B should be entered immediately upon discovery of the LOSF. | TS 3.6.4.3 Conditions A and B should be entered immediately upon discovery of the LOSF. | ||
(continued) | |||
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-13 Revision No. 23 SFD Evaluation Examples | TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-13 Revision No. 23 SFD Evaluation Examples | ||
Line 7,876: | Line 7,876: | ||
supplies. If a motor-operated valve is open and loses power, it cannot | supplies. If a motor-operated valve is open and loses power, it cannot | ||
provide the required isolation function. | provide the required isolation function. | ||
(continued) | |||
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-15 Revision No. 23 Attachments | TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-15 Revision No. 23 Attachments | ||
ATTACHMENT 3 This attachment is an aid which identifies all of the affected PCIVs. | 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 | supply. As noted, PCIVs are considered OPERABLE provided power is |
Revision as of 04:47, 25 April 2019
ML18249A160 | |
Person / Time | |
---|---|
Site: | Brunswick ![]() |
Issue date: | 08/13/2018 |
From: | Duke Energy Progress |
To: | Office of Nuclear Reactor Regulation |
Shared Package | |
ML18249A165 | List:
|
References | |
RA-18-0131 | |
Download: ML18249A160 (293) | |
Text
Technical Requirements Manual Brunswick Steam Electric Plant, Unit No. 2
Renewed Facility Operating License DPR-62
Revision 66
LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENTS MANUAL Brunswick Unit 2 LOEP-1 Revision No. 66
Page No. Revision No.
Page No. Revision No.
Title Page 66 3.0-1 23 3.0-2 23 List of Effective Pages 3.0-3 23
LOEP-1 66 3.1-1 23 LOEP-2 66 3.1-2 23 LOEP-3 66 LOEP-4 65 3.2-1 23 LOEP-5 65 3.3-1 23 0.0-1 55 3.3-2 23 0.0-2 66 3.3-3 23 0.0-3 45 3.3-4 36 0.0-4 23 0.0-5 23 3.4-1 60 0.0-6 23 3.4-2 29 3.4-3 60 1.1-1 23 1.1-2 23 3.5-1 32 1.1-3 23 3.5-2 23 3.5-3 23 1.2-1 23 1.2-2 23 3.6-1 31 1.2-3 23 3.6-2 23 3.6-3 23 1.3-1 23 1.3-2 23 3.7-1 23 1.3-3 23 1.3-4 23 3.8-1 31 1.3-5 23 3.8-2 23 1.3-6 23 1.3-7 23 3.9-1 47 1.3-8 23 3.9-2 47 1.3-9 23 3.9-3 47 1.3-10 23 1.3-11 23 3.10-1 31 1.3-12 23 3.11-1 23 1.4-1 23 3.11-2 51 1.4-2 23 3.11-3 51 1.4-3 23 1.4-4 23 3.12-1 23 1.4-5 23 3.12-2 57
2.0-1 23 (continued)
LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENTS MANUAL Brunswick Unit 2 LOEP-2 Revision No. 66
Page No. Revision No.
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)
LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENTS MANUAL Brunswick Unit 2 LOEP-3 Revision No. 66
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)
LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENTS MANUAL Brunswick Unit 2 LOEP-4 Revision No. 65
Page No. Revision No.
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APPENDIX B 23 APPENDIX D 23 B-1 23 D-1 23 B-2 44 D-2 26 B-3 23 D-3 23 B-4 44 D-4 30 B-5 23 D-5 26 B-6 23 D-6 26 B-7 39 D-7 26 B-8 23 D-8 23 B-9 23 D-9 42 B-10 23 D-10 26 B-11 23 D-11 26 B-12 24 D-12 26 B-13 23 D-13 23 B-14 23 D-14 49 B-15 23 D-15 49 B-16 23 D-16 23 B-17 23 D-17 59 B-18 28 D-18 23 B-19 23 D-19 23 B-20 23 D-20 23 B-21 23 D-21 24 B-22 48 B-23 23 APPENDIX E 23 B-24 34 E-1 23 B-25 23 E-2 23 B-26 63 B-27 64 APPENDIX F 23 B-28 23 SFDP-1 23 B-29 23 SFDP-2 23 SFDP-3 23 APPENDIX C 23 SFDP-4 23 C-1 23 SFDP-5 23 C-2 44 SFDP-6 23 C-3 61 SFDP-7 23 C-4 28 SFDP-8 23 C-5 23 SFDP-9 23 C-6 23 SFDP-10 23 C-7 23 SFDP-11 23 C-8 47 SFDP-12 23 C-9 52 SFDP-13 23 C-10 51 SFDP-14 23 C-11 57 SFDP-15 23
(continued)
LIST OF EFFECTIVE PAGES - TECHNICAL REQUIREMENTS MANUAL Brunswick Unit 2 LOEP-5 Revision 65
Page No. Revision No.
SFDP-16 23 SFDP-17 23 SFDP-18 23 SFDP-19 23 SFDP-20 23 SFDP-21 23 SFDP-22 23 SFDP-23 23 SFDP-24 23 SFDP-25 23 SFDP-26 23
B SFDP-1 23 B SFDP-2 23 B SFDP-3 23 B SFDP-4 23 B SFDP-5 23 B SFDP-6 23 B SFDP-7 23 B SFDP-8 23 B SFDP-9 23 B SFDP-10 23 B SFDP-11 23 B SFDP-12 23 B SFDP-13 23 B SFDP-14 23 B SFDP-15 23
Brunswick Unit 2 0.0-1 Revision No. 55 Carolina Power & Light Company Brunswick Unit 2 TITLE: Technical Requirements Manual Purpose, Control, and Contents PURPOSE: Provides information and guidance on requirements for various plant conditions, actions, and testing similar to the Technical Specifications, which is mainly required to support appropriate operation of the station in
accordance with commitments. The Technical Requirements Manual (TRM) is under the control of Carolina Power & Light (CP&L) Company
and all changes are to be evaluated for acceptance by performing
10 CFR 50.59 review.
SCOPE: This manual contains a wide variety of information on and requirements for various systems and processes, most of which existed in the
Technical Specifications at some previous point in time.
INTENDED USE: The TRM is intended to be used primarily by Operations to provide operating guidance for various plant equipment (similar to the Technical
Specifications) and as an aid for the Technical Specifications (e.g., valve
and instrument lists). The format of the requirements in the TRM is in
accordance with NUMARC 93-03, "Writers Guide for Restructured
Standard Technical Specifications".
Noncompliance with TRM requirements (i.e., Technical Requirements
Manual Specification (TRMS) and associated Required Compensatory
Measures not met or failure to perform a Test Requirement (TR) in
accordance with TR 3.0.2) requires the generation of a condition report
since the TRM requirements were violated, and other potential
consequences exist.
This manual is controlled in accordance with AD-LS-ALL-0015, "License
Amendment Request and Changes to SLC, TRM, and TS Bases."
Changes previously initiated under 0AP-057 (prior to October 7, 2013)
may be completed using that process. The technical information in each
section, including the associated Bases, and the Appendices is the
responsibility of the group(s) identified in the responsibility matrix on the
following page. All changes to TRM sections shall be reviewed by the
Licensing Unit prior to approval. In addition, all changes shall be
reviewed and approved by the Plant Nuclear Safety Committee prior to
implementation. Changes to this manual may be made by CP&L
Company as long as the changes are reviewed in accordance with
10 CFR 50.59 requirements and do not constitute a change to the
Technical Specifications or require a license amendment. The
responsibility for the administrative control of the manual is assigned to
the Licensing Unit.
Brunswick Unit 2 0.0-2 Revision No. 66 Matrix of Responsible Group(s) for TRM Sections, associated Bases, and Appendices SECTION TITLE RESPONSIBLE GROUP 3.0 Technical Requirements Manual Specifications (TRM) and Test Requirements (TR) Applicability Licensing /
Regulatory Programs 3.1 Control Rod Drive Housing Support BESS - MECH 3.2 Not used. 3.3 Control Rod Block Instrumentation BESS - MECH ELEC/I&C 3.4 Accident Monitoring Instrumentation BESS - ELEC/I&C 3.5 Chloride Intrusion Monitors BESS - ELEC/I&C 3.6 Bus Power Monitors BESS - ELEC/I&C 3.7 Automatic Depressurization System (ADS) Inhibit Switch BESS - ELEC/I&C 3.8 Suppression Chamber Water Temperature Instrumentation BESS - ELEC/I&C 3.9 Seismic Monitoring Instrumentation BESS - ELEC/I&C 3.10 Intake Canal High Water Level Instrumentation BESS - ELEC/I&C 3.11 Primary Containment Isolation Instrumentation BESS - ELEC/I&C 3.12 Control Room Emergency Ventilation (CREV) System Instrumentation BESS - ELEC/I&C 3.13 Reactor Coolant System (RCS) Chemistry E&RC 3.14 Structural Integrity BESS -
TECHNICAL SERVICES 3.15 Not used. 3.16 Service Water System Operability - Shutdown BESS - MECH 3.17 Service Water System - Shutdown Operations BESS - MECH 3.18 Control Room Emergency Vent ilation (CREV) System - Smoke Protection Mode BESS - MECH 3.19 Control Room Emergency Ventilation (CREV) System - Chlorine Protection Mode BESS - MECH 3.20 Flood Protection OPERATIONS 3.21 Snubbers FLEET PROGRAM ENGINEERING 3.22 Sealed Source Contamination E&RC 3.23 Decay Time BESS - MECH 3.24 Communications OPERATIONS 3.25 Crane and Hoist Operability BESS - MECH 3.26 Crane Travel - Spent Fuel Storage Pool BESS - MECH 5.5.1 Offsite Dose Calculation Manual E&RC 5.5.2 Primary Coolant Sources Outside Containment BESS -
TECHNICAL SERVICES 5.5.3 Deleted. 5.5.4 Radioactive Effluent Controls Program E&RC 5.5.5 Component Cyclic or Transient Limit Program BESS - MECH Brunswick Unit 2 0.0-3 Revision No. 45 Matrix of Responsible Group(s) for TRM Sections, associated Bases, and Appendices SECTION TITLE RESPONSIBLE GROUP 5.5.6 Inservice Testing Program BESS - TECHNICAL SERVICES 5.5.7 Ventilation Filter Testing Program BESS - MECH 5.5.8 Explosive Gas and Storage T ank Radioactivity Monitoring Program E&RC 5.5.9 Diesel Fuel Oil Testing Program E&RC 5.5.10 Technical Specification Bases Control Program LICENSING /
REGULATORY PROGRAMS 5.5.11 Safety Function Determination Program OPERATIONS 5.5.12 Primary Containment Leakage Rate Testing Program BESS - TECHNICAL SERVICES 5.5.13 Control Room Envelope Habitability Program BESS - SYSTEMS ENGINEERING 5.5.14 Configuration Risk Management Program OUTAGE &
SCHEDULING 5.5.15 Inservice Inspection Program BESS - TECHNICAL SERVICES APPENDIX A Relocated Items Matrix LICENSING /
REGULATORY PROGRAMS APPENDIX B Technical Specifications Instrumentation Numbers and Trip Setpoints List BESS - ELEC/I&C APPENDIX C Technical Requirements Manual Instrumentation Numbers and Trip Setpoints List BESS - ELEC/I&C APPENDIX D Primary Containment Isolation Valve List BESS - TECHNICAL SERVICES APPENDIX E Secondary Containment Isolation Damper List BESS - MECH APPENDIX F Safety Function Determination Program OPERATIONS
Brunswick Unit 2 0.0-4 Revision No. 23 TABLE OF CONTENTS
1.0 USE AND APPLICATION ..................................................................................... 1.1-1
1.1 Definitions
....................................................................................................... 1.1-1
1.2 Logical
Connectors ......................................................................................... 1.2-1
1.3 Completion
Times ........................................................................................... 1.3-1
1.4 Frequency
..................................................................................................... 1.4-1 2.0 NOT USED ........................................................................................................... 2.0-1
3.0 TECHNICAL
REQUIREMENTS MANUAL SPECIFICATION (TRMS) AND TEST REQUIREMENTS (TR) APPLICABILITY ....................................................... 3.0-1 3.1 CONTROL ROD DRIVE HOUSING SUPPORT ............................................. 3.1-1 3.2 NOT USED .................................................................................................... 3.2-1
3.3 CONTROL
ROD BLOCK ................................................................................ 3.3-1
3.4 ACCIDENT
MONITORING INSTRUMENTATION ......................................... 3.4-1 3.5 CHLORIDE INTRUSION MONITORS ............................................................ 3.5-1 3.6 BUS POWER MONITORS ............................................................................. 3.6-1
3.7 AUTOMATIC
DEPRESSURIZATION SYSTEM (ADS) INHIBIT SWITCH ...... 3.7-1 3.8 SUPPRESSION CHAMBER WATER TEMPERATURE INSTRUMENTATION ................................................................................ 3.8-1 3.9 SEISMIC MONITORING INSTRUMENTATION ............................................. 3.9-1 3.10 INTAKE CANAL HIGH WATER LEVEL INSTRUMENTATION .................... 3.10-1 3.11 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION .................. 3.11-1 3.12 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM INSTRUMENTATION .............................................................................. 3.12-1 3.13 REACTOR COOLANT SYSTEM (RCS) CHEMISTRY ................................. 3.13-1 3.14 STRUCTURAL INTEGRITY ......................................................................... 3.14-1 3.15 NOT USED ................................................................................................... 3.15-1 3.16 SERVICE WATER SYSTEM OPERABILITY-SHUTDOWN ....................... 3.16-1 3.17 SERVICE WATER SYSTEM-SHUTDOWN OPERATIONS ....................... 3.17-1
(continued)
TABLE OF CONTENTS (continued)
Brunswick Unit 2 0.0-5 Revision No. 23 3.18 CONTROL ROOM EMERGENCY VENTILATION (CREV)
SYSTEM-SMOKE PROTECTION MODE ............................................. 3.18-1 3.19 CONTROL ROOM EMERGENCY VENTILATION (CREV)
SYSTEM-CHLORINE PROTECTION MODE ......................................... 3.19-1 3.20 FLOOD PROTECTION ................................................................................. 3.20-1 3.21 SNUBBERS .................................................................................................. 3.21-1 3.22 SEALED SOURCE CONTAMINATION ........................................................ 3.22-1 3.23 DECAY TIME ................................................................................................ 3.23-1 3.24 COMMUNICATIONS .................................................................................... 3.24-1 3.25 CRANE AND HOIST OPERABILITY ............................................................ 3.25-1 3.26 CRANE TRAVEL-SPENT FUEL STORAGE POOL ................................... 3.26-1 4.0 NOT USED ............................................................................................................ 4.0-1
5.0 PROGRAMS
AND MANUALS ............................................................................... 5.0-1 B 3.0 TECHNICAL REQUIREMENTS MANUAL SPECIFICATION (TRMS) AND TEST REQUIREMENT (TR) APPLICABILITY ..................... B 3.0-1 B 3.1 CONTROL ROD DRIVE HOUSING SUPPORT ......................................... B 3.1-1 B 3.2 NOT USED ................................................................................................ B 3.2-1 B 3.3 CONTROL ROD BLOCK INSTRUMENTATION ........................................ B 3.3-1 B 3.4 ACCIDENT MONITORING INSTRUMENTATION ..................................... B 3.4-1 B 3.5 CHLORIDE INTRUSION MONITORS ........................................................ B 3.5-1 B 3.6 BUS POWER MONITORS ......................................................................... B 3.6-1 B 3.7 AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) INHIBIT SWITCH ................................................................................................. B 3.7-1 B 3.8 SUPPRESSION CHAMBER WATER TEMPERATURE INSTRUMENTATION ............................................................................ B 3.8-1 B 3.9 SEISMIC MONITORING INSTRUMENTATION ......................................... B 3.9-1 (continued)
TABLE OF CONTENTS (continued)
Brunswick Unit 2 0.0-6 Revision No. 23 B 3.10 INTAKE CANAL HIGH WATER LEVEL INSTRUMENTATION ................ B 3.10-1 B 3.11 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION .............. B 3.11-1 B 3.12 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM INSTRUMENTATION .......................................................................... B 3.12-1 B 3.13 REACTOR COOLANT SYSTEM (RCS) CHEMISTRY ............................. B 3.13-1 B 3.14 STRUCTURAL INTEGRITY ..................................................................... B 3.14-1 B 3.15 NOT USED ............................................................................................... B 3.15-1 B 3.16 SERVICE WATER SYSTEM OPERABILITY-SHUTDOWN ................... B 3.16-1 B 3.17 SERVICE WATER SYSTEM-SHUTDOWN OPERATIONS ................... B 3.17-1 B 3.18 CONTROL ROOM EMERGENCY VENTILATION (CREV)
SYSTEM-SMOKE PROTECTION MODE ......................................... B 3.18-1 B 3.19 CONTROL ROOM EMERGENCY VENTILATION (CREV)
SYSTEM-CHLORINE PROTECTION MODE .................................... B 3.19-1 B 3.20 FLOOD PROTECTION ............................................................................. B 3.20-1 B 3.21 SNUBBERS .............................................................................................. B 3.21-1 B 3.22 SEALED SOURCE CONTAMINATION .................................................... B 3.22-1 B 3.23 DECAY TIME ............................................................................................ B 3.23-1 B 3.24 COMMUNICATIONS ................................................................................ B 3.24-1 B 3.25 CRANE AND HOIST OPERABILITY ........................................................ B 3.25-1 B 3.26 CRANE TRAVEL-SPENT FUEL STORAGE POOL ............................... B 3.26-1
APPENDIX A RELOCATED ITEMS MATRIX APPENDIX B TECHNICAL SPECIFICATION (TS) INSTRUMENT LIST APPENDIX C TECHNICAL REQUIREMENTS MANUAL (TRM) INSTRUMENT LIST APPENDIX D PRIMARY CONTAINMENT ISOLATION VALVE (PCIV) LIST APPENDIX E SECONDARY CONTAINMENT ISOLATION DAMPER (SCID) LIST APPENDIX F SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)
Definitions
1.1 Brunswick
Unit 2 1.1-1 Revision No. 23 1.0 USE AND APPLICATION
TRMS 1.1 Definitions
NOTE -----------------------------------------------------------
The defined terms of this section appear in capitalized type and are applicable throughout these
Technical Requirements Manual Specifications and Bases.
Term Definition CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within
the necessary range and accuracy to known values of the
parameter that the channel monitors. The CHANNEL
CALIBRATION shall encompass the entire channel, including
the required sensor, alarm, display, and trip functions, and
shall include the CHANNEL FUNCTIONAL TEST. Calibration
of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace
qualitative assessment of sensor behavior and normal
calibration of the remaining adjustable devices in the channel.
The CHANNEL CALIBRATION may be performed by means
of any series of sequential, overlapping, or total channel
steps so that the entire channel is calibrated.
CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This
determination shall include, where possible, comparison of
the channel indication and status to other indications or
status derived from independent instrument channels
measuring the same parameter.
CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the
sensor as practicable to verify OPERABILITY, including
required alarm, interlock, display, and trip functions, and
channel failure trips. The CHANNEL FUNCTIONAL TEST
may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel
is tested.
(continued)
Definitions
1.1 Brunswick
Unit 2 1.1-2 Revision No. 23 TRMS 1.1 Definitions (continued)
CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor
vessel with the vessel head removed and fuel in the vessel.
The following exceptions are not considered CORE
ALTERATIONS:
- a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore
probes, or special movable detectors (including
undervessel replacement); and b. Control rod movement, provided there are no fuel assemblies in the associated core cell.
Suspension of CORE ALTERATIONS shall not preclude
completion of movement of a component to a safe position. LOGIC SYSTEM FUNCTIONAL A LOGIC SYSTEM FUNCTIONAL TEST shall be a test TEST of all required logic components (i.e., all required relays and contacts, trip units, solid state logic elements, etc.) of a logic
circuit, from as close to the sensor as practicable up to, but
not including, the actuated device, to verify OPERABILITY.
The LOGIC SYSTEM FUNCTIONAL TEST may be performed
by means of any series of sequential, overlapping, or total
system steps so that the entire logic system is tested.
MODE A MODE shall be as required by Technical Specifications.
OPERABLE-OPERABILITY A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of
performing its specified safety function(s) and when all
necessary attendant instrumentation, controls, normal or
emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for
the system, subsystem, division, component, or device to
perform its specified safety function(s) are also capable of
performing their related support function(s).
(continued)
Definitions
1.1 Brunswick
Unit 2 1.1-3 Revision No. 23 TRMS 1.1 Definitions (continued)
RATED THERMAL POWER RTP shall be a total reactor core heat transfer rate to the (RTP) reactor coolant of 2923 MWt.
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
Logical Connectors
1.2 Brunswick
Unit 2 1.2-1 Revision No. 23 1.0 USE AND APPLICATION
TRMS 1.2 Logical Connectors
PURPOSE The purpose of this section is to explain the meaning of logical connectors.
Logical connectors are used in Technical Requirements
Manual Specifications (TRMS) to discriminate between, and
yet connect, discrete Conditions, Required Compensatory
Measures, Completion Times, Tests, and Frequencies. The
only logical connectors that appear in TRMS are AND and OR. The physical arrangement of these connectors constitutes logical conventions with specific meanings.
BACKGROUND Several levels of logic may be used to state Required Compensatory Measures. These levels are identified by the
placement (or nesting) of the logical connectors and by the
number assigned to each Required Compensatory Measure.
The first level of logic is identified by the first digit of the
number assigned to a Required Compensatory Measure and
the placement of the logical connector in the first level of
nesting (i.e., left justified with the number of the Required
Compensatory Measure). The successive levels of logic are
identified by additional digits of the Required Compensatory
Measure number and by successive indentions of the logical
connectors.
When logical connectors are used to state a Condition, Completion Time, Test, or Frequency, only the first level of
logic is used, and the logical connector is left justified with the
statement of the Condition, Completion Time, Test, or
Frequency.
EXAMPLES The following examples illustrate the use of logical connectors.
(continued)
Logical Connectors
1.2 Brunswick
Unit 2 1.2-2 Revision No. 23 TRMS 1.2 Logical Connectors
EXAMPLES EXAMPLE 1.2-1 (continued)
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. TRMS not met. A.1 Verify . . .
AND A.2 Restore . . .
In this example the logical connector AND is used to indicate that when in Condition A, both Required Compensatory Measures A.1 and A.2 must
be completed.
(continued)
Logical Connectors
1.2 Brunswick
Unit 2 1.2-3 Revision No. 23 TRMS 1.2 Logical Connectors
EXAMPLES EXAMPLE 1.2-2 (continued)
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. TRMS not met. A.1 Trip . . .
OR A.2.1 Verify . . .
AND A.2.2.1 Reduce . . .
OR A.2.2.2 Perform . . .
OR A.3 Align . . .
This example represents a more complicated use of logical connectors.
Required Compensatory Measures A.1, A.2, and A.3 are alternative
choices, only one of which must be performed as indicated by the use of
the logical connector OR and the left justified placement. Any one of these three Compensatory Measures may be chosen. If A.2 is chosen, then both A.2.1 and A.2.2 must be performed as indicated by the logical
connector AND. Required Compensatory Measure A.2.2 is met by performing A.2.2.1 or A.2.2.2. The indented position of the logical
connector OR indicates that A.2.2.1 and A.2.2.2 are alternative choices, only one of which must be performed.
Completion Times
1.3 Brunswick
Unit 2 1.3-1 Revision No. 23 1.0 USE AND APPLICATION
TRMS 1.3 Completion Times
PURPOSE The purpose of this section is to establish the Completion Time convention and to provide guidance for its use.
BACKGROUND Technical Requirements Manual Spec ifications (TRMS) specify minimum requirements for unit systems or variables. The COMPENSATORY
MEASURES associated with a TRMS state Conditions that typically
describe the ways in which the requirements of the TRMS can fail to be
met. Specified with each stated Condition are Required Compensatory
Measure(s) and Completion Times(s).
DESCRIPTION The Completion Time is the amount of time allowed for completing a Required Compensatory Measure. It is referenced to the time of
discovery of a situation (e.g., inoperable equipment or variable not within
limits) that requires entering a COMPENSATORY MEASURES Condition
unless otherwise specified, providing the unit is in a MODE or specified
condition stated in the Applicability of the TRMS. Required
Compensatory Measures must be completed prior to the expiration of the
specified Completion Time. A COMPENSATORY MEASURES Condition
remains in effect and the Required Compensatory Measures apply until
the Condition no longer exists or the unit is not within the TRMS
Applicability.
If situations are discovered that require entry into more than one
Condition at a time within a single TRMS (multiple Conditions), the
Required Compensatory Measures for each Condition must be performed
within the associated Completion Time. When in multiple Conditions, separate Completion Times are tracked for each Condition starting from
the time of discovery of the situation that required entry into the Condition.
Once a Condition has been entered, subsequent divisions, subsystems, components, or variables expressed in the Condition, discovered to be
inoperable or not within limits, will not result in separate entry into the Condition unless specifically stated. The Required Compensatory
Measures of the Condition continue to apply to each additional failure, with Completion Times based on initial entry into the Condition.
(continued)
Completion Times
1.3 Brunswick
Unit 2 1.3-2 Revision No. 23 TRMS 1.3 Completion Times
DESCRIPTION However, when a subsequent division, subsystem, component, (continued) or variable expressed in the Condition is discovered to be inoperable or not within limits, the Completion Time(s) may be extended. To apply this
Completion Time extension, two criteria must first be met. The
subsequent inoperability:
- a. Must exist concurrent with the first inoperability; and b. Must remain inoperable or not within limits after the first inoperability is resolved.
The total Completion Time allowed for completing a Required
Compensatory Measure to address the subsequent inoperability shall be
limited to the more restrictive of either:
- a. The stated Completion Time, as measured from the initial entry into the Condition, plus an additional 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />; 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />," where the
Completion Time is referenced from a previous completion of the
Required Compensatory Measures versus the time of Condition entry) or
as a time modified by the phrase "from discovery . . ." Example 1.3-3
illustrates one use of this type of Completion Time. The 10 day
Completion Time specified for Condition A and B in Example 1.3-3 may
not be extended.
(continued)
Completion Times
1.3 Brunswick
Unit 2 1.3-3 Revision No. 23 TRMS 1.3 Completion Times (continued)
EXAMPLES The following examples illustrate the use of Completion Times with different types of Conditions and changing Conditions.
EXAMPLE 1.3-1 COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME B. Required Compensatory
Measure and
associated
Completion
Time not met. B.1 Be in MODE 3.
AND B.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND in MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. A total of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is allowed for reaching MODE 3 and a total of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (not
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />) 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, the time allowed for
reaching MODE 4 is the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> because the total time allowed for
reaching MODE 4 is 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
If Condition B is entered while in MODE 3, the time allowed for reaching
MODE 4 is the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.
(continued)
Completion Times
1.3 Brunswick
Unit 2 1.3-4 Revision No. 23 TRMS 1.3 Completion Times
EXAMPLES EXAMPLE 1.3-2 (continued)
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One pump inoperable. A.1 Restore pump to OPERABLE status. 7 days B. Required Compensatory
Measure and
associated
Completion
Time not met. B.1 Be in MODE 3.
AND B.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> When a pump is declared inoperable, Condition A is entered. If the pump
is not restored to OPERABLE status within 7 days, Condition B is also
entered and the Completion Time clocks for Required Compensatory
Measures B.1 and B.2 start. If the inoperable pump is restored to
OPERABLE status after Condition B is entered, Condition A and B are
exited, and therefore, the Required Compensatory Measures of
Condition B may be terminated.
(continued)
Completion Times
1.3 Brunswick
Unit 2 1.3-5 Revision No. 23 TRMS 1.3 Completion Times
EXAMPLES EXAMPLE 1.3-3 (continued)
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One Function X subsystem
A.1 Restore Function X
subsystem to
OPERABLE status. 7 days AND 10 days from
discovery of failure
to meet the TRMS B. One Function Y subsystem
B.1 Restore Function Y
subsystem to
OPERABLE status. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> AND 10 days from
discovery of failure
to meet the TRMS C. One Function X subsystem
AND One Function Y subsystem
C.1 Restore Function X
subsystem to
OPERABLE status. OR C.2 Restore Function Y
subsystem to
OPERABLE status. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> (continued)
Completion Times
1.3 Brunswick
Unit 2 1.3-6 Revision No. 23 TRMS 1.3 Completion Times
EXAMPLES EXAMPLE 1.3-3 (continued) When one Function X subsystem and one Function Y subsystem are
inoperable, Condition A and Condition B are concurrently applicable. The
Completion Times for Condition A and Condition B are tracked separately
for each subsystem, starting from the time each subsystem was declared
inoperable and the Condition was entered. A separate Completion Time
is established for Condition C and tracked from the time the second
subsystem was declared inoperable (i.e., the time the situation described
in Condition C was discovered).
If Required Compensatory Measure C.2 is completed within the specified
Completion Time, Conditions B and C are exited. If the Completion Time
for Required Compensatory Measure A.1 has not expired, operation may
continue in accordance with Condition A. The remaining Completion
Time in Condition A is measured from the time the affected subsystem
was declared inoperable (i.e., initial entry into Condition A).
The Completion Times of Conditions A and B are modified by a logical
connector, with a separate 10 day Completion Time measured from the
time it was discovered the TRMS was not met. In this example, without
the separate Completion Time, it would be possible to alternate between
Conditions A, B, and C in such a manner that operation could continue
indefinitely without ever restoring systems to meet the TRMS. The
separate Completion Time modified by the phrase "from discovery of
failure to meet the TRMS" is designed to prevent indefinite continued
operation while not meeting the TRMS. This Completion Time allows for
an exception to the normal "time zero" for beginning the Completion Time "clock". In this instance, the Completion Time "time zero" is specified as
commencing at the time the TRMS was initially not met, instead of at the
time the associated Condition was entered.
(continued)
Completion Times
1.3 Brunswick
Unit 2 1.3-7 Revision No. 23 TRMS 1.3 Completion Times
EXAMPLES EXAMPLE 1.3-4 (continued)
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One or more valves inoperable. A.1 Restore valve(s) to OPERABLE
status. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B. Required Compensatory
Measure and
associated
Completion
Time not met. B.1 Be in MODE 3.
AND B.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> 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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> provided this does not result in any subsequent valve being
inoperable for > 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
If the Completion Time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (plus the extension) expires while one
or more valves are still inoperable, Condition B is entered.
(continued)
Completion Times
1.3 Brunswick
Unit 2 1.3-8 Revision No. 23 TRMS 1.3 Completion Times
EXAMPLES EXAMPLE 1.3-5 (continued)
COMPENSATORY MEASURES
NOTE --------------------------------------------
Separate Condition entry is allowed for each inoperable valve.
CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One or more valves inoperable. A.1 Restore valve to OPERABLE status. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> B. Required Compensatory
Measure and
associated
Completion
Time not met. B.1 Be in MODE 3.
AND B.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> The Note above the COMPENSATORY MEASURES Table is a method
of modifying how the Completion Time is tracked. If this method of
modifying how the Completion Time is tracked was applicable only to a
specific Condition, the Note would appear in that Condition rather than at
the top of the COMPENSATORY MEASURES Table.
The Note allows Condition A to be entered separately for each inoperable
valve, and Completion Times tracked on a per valve basis. When a valve
is declared inoperable, Condition A is entered and its Completion Time
starts. If subsequent valves are declared inoperable, Condition A is
entered for each valve and separate Completion Times start and are
tracked for each valve.
(continued)
Completion Times
1.3 Brunswick
Unit 2 1.3-9 Revision No. 23 TRMS 1.3 Completion Times
EXAMPLES EXAMPLE 1.3-5 (continued)
If the Completion Time associated with a valve in Condition A expires, Condition B is entered for that valve. If the Completion Times associated
with subsequent valves in Condition A expire, Condition B is entered
separately for each valve and separate Completion Times start and are
tracked for each valve. If a valve that caused entry into Condition B is
restored to OPERABLE status, Condition B is exited for that valve.
Since the Note in this example allows multiple Condition entry and
tracking of separate Completion Times, Completion Time extensions do
not apply.
EXAMPLE 1.3-6 COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One channel inoperable.
A.1 Perform TR 3.x.x.x.
OR A.2 Reduce THERMAL POWER to 50% RTP.
Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> B. Required Compensatory
Measure and
associated
Completion
Time not met. B.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (continued)
Completion Times
1.3 Brunswick
Unit 2 1.3-10 Revision No. 23 TRMS 1.3 Completion Times
EXAMPLES EXAMPLE 1.3-6 (continued)
Entry into Condition A offers a choice between Required Compensatory
Measure A.1 or A.2. Required Compensatory Measure A.1 has a "once
per" Completion Time, which qualifies for the 25% extension, per
TR 3.0.2, to each performance after the initial performance. The initial
8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> is not met, Condition B is entered.
If after entry into Condition B, Required Compensatory Measure A.1
or A.2 is met, Condition B is exited and operation may then continue in
Condition A.
(continued)
Completion Times
1.3 Brunswick
Unit 2 1.3-11 Revision No. 23 TRMS 1.3 Completion Times
EXAMPLES EXAMPLE 1.3-7 (continued)
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One subsystem inoperable. A.1 Verify affected subsystem
isolated.
AND A.2 Restore subsystem to
OPERABLE status. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> AND Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
thereafter
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B. Required Compensatory
Measure and
associated
Completion
Time not met. B.1 Be in MODE 3.
AND B.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Required Compensatory Measure A.1 has two Completion Times. The
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time begins at the time the Condition is entered and
each "Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or any subsequent 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> interval
from the previous performance (plus the extension allowed by TR 3.0.2),
Condition B is entered. The Completion Time clock for Condition A does
not stop after Condition B is entered, but continues from the (continued)
Completion Times
1.3 Brunswick
Unit 2 1.3-12 Revision No. 23 TRMS 1.3 Completion Times
EXAMPLES EXAMPLE 1.3-7 (continued) time Condition A was initially entered. If Required Compensatory
Measure A.1 is met after Condition B is entered, Condition B is exited and
operation may continue in accordance with Condition A, provided the
Completion Time for Required Compensatory Measure A.2 has not
expired.
IMMEDIATE When "Immediately" is used as a Completion Time, the Required COMPLETION TIME Compensatory Measure should be pursued without delay and in a controlled manner.
Frequency
1.4 Brunswick
Unit 2 1.4-1 Revision No. 23 1.0 USE AND APPLICATION
TRMS 1.4 Frequency
PURPOSE The purpose of this section is to define the proper use and application of Frequency requirements.
DESCRIPTION Each Test Requirement (TR) has a specified Frequency in which the Test must be met in order to meet the associated Technical Requirements
Manual Specification (TRMS). An understanding of the correct
application of the specified Frequency is necessary for compliance with
the TR.
The "specified Frequency" is referred to throughout this section and each
of the Specifications of Section 3.0, Test Requirement (TR) Applicability.
The "specified Frequency" consists of the requirements of the Frequency
column of each TR, as well as certain Notes in the Test column that
modify performance requirements.
Sometimes special situations dictate when the requirements of a Test are
to be met. They are "otherwise stated" conditions allowed by TR 3.0.1.
They may be stated as clarifying Notes in the Test, as part of the Test, or
both. Example 1.4-4 discusses these special situations.
Situations where a Test could be required (i.e., its Frequency could
expire), but where it is not possible or not desired that it be performed
until sometime after the associated TRMS is within its Applicability, represent potential TR 3.0.4 conflicts. To avoid these conflicts, the TR (i.e., the Test or the Frequency) is stated such that it is only "required" when it can be and should be performed. With a TR satisfied, TR 3.0.4
imposes no restriction.
The use of "met or "performed" in these instances conveys specific
meanings. A Test is "met" only when the acceptance criteria are
satisfied. Known failure of the requirements of a Test, even without a
Test specifically being "performed," constitutes a Test not "met."
"Performance" refers only to the requirement to specifically determine the (continued)
Frequency
1.4 Brunswick
Unit 2 1.4-2 Revision No. 23 TRMS 1.4 Frequency
DESCRIPTION ability to meet the acceptance criteria. TR 3.0.4 restrictions would not (continued) apply if both the following conditions are satisfied: a. The Test is not required to be performed; and
- b. The Test is not required to be met or, even if required to be met, is not known to be failed.
EXAMPLES The following examples illustrate the various ways that Frequencies are specified. In these examples, the Applicability of the TRMS (TRMS not
shown) is MODES 1, 2, and 3.
EXAMPLE 1.4-1 TEST REQUIREMENTS TEST FREQUENCY Perform CHANNEL CHECK.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />) 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, an extension of the time interval to 1.25 times the interval
specified in the Frequency is allowed by TR 3.0.2 for operational
flexibility. The measurement of this interval continues at all times, even
when the TR is not required to be met per TR 3.0.1 (such as when the
equipment is inoperable, a variable is outside specified limits, or the unit
is outside the Applicability of the TRMS). If the interval specified by
TR 3.0.2 is exceeded while the unit is in a MODE or other specified
condition in the Applicability of the TRMS, and the performance of the
Test is not otherwise modified (refer to Examples 1.4-3 and 1.4-4), then
TR 3.0.3 becomes applicable.
(continued)
Frequency
1.4 Brunswick
Unit 2 1.4-3 Revision No. 23 TRMS 1.4 Frequency
EXAMPLES EXAMPLE 1.4-1 (continued)
If the interval as specified by TR 3.0.2 is exceeded while the unit is not in
a MODE or other specified condition in the Applicability of the TRMS for
which performance of the TR is required, the Test must be performed
within the Frequency requirements of TR 3.0.2 prior to entry into the
MODE or other specified condition. Failure to do so would result in a
violation of TR 3.0.4.
EXAMPLE 1.4-2 TEST REQUIREMENTS TEST FREQUENCY Verify flow is within limits.
Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after 25% RTP AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
The use of "once" indicates a single performance will satisfy the specified
Frequency (assuming no other Frequencies are connected by "AND
"). This type of Frequency does not qualify for the extension allowed by
TR 3.0.2.
(continued)
Frequency
1.4 Brunswick
Unit 2 1.4-4 Revision No. 23 TRMS 1.4 Frequency
EXAMPLES EXAMPLE 1.4-2 (continued) "Thereafter" indicates future performances must be established per
TR 3.0.2, but only after a specified condition is first met (i.e., the "once" performance in this example). If reactor power decreases to < 25% RTP, the measurement of both intervals stops. New intervals start upon
reactor power reaching 25% RTP.
EXAMPLE 1.4-3 TEST REQUIREMENTS TEST FREQUENCY
NOTE----------------------------
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> with power 25% RTP.
(continued)
Frequency
1.4 Brunswick
Unit 2 1.4-5 Revision No. 23 TRMS 1.4 Frequency
EXAMPLES EXAMPLE 1.4-3 (continued)
Once the unit reaches 25% RTP, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> would be allowed for
completing the Test. If the Test were not performed within this 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency were
not met), TR 3.0.4 would require satisfying the TR.
Brunswick Unit 2 2.0-1 Revision No. 23 2.0 Not used.
TRMS Applicability
3.0 Brunswick
Unit 2 3.0-1 Revision No. 23 3.0 TECHNICAL REQUIREMENTS MANUAL SPECIFICATION (TRMS) APPLICABILITY
TRMS 3.0.1 TRMSs shall be met during the MODES or other specified conditions in the Applicability, except as provided in TRMS 3.0.2.
TRMS 3.0.2 Upon discovery of a failure to meet a TRMS, the Required Compensatory Measures of the associated Conditions shall be met, except as provided
in TRMS 3.0.5.
If the TRMS is met or is no longer applicable prior to the expiration of the
specified Completion Times(s), completion of the Required
Compensatory Measure(s) is not required, unless otherwise stated.
TRMS 3.0.3 Not used.
TRMS 3.0.4 When a TRMS is not met, entry into a MODE or other specified condition in the Applicability shall not be made except when the associated
COMPENSATORY MEASURES to be entered permit continued operation
in the MODE or other specified condition in the applicability for an
unlimited period of time. This TRMS shall not prevent changes in
MODES or other specified conditions in the Applicability that are required
to comply with COMPENSATORY MEASURES, or that are part of a
shutdown of the unit.
Exceptions to this TRMS are stated in the individual TRMSs. These
exceptions allow entry into MODES or other specified conditions in the
Applicability when the associated COMPENSATORY MEASURES to be
entered allow unit operation in the MODE or other specified condition in
the Applicability only for a limited period of time.
TRMS 3.0.5 Equipment removed from serv ice or declared inoperable to comply with COMPENSATORY MEASURES may be returned to service under
administrative control solely to perfo rm testing required to demonstrate its OPERABILITY or the OPERABILITY of other equipment. This is an
exception to TRMS 3.0.2 for the system returned to service under
administrative control to perform the required testing.
TR Applicability
3.0 Brunswick
Unit 2 3.0-2 Revision No. 23 3.0 TEST REQUIREMENT (TR) APPLICABILITY
TR 3.0.1 TRs shall be met during the MODES or other specified conditions in the Applicability for individual TRMSs, unless otherwise stated in the TR.
Failure to meet a Test whether such failure is experienced during the
performance of the Test or between performances of the Test, shall be
failure to meet the TRMS. Failure to perform a Test within the specified
Frequency shall be failure to meet the TRMS except as provided in TR
3.0.3. Tests
do not have to be performed on inoperable equipment or
variables outside specified limits.
TR 3.0.2 The specified Frequency for each TR is met if the Test is performed within 1.25 times the interval specified in the Frequency, as measured
from the previous performance or as measured from the time a specified condition of the Frequency is met.
For Frequencies specified as "once," the above interval extension does
not apply. If a Completion Time requires periodic performance on a "once
per " basis, the above Frequency extension applies to each
performance after the initial performance.
Exceptions to this TRMS are stated in the individual TRMSs.
TR 3.0.3 If it is discovered that a Test was not performed within its specified Frequency, then compliance with the requirement to declare the TRMS
not met may be delayed, from the time of discovery, up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or up
to the limit of the specified Frequency, whichever is less. This delay
period is permitted to allow performance of the Test.
If the Test is not performed within the delay period, the TRMS must
immediately be declared not met, and the applicable Condition(s) must be
entered.
When the Test is performed within the delay period and the Test is not
met, the TRMS must immediately be declared not met, and the applicable
Condition(s) must be entered.
(continued)
TR Applicability
3.0 Brunswick
Unit 2 3.0-3 Revision No. 23 3.0 TR APPLICABILITY (continued)
TR 3.0.4 Entry into a MODE or other specified condition in the Applicability of a TRMS shall not be made unless the TRMS's Tests have been met within
their specified Frequency. This provision shall not prevent entry into
MODES or other specified conditions in the Applicability that are required
to comply with COMPENSATORY MEASURES or that are part of a
shutdown of the unit.
Control Rod Drive Housing Support
3.1 Brunswick
Unit 2 3.1-1 Revision No. 23 3.1 CONTROL ROD DRIVE HOUSING SUPPORT TRMS 3.1 The control rod drive housing support shall be in place.
APPLICABILITY: MODES 1, 2, and 3.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. Control rod drive housing support not in place. A.1 Be in MODE 3
AND A.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Control Rod Drive Housing Support
3.1 Brunswick
Unit 2 3.1-2 Revision No. 23 TEST REQUIREMENTS TEST FREQUENCY TR 3.1.1 Verify the control rod drive housing support is in place by inspection after reassembly.
Once prior to
startup any time
control rod drive
housing support
has been disassembled
AND Once prior to
startup any time
maintenance has
been performed in
the control rod
drive housing
support area
Brunswick Unit 2 3.2-1 Revision No. 23 3.2 Not used.
Control Rod Block Instrumentation
3.3 Brunswick
Unit 2 3.3-1 Revision No. 23 3.3 CONTROL ROD BLOCK INSTRUMENTATION TRMS 3.3 The control rod block instrumentation for each Function in Table 3.3-1 shall be OPERABLE. APPLICABILITY: According to Table 3.3-1.
COMPENSATORY MEASURES
NOTE -----------------------------------------------------------
Separate Condition entry is allowed for each channel.
CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. --------------NOTE---------------
Only applicable for
Functions 1, 2 and 3.
One or more functions with one or more required
channels inoperable. A.1 Restore channel(s) to OPERABLE status.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> B. One or more functions with control rod block capability
not maintained.
OR Required Compensatory Measures and associated
Completion Time of
Condition A not met. B.1 Place one channel in trip. 1 hour`
Control Rod Block Instrumentation
3.3 Brunswick
Unit 2 3.3-2 Revision No. 23 TEST REQUIREMENTS
NOTES ----------------------------------------------------------
- 1. Refer to Table 3.3-1 to determine which TRs apply for each Control Rod Block Instrumentation Function. 2. When a channel is placed in an inoperable status solely for performance of required Tests, entry into associated Conditions and Required Compensatory Measures may be delayed
for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.
Perform CHANNEL FUNCTIONAL TEST.
7 days TR 3.3.2 Perform CHANNEL FUNCTIONAL TEST.
92 days TR 3.3.3 --------------------------------NOTES------------------------------
Neutron detectors are excluded.
Perform CHANNEL CALIBRATION.
24 months TR 3.3.4 Adjust recirculation drive flow to conform to reactor flow. Once within
7 days after
reaching equilibrium
conditions
following refueling
outage (continued)
Control Rod Block Instrumentation
3.3 Brunswick
Unit 2 3.3-3 Revision No. 23 TEST REQUIREMENTS (continued)
TEST FREQUENCY TR 3.3.5 ---------------------------------NOTE-------------------------------
For Function 1.d, not required to be performed when
entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after
entering MODE 2.
Perform CHANNEL FUNCTIONAL TEST.
184 days Control Rod Block Instrumentation
3.3 Brunswick
Unit 2 3.3-4 Revision No. 36 Table 3.3-1 (page 1 of 1)
Control Rod Block Instrumentation
FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS
REQUIRED CHANNELS
TEST REQUIREMENTS
ALLOWABLE VALUE
- 1. Average Power Range Monitors
- a. Upscale (Flow Biased)
- b. Inoperative
- c. Downscale
- d. Upscale (Fixed)
1
1,2 1 2
3
3 3 3
TR 3.3.3 TR 3.3.4 TR 3.3.5 TR 3.3.5 TR 3.3.5
0.55W + 55.0%RTP (a) and 109.3% RTP NA 1.1% APRM power 14% RTP
- 2. Source Range Monitors
- a. Detector Not Full In
- b. Upscale
- c. Inoperative
- d. Downscale
2 (b),5 2(c),5 2(c),5 2 (b),5
2 2 2 2
NA 5 x 10 5 cps NA 3 cps
- a. Detector Not Full In
- b. Upscale
- c. Inoperable
- d. Downscale
2,5 2,5
2,5 2 (e),5
6 6
6 6
NA 108/125 of full scale
NA 3/125 of full scale 4. Scram Discharge Volume Water Level-High
1,2,5(f) 1 (g) TR 3.3.2 TR 3.3.3 73 gallons
(a) [0.55(W - W) + 55.0% RTP] when Technical Specification 3.3.1.1, Function 2.b, is reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating." The value of W is defined in plant procedures. (b) Bypassed when detector is reading > 100 cps or Intermediate Range Monitor (IRM) channels are on Range 3 or higher.
(c) Bypassed when associated IRM channels are on Range 8 or higher.
(d) Deleted.
(e) Bypassed when IRM channels are on Range 1.
(f) With any control rod withdrawn from a core cell containing one or more fuel assemblies. Not applicable to control rods removed per Technical Specification 3.10.5, "Single Control Rod Drive (CRD) Removal-Refueling," or 3.10.6, "Multiple Control Rod Withdrawal-Refueling." (g) Signal is contained in Channel A logic only.
Accident Monitoring Instrumentation
3.4 Brunswick
Unit 2 3.4-1 Revision No. 60 3.4 ACCIDENT MONITORING INSTRUMENTATION TRMS 3.4 The accident monitoring instrumentation for each Function in Table 3.4-1 shall be OPERABLE. APPLICABILITY: According to Table 3.4-1.
COMPENSATORY MEASURES
NOTES ----------------------------------------------------------
- 1. TRMS 3.0.4 is not applicable.
- 2. Separate Condition entry is allowed for each Function.
CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. --------------NOTE---------------
Only applicable to
Functions 1, 2, 3, 6, and 7.
One or more Functions with one required channel
inoperable. A.1 Restore required channel to OPERABLE status.
31 days B. One or more Functions with two required channels
OR --------------NOTE--------------
Only applicable to
Functions 4 and 5.
One or more Functions with one required channel
inoperable. B.1 Restore one required channel to OPERABLE
status. 7 days (continued)
Accident Monitoring Instrumentation
3.4 Brunswick
Unit 2 3.4-2 Revision No. 29 COMPENSATORY MEASURES (continued)
CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME C. Required Compensatory Measure and associated
Completion Time not met. C.1 Submit a Special Report to the NRC outlining the
preplanned alternate
monitoring method, the
cause of the inoperability, and plans for restoring the
instrumentation to
OPERABLE status.
14 days TEST REQUIREMENTS TEST FREQUENCY TR 3.4.1 Perform CHANNEL CHECK.
31 days TR 3.4.2 Perform CHANNEL CALIBRATION except for Drywell and Suppression Chamber H 2 and O 2 Analyzers.
24 months TR 3.4.3 Perform CHANNEL CALIBRATION of the Drywell and Suppression Chamber H 2 and O 2 Analyzers.
92 days Accident Monitoring Instrumentation
3.4 Brunswick
Unit 2 3.4-3 Revision No. 60 Table 3.4-1 (page 1 of 1)
Accident Monitoring Instrumentation FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS 1. Suppression Chamber Atmosphere Temperature 2. Drywell Radiation
- 3. Safety/Relief Valve Position Indication
- a. Primary-Sonic
- b. Secondary-Temperature 4. Turbine Building Ventilation Monitor 5. Offgas Stack Ventilation Monitor
- 6. Drywell and Suppression Chamber H 2 Analyzer 7. Drywell and Suppression Chamber O 2 Analyzer 1,2 1,2,3 1,2
1,2,3 1,2,3 1,2 1,2 2 2 1 per valve
1 1 1 1
Chloride Intrusion Monitors
3.5 Brunswick
Unit 2 3.5-1 Revision No. 32
3.5 CHLORIDE
INTRUSION MONITORS TRMS 3.5 The chloride intrusion monitor channels for each Function in Table 3.5-1 shall be OPERABLE. APPLICABILITY: MODE 1 and 2.
COMPENSATORY MEASURES
NOTE -----------------------------------------------------------
Operation may continue with one or two Functions inoperable.
CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. Three or four Functions with one or more required
channels inoperable. A.1 Sample one parameter monitored by the
inoperable Function(s).
4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> AND Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />
thereafter
Chloride Intrusion Monitors
3.5 Brunswick
Unit 2 3.5-2 Revision No. 23 TEST REQUIREMENTS
NOTE -----------------------------------------------------------
Refer to Table 3.5-1 to determine which TRs apply for each Chloride Intrusion Monitor Function.
TEST FREQUENCY TR 3.5.1 Perform CHANNEL CHECK.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TR 3.5.2 Perform CHANNEL FUNCTIONAL TEST.
31 days TR 3.5.3 Perform CHANNEL CALIBRATION.
184 days TR 3.5.4 Perform CHANNEL CALIBRATION.
24 months
Chloride Intrusion Monitors
3.5 Brunswick
Unit 2 3.5-3 Revision No. 23 Table 3.5-1 (page 1 of 1)
Chloride Intrusion Monitors FUNCTION REQUIRED CHANNELS TEST REQUIREMENTS ALLOWABLE VALUE 1. Chloride Leak Detectors in the Condenser Hotwell
Outlet Headers 2. Chloride Leak Detector in the Condensate Pump
Discharge (Wide Range or
Narrow Range)
- a. Wide Range
- b. Narrow Range 3. Chloride Leak Detector in the Inlet to the Condensate
Filter Demineralizer 4. Chloride Leak Detector in the Inlet to the Deep Bed
Demineralizer 4
1
1 1 TR 3.5.1
TR 3.5.2
TR 3.5.4
TR 3.5.1
TR 3.5.2
TR 3.5.3
TR 3.5.1
TR 3.5.2
TR 3.5.3
TR 3.5.1
TR 3.5.2
TR 3.5.3 2.0 mhos/cm
10 mhos/cm 0.5 mhos/cm 0.5 mhos/cm 0.5 mhos/cm Bus Power Monitors
3.6 Brunswick
Unit 2 3.6-1 Revision No. 31 3.6 BUS POWER MONITORS TRMS 3.6 The alarm function of the Emergency Core Cooling System (ECCS) and Reactor Core Isolation Cooling (RCIC) System actuation instrumentation
bus power monitors in Table 3.6-1 shall be OPERABLE.
NOTE---------------------------------------------
The annunciator function may be removed from operation for performance of troubleshooting for up to 30 minutes provided no work on the associated
power supplies is in progress. --------------------------------------------------------------------------------------------------
APPLICABILITY: According to Table 3.6-1.
COMPENSATORY MEASURES
NOTE -----------------------------------------------------------
Separate Condition entry is allowed for each channel.
CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One or more channels inoperable. A.1 Verify bus power availability to the system's
logic. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
thereafter B. Required Compensatory Measure and associated
Completion Time not met. B.1 Declare associated supported equipment
Immediately
Bus Power Monitors
3.6 Brunswick
Unit 2 3.6-2 Revision No. 23 TEST REQUIREMENTS TEST FREQUENCY TR 3.6.1 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months
Bus Power Monitors
3.6 Brunswick
Unit 2 3.6-3 Revision No. 23 Table 3.6-1 (page 1 of 1)
Bus Power Monitors FUNCTION APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED CHANNELS PER BUS 1. Core Spray System Bus Power Monitor 2. Low Pressure Coolant Injection (Residual Heat Removal System)
Bus Power Monitor 3. High Pressure Cooling Injection System Bus Power Monitor 4. Automatic Depressurization System Bus Power Monitor 5. RCIC System Bus Power Monitor 1,2,3 4 (a),5 (a) 1,2,3 4 (a),5 (a) 1,2,3 1,2 (a),3 (a) 1,2,3 1 1 1 1 1 (a) When associated subsystems are required to be OPERABLE.
ADS Inhibit Switch
3.7 Brunswick
Unit 2 3.7-1 Revision No. 23 3.7 AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) INHIBIT SWITCH TRMS 3.7 Two channels of the ADS Inhibit Switch Function shall be OPERABLE.
APPLICABILITY: MODE 1, MODES 2 and 3 with reactor steam dome pressure > 150 psig.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One or both ADS Inhibit Switches not in the
automatic position. A.1 Place both ADS Inhibit Switches in the automatic
position.
AND A.2 Declare ADS inoperable.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> B. One or both ADS Inhibit Switch channels inoperable.B.1 Declare ADS inoperable. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
TEST REQUIREMENTS TEST FREQUENCY TR 3.7.1 Verify ADS Inhibit Switches are in the automatic position.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TR 3.7.2 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months
Suppression Chamber Water Temperature
3.8 Brunswick
Unit 2 3.8-1 Revision No. 31
3.8 SUPPRESSION
CHAMBER WATER TEMPERATURE INSTRUMENTATION TRMS 3.8 Two suppression chamber water temperature instrumentation channels shall be OPERABLE with 11 OPERABLE RTD inputs per channel.
NOTE---------------------------------------------
The annunciator function may be removed from operation for performance of troubleshooting for up to 30 minutes provided the associated function
maintains monitoring capability. --------------------------------------------------------------------------------------------------
APPLICABILITY: MODE 1, 2 and 3.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One suppression chamber water temperature
instrumentation channel
inoperable. A.1 Restore channel to OPERABLE status.
7 days B. Two suppression chamber water temperature
instrumentation channels
inoperable. B.1 Restore one channel to OPERABLE status.
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> C. Required Compensatory Measure and associated
Completion Time not met. C.1 Verify suppression chamber water
temperature is within
required limits.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
thereafter
Suppression Chamber Water Temperature Instrumentation
3.8 Brunswick
Unit 2 3.8-2 Revision No. 23 TEST REQUIREMENTS TEST FREQUENCY TR 3.8.1 Perform CHANNEL CHECK.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TR 3.8.2 Perform CHANNEL FUNCTIONAL TEST.
31 days TR 3.8.3 Perform CHANNEL CALIBRATION. The Allowable Value of the alarm shall be 95°F. 24 months Seismic Monitoring Instrumentation
3.9 Brunswick
Unit 2 3.9-1 Revision No. 47 3.9 SEISMIC MONITORING INSTRUMENTATION TRMS 3.9 Seismic monitoring instrumentation in Table 3.9-1 shall be OPERABLE.
APPLICABILITY: At all times.
COMPENSATORY MEASURES
NOTE -----------------------------------------------------------
Separate Condition entry is allowed for each instrument.
CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One or more seismic monitoring instruments
inoperable. A.1 Restore seismic monitoring instrument to
OPERABLE status.
31 days B. Required Compensatory Measure A.1 and associated
Completion Time not met. B.1 Submit a Special Report to the NRC outlining the
cause of the malfunction
and plans for restoring the
instrument to OPERABLE
status. 14 days C. --------------NOTE---------------
Required Compensatory
Measures C.2 and C.3 shall
be completed whenever
Condition C is entered.
OBE exceedance light is
energized. C.1 Restore seismic monitoring instrument to
OPERABLE status.
AND C.2 Perform TR 3.9.3.
AND C.3 Submit a Special Report to the NRC describing the
magnitude and frequency
spectrum and effect upon
facility features important
to safety. The magnitude
and frequency spectrum of
the event shall be based
upon data retrieved and
analyzed from the
actuated instruments.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
10 days
14 days Seismic Monitoring Instrumentation
3.9 Brunswick
Unit 2 3.9-2 Revision No. 47 TEST REQUIREMENTS
NOTE -----------------------------------------------------------
Refer to Table 3.9-1 to determine which TRs apply to each seismic monitoring instrument.
TEST FREQUENCY TR 3.9.1 Perform CHANNEL CHECK.
31 days TR 3.9.2 Perform CHANNEL FUNCTIONAL TEST.
184 days TR 3.9.3 Perform CHANNEL CALIBRATION.
24 months
Seismic Monitoring Instrumentation
3.9 Brunswick
Unit 2 3.9-3 Revision No. 47 Table 3.9-1 (page 1 of 1)
Seismic Monitoring Instrumentation INSTRUMENTS AND SENSOR LOCATIONS MEASUREMENT RANGE REQUIRED INSTRUMENTS TEST REQUIREMENTS 1. Passive Triaxial Peak Shock Recorders
- a. Reactor Building Basement/Equipment
Drain Tank (-17' level) b. Reactor Building RHR Heat Exchanger Support
(+20' level) c. Reactor Building Refueling Area (+117'
level) 2-25 Hz 2-25 Hz 2-25 Hz 1 1 1 TR 3.9.3 TR 3.9.3 TR 3.9.3 2. Active Triaxial Accelerometers
- a. Reactor Building
(+89'4" level)
- b. Reactor Building
(-17' level)
- 3. Active Seismic Recording System
- a. Control Room 0-1.0g 0-1.0g
0-1.0g 1 1
1 TR 3.9.1
TR 3.9.2
TR 3.9.3
TR 3.9.1
TR 3.9.2
TR 3.9.3
TR 3.9.1
TR 3.9.2
TR 3.9.3
Intake Canal High Water Level Instrumentation 3.10 Brunswick Unit 2 3.10-1 Revision No. 31 3.10 INTAKE CANAL HIGH WATER LEVEL INSTRUMENTATION TRMS 3.10 The intake canal high water level instrumentation shall be OPERABLE.
NOTE---------------------------------------------
The annunciator function may be removed from operation for performance of troubleshooting for up to 30 minutes provided a method to monitor water
level is maintained. --------------------------------------------------------------------------------------------------
APPLICABILITY: At all times.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. Intake canal high water level instrumentation inoperable. A.1 Verify intake canal water level is 17'6" mean sea level USGS datum.
Immediately
AND Once per 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />
thereafter
TEST REQUIREMENTS TEST FREQUENCY TR 3.10.1 Perform CHANNEL FUNCTIONAL TEST.
92 days TR 3.10.2 Perform CHANNEL CALIBRATION.
24 months
Primary Containment Isolation Instrumentation 3.11 Brunswick Unit 2 3.11-1 Revision No. 23 3.11 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION TRMS 3.11 The primary containment instrumentation for each Function in Table 3.11-1 shall be OPERABLE. APPLICABILITY: MODES 1, 2, and 3.
COMPENSATORY MEASURES
NOTE -----------------------------------------------------------
Separate Condition entry is allowed for each channel.
CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One or more required channels inoperable.
A.1 ---------------NOTE-------------
An inoperable channel
need not be placed in trip
where this would cause
the isolation to occur. In
this case, if the channel is
not restored to
OPERABLE status within
the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Completion
Time, Condition B must be
entered.
-- Place channel in trip.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (continued)
Primary Containment Isolation Instrumentation 3.11 Brunswick Unit 2 3.11-2 Revision No. 51 COMPENSATORY MEASURES (continued)
CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME B. Required Compensatory Measure and associated
Completion Time not met.
OR One or more functions with isolation capability not
maintained. B.1 Restore isolation capability.
OR B.2.1 Prepare a plan to restore channel(s) to OPERABLE
status and assign a
responsible individual to
ensure the restoration plan
is carried out.
AND B.2.2 Initiate a condition report.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains isolation capability.
TEST FREQUENCY TR 3.11.1 Perform CHANNEL FUNCTIONAL TEST.
184 days TR 3.11.2 Perform CHANNEL CALIBRATION.
24 months TR 3.11.3 Perform LOGIC SYSTEM FUNCTIONAL TEST and simulated automatic operation.
24 months Primary Containment Isolation Instrumentation 3.11 Brunswick Unit 2 3.11-3 Revision No. 51 Table 3.11-1 (page 1 of 1)
Primary Containment Isolation Instrumentation FUNCTION REQUIRED CHANNELS PER TRIP SYSTEM ALLOWABLE VALUE 1. Main Steam Line Tunnel Temperature-High (except for Main Steam Isolation
Valve Pit instruments) 2. Turbine Building Area Temperature-High 2 (a) 4 (b) 197°F 197°F (a) A channel is OPERABLE if 2 of 3 instruments in the channel are OPERABLE.
(b) A channel is OPERABLE if 2 of 4 instruments in the channel are OPERABLE.
CREV System Instrumentation 3.12 Brunswick Unit 2 3.12-1 Revision No. 23 3.12 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM INSTRUMENTATION TRMS 3.12 The CREV System instrumentation for each Function in Table 3.12-1 shall be OPERABLE. APPLICABILITY: According to Table 3.12-1.
COMPENSATORY MEASURES
NOTE -----------------------------------------------------------
Separate Condition entry is allowed for each Function.
CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One or both Chlorine Isolation Functions with one
chlorine detector inoperable
in one or both associated
trip subsystems. A.1 Restore detector(s) to OPERABLE status.
7 days B. Required Compensatory Measure and associated
Completion Time of
Condition A not met. B.1 Place the CREV System in the chlorine protection
mode of operation.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> C. One or both Chlorine Isolation Functions with two
chlorine detectors
inoperable in one or both
associated trip subsystems. C.1 Place the CREV System in the chlorine protection
mode of operation.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (continued)
CREV System Instrumentation 3.12 Brunswick Unit 2 3.12-2 Revision No. 57 COMPENSATORY MEASURES (continued)
CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME D. One Control Building Intake Air Duct Detector InoperableD.1 Restore detector(s) to OPERABLE status.
7 days E. Required Compensatory Measure and associated
Completion Time of
Condition D not met. E.1 Place CREV System in the radiation/smoke protection
mode of operation.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> F. Both Control Building Intake Air Duct Detectors
Inoperable F.1 Place the CREV System in the radiation/smoke
protection mode of
operation.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> CREV System Instrumentation 3.12 Brunswick Unit 2 3.12-3 Revision No. 23 TEST REQUIREMENTS
NOTE -----------------------------------------------------------
Refer to Table 3.12-1 to determine which TRs apply for each CREV System Instrumentation
Function.
TEST FREQUENCY TR 3.12.1 Perform CHANNEL FUNCTIONAL TEST.
31 days TR 3.12.2 Perform CHANNEL FUNCTIONAL TEST.
184 days TR 3.12.3 Perform CHANNEL CALIBRATION.
12 months
CREV System Instrumentation 3.12 Brunswick Unit 2 3.12-4 Revision No. 57 Table 3.12-1 (page 1 of 1)
CREV System Instrumentation FUNCTION
APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS REQUIRED DETECTORS PER TRIP SYSTEM TEST REQUIREMENTS
ALLOWABLE VALUE
- 1. Chlorine Isolation
- a. Control Building Air Intake (Local)
- b. Chlorine Tank Car Area (Remote)
(a)
(a)
4(b) 4(b)
TR 3.12.1
TR 3.12.3
5 ppm 5 ppm
- 2. Control Room Envelope Smoke Protection
- a. Control Building Intake Air Duct Smoke Detectors
1,2,3,4 5, (c)
1
TR 3.12.2
NA
(a) With chlorine tank car within the exclusion area.
(b) Four OPERABLE detectors per Trip System, consisting of two detectors per trip subsystem.
(c) During movement of irradiated fuel assemblies in secondary containment.
RCS Chemistry 3.13 Brunswick Unit 2 3.13-1 Revision No. 23 3.13 REACTOR COOLANT SYSTEM (RCS) CHEMISTRY TRMS 3.13 The chemistry of the RCS shall be maintained within the limits of Table 3.13-1. APPLICABILITY: According to Table 3.13-1.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. Conductivity greater than the limit of Table 3.13-1 but
< 10mhos/cm at 25
°C in MODE 1, 2, or 3.
OR Chloride concentration greater than the limit of
Table 3.13-1 but < 0.5 ppm
in MODE 1, 2, or 3. A.1 Verify by administrative means that operation
under this condition shall
not exceed 336 hours0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br /> per
year. AND A.2 ---------------NOTE-------------
TRMS 3.0.4 is not
applicable.
-- Restore chemistry parameter(s) to within
limit(s).
Immediately
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> B. Required Compensatory Measure A.1 and associated
Completion Time not met. B.1 Submit a Special Report to the NRC outlining the
cause of the
non-compliance, plans for
restoring the parameter to
within limit, and the impact
of the non-compliance on
RCS integrity.
14 days (continued)
RCS Chemistry 3.13 Brunswick Unit 2 3.13-2 Revision No. 23 COMPENSATORY MEASURES (continued)
CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME C. Required Compensatory Measure A.2 and associated
Completion Time not met.
OR Conductivity 10mhos/cm @ 25°C in MODE 1, 2, or 3.
OR Chloride concentration 0.5 ppm in MODE 1, 2, or 3. C.1 Be in MODE 3.
AND C.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> D. Conductivity greater than the limit of Table 3.13-1 in
MODE 4 or 5.
OR Chloride concentration greater than the limit of
Table 3.13-1 in MODE 4
or 5. D.1 Restore chemistry parameter to within limit.
48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />
RCS Chemistry 3.13 Brunswick Unit 2 3.13-3 Revision No. 23 TEST REQUIREMENTS TEST FREQUENCY TR 3.13.1 ---------------------------------NOTE-------------------------------
Not required to be met if all continuous recording
conductivity monitors are inoperable and TR 3.13.2 is
satisfied.
Record RCS conductivity.
Continuously TR 3.13.2 ---------------------------------NOTE-------------------------------
Not required to be met if TR 3.13.1 is satisfied.
Analyze an RCS sample for conductivity.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TR 3.13.3 Analyze an RCS sample for conductivity.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> TR 3.13.4 Analyze an RCS sample for chloride concentration. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
RCS Chemistry 3.13 Brunswick Unit 2 3.13-4 Revision No. 23 Table 3.13-1 (page 1 of 1)
RCS Chemistry Limits CHEMISTRY PARAMETER
APPLICABLE MODES OR OTHER SPECIFIED CONDITION LIMIT
- 1. Chlorides 1 2,3,4,5 < 0.5 ppm
< 0.2 ppm
- 2. Conductivity 1,2 3,4,5 < 2.0 mhos/cm @ 25
°C < 10.0 mhos/cm @ 25
°C Structural Integrity 3.14 Brunswick Unit 2 3.14-1 Revision No. 65 3.14 STRUCTURAL INTEGRITY TRMS 3.14 The structural integrity of the ASME Code Class 1, 2, 3, MC, and CC components shall be maintained.
APPLICABILITY: MODES 1, 2, 3, 4, and 5.
COMPENSATORY MEASURES
NOTE -----------------------------------------------------------------
Separate Condition entry is allowed for each component.
CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. -------------NOTE------------
Required Action A.1 shall be
completed if this Condition is
entered.
Unevaluated indication or
failed inspection is found in
an ASME Code Class 1, 2, 3
MC, or CC component(s), or
structural support
component(s). A.1 Evaluate the impact of the indication or failed
inspection on
OPERABILITY and
structural integrity of the affected systems, structures, or components.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B. Structural integrity of any of ASME Code Class 1
component(s) not
maintained. B.1 Declare the associated system, structure, or
component inoperable.
AND B.2 Initiate action to isolate the affected component(s).
AND B.3 Restore the structural integrity of affected
component(s) to within
limits. Immediately
Immediately
Prior to entering
MODES 1, 2, or 3 (continued)
Structural Integrity 3.14 Brunswick Unit 2 3.14-2 Revision No. 65 COMPENSATORY MEASURES (continued) CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME C. Structural integrity of any of ASME Code Class 2 or
Class 3 component(s) not
maintained. C.1.1 Initiate action to isolate the affected component(s).
OR C.1.2 Declare the affected component(s)
inoperable/nonfunctional.
AND C.2 Initiate action to restore structural integrity of
affected component(s) to
within limits.
AND C.3 Restore the structural integrity of affected
component(s) to within
limits. Immediately
Immediately
Immediately
Prior to entering
MODES 1, 2, or 3 D. Structural integrity of any of ASME Code Class MC or
Class CC component(s) not
maintained. D.1 Declare the affected component(s)
inoperable/nonfunctional.
AND D.2 Initiate action to restore structural integrity of
affected component(s) to
within limits.
AND D.3 Restore the structural integrity of affected
component(s) to within
limits. Immediately
Immediately
Prior to entering
MODES 1, 2, or 3 E. Condition A, B, C, or D or associated Completion Time
not met. E.1 Declare the associated systems, structures, or
components
inoperable/nonfunctional.
Immediately
Structural Integrity 3.14 Brunswick Unit 2 3.14-3 Revision No. 65 TEST REQUIREMENTS TEST FREQUENCY TR 3.14.1 Verify the structural integrity of ASME Code Class 1, 2, 3, MC, and CC components.
In accordance with
the Inservice
Inspection
Program Brunswick Unit 2 3.15-1 Revision No. 23 3.15 Not used.
Service Water System OPERABILITY-Shutdown 3.16 Brunswick Unit 2 3.16-1 Revision No. 58 3.16 SERVICE WATER SYSTEM OPERABILITY-SHUTDOWN TRMS 3.16 The Service Water System shall be OPERABLE with: a. Three OPERABLE site Nuclear Service Water (NSW) pumps and
- b. Two OPERABLE Service Water (SW) pumps (any combination of NSW or Conventional Service Water (CSW) pumps) powered from
separate emergency buses and capable of supplying the nuclear
service water header. APPLICABILITY: MODES 4 and 5.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One required NSW pump inoperable due to inoperable
Unit 2 nuclear service water
header. --------------------NOTE-------------------
TRMS 3.0.4 is not applicable.
A.1 Verify by administrative means that two Unit 1
NSW pumps are
AND A.2 Administratively control nuclear service water
header valves to ensure
cooling water to the
required diesel generators.
AND A.3 Verify two Unit 2 SW pumps are OPERABLE on
the conventional service
water header.
AND
Immediately
Immediately
Immediately (continued)
Service Water System OPERABILITY-Shutdown 3.16 Brunswick Unit 2 3.16-2 Revision No. 58 COMPENSATORY MEASURES (continued)
CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. (continued) A.4 Administratively control valves to isolate
OPERABLE CSW pumps
and required loads from
the inoperable nuclear
header. AND A.5 Restore required NSW pump. Immediately
14 days B. One required NSW pump inoperable for reasons other
than Condition A. B.1 Restore required NSW pump. 7 days C. Required Compensatory Measure and associated
Completion Time of
Condition A or B not met.
OR Two or more required NSW pumps inoperable. C.1 Declare required diesel generators inoperable.
Immediately D. One required SW pump inoperable. D.1 Restore required SW pump. 7 days E. Required Compensatory Measure and associated
Completion Time of
Condition D not met.
OR Two required SW pumps inoperable. E.1 Declare required supported equipment
Immediately
Service Water System OPERABILITY-Shutdown 3.16 Brunswick Unit 2 3.16-3 Revision No. 33 TEST REQUIREMENTS TEST FREQUENCY TR 3.16.1 ---------------------------------NOTE-----------------------------
Isolation of flow to individual components does not
render the Service Water System inoperable.
Verify each Service Water System manual, power operated, and automatic valve in the flow paths servicing safety related systems or components, that is
not locked, sealed, or otherwise secured in position, is
in the correct position.
31 days TR 3.16.2 --------------------------------NOTES--------------------------- 1. A single test at the specified Frequency will satisfy this test for both units. 2. Isolation of flow to individual components does not render the Service Water System
Verify automatic transfer of each diesel generator cooling water supply from the normal service water
supply to the alternate service water supply on low
diesel generator jacket cooling water supply pressure.
92 days TR 3.16.3 ---------------------------------NOTE-----------------------------
Isolation of flow to individual components does not
render the Service Water System inoperable.
Verify each required Service Water System automatic component actuates on an actual or simulated
initiation signal.
24 months Service Water System-Shutdown Operations 3.17 Brunswick Unit 2 3.17-1 Revision No. 23 TEST REQUIREMENTS (continued) 3.17 SERVICE WATER SYSTEM-SHUTDOWN OPERATIONS TRMS 3.17 The conventional service water header may be removed from operation by stopping the service water pumps to permit isolating and draining the
nuclear service water header for maintenance provided:
- a. The conventional service water header is lined up to supply cooling to required ECCS loads; b. The draining/maintenance on the nuclear service water header will not affect the Conventional Service Water System or the lineup described
in TRMS 3.17.a above; c. Average Reactor Coolant System (RCS) coolant temperature is 100°F at the start of the evolution and the heatup rate is 10°F per hour; and d. Two dedicated, qualified members of the unit operational staff are assigned to manually initiate the conventional service water pumps in
response to: 1. Any event which requires ECCS actuation, or
- 2. RCS coolant temperature > 180
°F, or 3. A loss of offsite power. APPLICABILITY: MODES 4 and 5 with the nuclear service water header inoperable.
Service Water System-Shutdown Operations 3.17 Brunswick Unit 2 3.17-2 Revision No. 23 COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. Requirements of TRMS not met. A.1 Initiate action to restore conventional service water
header to operation.
OR A.2 Initiate action to restore nuclear service water
status. Immediately
Immediately
TEST REQUIREMENTS TEST FREQUENCY TR 3.17.1 Verify the conventional service water header is lined up to supply cooling water for ECCS by verifying that
each valve servicing safety related equipment that is
not locked in the proper position is administratively
controlled in the proper position.
Prior to securing
all service water
pumps TR 3.17.2 Verify two way communications between the control room and the service water building.
Prior to securing
all service water
pumps AND 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter (continued)
Service Water System-Shutdown Operations 3.17 Brunswick Unit 2 3.17-3 Revision No. 23 TEST REQUIREMENTS (continued)
TEST FREQUENCY TR 3.17.3 Verify RCS coolant temperature is 180°F. 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> CREV System-Smoke Protection Mode 3.18 Brunswick Unit 2 3.18-1 Revision No. 23 3.18 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM-SMOKE PROTECTION MODE TRMS 3.18 The smoke protection mode of the CREV System shall be OPERABLE with two OPERABLE control room emergency filtration subsystems. APPLICABILITY: MODES 1, 2, 3, 4, and 5, During movement of irradiated fuel assemblies in the secondary containment.
COMPENSATORY MEASURES
NOTE -----------------------------------------------------------
Required Compensatory Measures to initiate condition reports need not be completed when
control room emergency filtration subsystem inoperability is due solely to planned maintenance
or surveillance testing.
CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One control room emergency filtration
subsystem inoperable. A.1 Restore control room emergency filtration
subsystem to OPERABLE
status. OR A.2.1 Prepare a plan to return the control room
emergency filtration
subsystem to OPERABLE
status and assign a
responsible individual to
ensure the restoration plan
is carried out.
AND A.2.2 Initiate a condition report.
7 days
7 days
7 days (continued)
CREV System-Smoke Protection Mode 3.18 Brunswick Unit 2 3.18-2 Revision No. 23 COMPENSATORY MEASURES (continued)
CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME B. Two control room emergency filtration
subsystems inoperable. B.1 Prepare a plan to return the control room
emergency filtration
subsystems to
OPERABLE status and
assign a responsible
individual to ensure the
restoration plan is carried
out. AND B.2 Initiate a condition report.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TEST REQUIREMENTS TEST FREQUENCY TR 3.18.1 Verify the CREV System automatically diverts its inlet flow through the HEPA filters and charcoal adsorber
banks of the Control Room Emergency Filtration
System on an actual or simulated smoke detection
signal. 24 months CREV System-Chlorine Protection Mode 3.19 Brunswick Unit 2 3.19-1 Revision No. 23 3.19 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM-CHLORINE PROTECTION MODE TRMS 3.19 The chlorine protection mode of the CREV System shall be OPERABLE.
APPLICABILITY: When the chlorine tank car is located within the exclusion area.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. Chlorine protection mode of the CREV System
inoperable for reasons other
than inoperable chlorine
isolation instrumentation. A.1 Remove the chlorine tank car from the exclusion
area. OR A.2.1 Prepare a plan to return the chlorine protection
mode of the CREV
System to OPERABLE
status and assign a
responsible individual to
ensure the restoration plan
is carried out.
AND A.2.2 ---------------NOTE-------------
Condition report need not
be generated when
inoperability is due solely
to planned maintenance or
surveillance testing.
-- Initiate a condition report.
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> CREV System-Chlorine Protection Mode 3.19 Brunswick Unit 2 3.19-2 Revision No. 23 TEST REQUIREMENTS TEST FREQUENCY TR 3.19.1 Verify the CREV Syst em automatically isolates on an actual or simulated chlorine detection signal and the
Control Room Emergency Filtration System cannot be
started by an actual or simulated smoke or radiation
detection signal.
24 months Flood Protection 3.20 Brunswick Unit 2 3.20-1 Revision No. 23 3.20 FLOOD PROTECTION TRMS 3.20 Intake canal water level shall be 17'6" Mean Sea Level USGS datum. APPLICABILITY: At all times.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. Intake canal water not within limit. A.1 Initiate applicable emergency procedure to
mitigate consequences of
flooding vital equipment.
AND A.2. Be in MODE 3.
AND A.3 Be in MODE 4.
Immediately
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> TEST REQUIREMENTS TEST FREQUENCY TR 3.20.1 ---------------------------------NOTE-------------------------------
Not required to be performed when intake canal water
level is < 15'0" mean sea level USGS datum.
Verify intake canal water level is 17'6" mean sea level USGS datum.
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Snubbers 3.21 Brunswick Unit 2 3.21-1 Revision No. 40 3.21 SNUBBERS TRMS 3.21 All hydraulic and mechanical snubbers shall be OPERABLE.
APPLICABILITY: When associated systems are required to be OPERABLE.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. ---------------NOTE--------------
Required Compensatory
Measure A.1 shall be
completed if this Condition is
entered.
One or more snubbers inoperable that are
associated with only one
train or subsystem of a
multiple train or subsystem
supported system or are
associated with a single
train or subsystem
supported system. A.1 Determine snubber failure mode and that supported
system is acceptable for
continued operation.
AND A.2 Restore snubber to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B. ---------------NOTE--------------
Required Compensatory
Measure B.1 shall be
completed if this Condition is
entered.
One or more snubbers inoperable that are
associated with more than
one train or subsystem of a
multiple train or subsystem
supported system. B.1 Determine snubber failure mode and that supported
system is acceptable for
continued operation.
AND B.2 Restore snubber to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> C. Required Compensatory Measure and associated
Completion Time not met. C.1 Declare associated system(s) inoperable.
Immediately Snubbers 3.21 Brunswick Unit 2 3.21-2 Revision No. 66 TEST REQUIREMENTS TEST FREQUENCY TR 3.21.1 Perform snubber testing in accordance with the Snubber Program Plan.
In accordance with
AD-EG-BNP-1618, "Snubber Program
Plan."
Sealed Source Contamination 3.22 Brunswick Unit 2 3.22-1 Revision No. 23 3.22 SEALED SOURCE CONTAMINATION TRMS 3.22 Each sealed source containing radioactive material in excess of 100Ci of beta and/or gamma emitting material or in excess of 5Ci of alpha emitting material shall have < 0.005Ci of removable contamination. APPLICABILITY: At all times.
COMPENSATORY MEASURES
NOTE -----------------------------------------------------------
Separate Condition entry is allowed for each sealed source.
CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. One or more sealed sources with removable
contamination 0.005Ci. A.1 Withdraw the sealed source from use.
AND A.2.1 Initiate action to decontaminate and repair
the sealed source.
OR A.2.2 Initiate action to dispose of the sealed source in
accordance with NRC
regulations.
AND A.3 Submit a Special Report to the NRC. Immediately
Immediately
Immediately
12 months Sealed Source Contamination 3.22 Brunswick Unit 2 3.22-2 Revision No. 23 TEST REQUIREMENTS
NOTES ----------------------------------------------------------
- 1. Tests for leakage and/or contamination shall be performed by the licensee or other persons specifically authorized by the NRC or an Agreement State. 2. The test method shall have a detection sensitivity of 0.005Ci per test sample. ------------------------------------------------------------------------------------------------------------------------------- TEST FREQUENCY TR 3.22.1 --------------------------------NOTES------------------------------ 1. Startup sources and fission detectors previously subjected to core flux are excluded. 2. Sealed sources and fission detector sources that are stored and not being used are excluded.
Perform testing for leakage and/or contamination for each sealed source containing radioactive material
with a half-life > 30 days and in any form other than
gas, excluding hydrogen 3.
184 days TR 3.22.2 ---------------------------------NOTE-------------------------------
Not required to be performed if performed within the
previous 184 days.
Perform testing for leakage for each sealed source and fission detector source that is stored and not in
use.
Prior to use or
transfer to another
licensee TR 3.22.3 Perform testing of sealed sources transferred without a certificate indicating the last test date.
Prior to use (continued)
Sealed Source Contamination 3.22 Brunswick Unit 2 3.22-3 Revision No. 23 TEST REQUIREMENTS (continued)
TEST FREQUENCY TR 3.22.4 ---------------------------------NOTE-------------------------------
Not required to be performed for sealed startup
sources or fission detectors that are continuously
enclosed within a shielded mechanism.
Perform leak testing of each sealed startup source and fission detector.
Once within
31 days prior to
being subjected to
core flux
AND Once within
31 days prior to
being installed in
the core following
any repair or
maintenance Decay Time 3.23 Brunswick Unit 2 3.23-1 Revision No. 23 3.23 DECAY TIME TRMS 3.23 The reactor shall be subcritical for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. APPLICABILITY: During movement of irradiated fuel in the reactor pressure vessel.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. Reactor subcritical
< 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. A.1 Suspend movement of irradiated fuel in the
Immediately
TEST REQUIREMENTS TEST FREQUENCY TR 3.23.1 Determine the reactor has been subcritical for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verification of the date and time of subcriticality.
Prior to movement
of irradiated fuel in
the reactor pressure vessel Communications 3.24 Brunswick Unit 2 3.24-1 Revision No. 23 3.24 COMMUNICATIONS TRMS 3.24 Direct communications shall be maintained between the control room and refueling platform personnel. APPLICABILITY: During CORE ALTERATIONS, except normal control rod movement.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. Direct communications between control room and
refueling platform personnel
not maintained. A.1 Suspend CORE ALTERATIONS except for
normal control rod
movement.
Immediately
TEST REQUIREMENTS TEST FREQUENCY TR 3.24.1 Verify the availability of direct communications between the control room and refueling platform
personnel.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Crane and Hoist OPERABILITY 3.25 Brunswick Unit 2 3.25-1 Revision No. 23 3.25 CRANE AND HOIST OPERABILITY TRMS 3.25 All cranes and hoists used for handling fuel assemblies and control rods within the reactor pressure vessel (RPV) shall be OPERABLE. APPLICABILITY: During movement of fuel assemblies or control rods within the RPV using cranes or hoists.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY MEASURE COMPLETION TIME A. Requirements of TRMS not met. A.1 Suspend use of any inoperable crane and hoist
from operations involving
movement of fuel
assemblies or control rods
in the RPV after placing
the load in a safe location.
Immediately
Crane and Hoist OPERABILITY 3.25 Brunswick Unit 2 3.25-2 Revision No. 23 TEST REQUIREMENTS TEST FREQUENCY TR 3.25.1 Demonstrate operation of the overload cutoff of each crane or hoist to be used for movement of fuel
assemblies or control rods within the RPV:
- a. When the load is 1600 lbs for the mast fuel gripper; and b. When the load is 1050 lbs for all other cranes and hoists.
Once within
7 days prior to
start of movement
of fuel assemblies
or control rods
within the RPV
using the
associated crane
or hoist, if not
performed within
the previous 30
days. TR 3.25.2 Demonstrate operation of the loaded interlock of each crane or hoist to be used for movement of fuel
assemblies or control rods within the RPV:
- a. When the load is 750 lbs for the mast fuel gripper; and b. When the load is 350 lbs for all other cranes and hoists.
Once within
7 days prior to
start of movement
of fuel assemblies
or control rods
within the RPV
using the
associated crane
or hoist, if not
performed within
the previous 30
days. (continued)
Crane and Hoist OPERABILITY 3.25 Brunswick Unit 2 3.25-3 Revision No. 23 TEST REQUIREMENTS (continued)
TEST FREQUENCY TR 3.25.3 Demonstrate operation of the slack cable cutoff of the mast fuel gripper when the load is < 50 +/- 25 lbs.
Once within
7 days prior to
start of movement
of fuel assemblies
or control rods
within the RPV
using the mast fuel
gripper, if not
performed within
the previous 30
days. TR 3.25.4 Perform a load test of 1000 lbs of each crane or hoist to be used for movement of fuel assemblies or
control rods within the RPV.
Once within
7 days prior to
start of movement
of fuel assemblies
or control rods
within the RPV
using the
associated crane
or hoist, if not
performed within
the previous 30
days. (continued)
Crane and Hoist OPERABILITY 3.25 Brunswick Unit 2 3.25-4 Revision No. 23 TEST REQUIREMENTS (continued)
TEST FREQUENCY TR 3.25.5 Demonstrate operation of the uptravel stop of each crane or hoist (other than the mast fuel gripper) to be
used for movement of fuel assemblies or control rods
within the RPV when uptravel would bring the top of
active fuel to 7 ft below the normal spent fuel pool
water level.
Once within
7 days prior to
start of movement
of fuel assemblies
or control rods
within the RPV
using the
associated crane
or hoist, if not
performed within
the previous 30
days.
Crane Travel-Spent Fuel Storage Pool 3.26 Brunswick Unit 2 3.26-1 Revision No. 23 3.26 CRANE TRAVEL-SPENT FUEL STORAGE POOL TRMS 3.26 Loads > 1600 lbs shall be prohibited from travel over fuel assemblies in the spent fuel pool storage racks. APPLICABILITY: When fuel assemblies are in the spent fuel pool storage racks.
COMPENSATORY MEASURES CONDITION REQUIRED COMPENSATORY ACTION COMPLETION TIME A. Requirements of TRMS not met. A.1 Place the load in a safe condition.
Immediately
TEST REQUIREMENTS TEST FREQUENCY TR 3.26.1 Verify loads, other than fuel assemblies, are 1600 lbs. Prior to movement
of loads over fuel assemblies in the
spent fuel pool
storage racks Brunswick Unit 2 4.0-1 Revision No. 23 4.0 Not used.
Programs and Manuals
5.0 Brunswick
Unit 2 5.0-1 Revision No. 45
5.0 PROGRAMS
AND MANUALS
5.5.1 Offsite
Dose Calculation Manual Technical Specification 5.5.1, "Offsite Dose Calculation Manual," is
implemented by the Brunswick Steam Electric Plant Off-Site Dose Calculation
Manual. 5.5.2 Primary Coolant Sources Outside Containment Technical Specification 5.5.2, "Primary Coolant Sources Outside
Containment," requires controls be provided to minimize leakage from those
portions of systems outside containment that could contain highly radioactive
fluids during a serious transient or accident to levels as low as practicable.
The program is implemented by the following procedures:
0PT-07.2.4A, 0PT-07.2.4B, 0PT-08.2.2C, 0PT-08.2.2B, 0PT-09.2, 0PT-10.1.1, and
0PT-14.6.
5.5.3 Deleted.
(continued)
Programs and Manuals
5.0 Brunswick
Unit 2 5.0-2 Revision No. 41
5.0 PROGRAMS
AND MANUALS (continued)
5.5.4 Radioactive
Effluent Controls Program Technical Specification 5.5.4, "Radioactive Effluent Controls Program,"
requires controls be established to conform with 10 CFR 50.36a for control of
radioactive effluents and for maintaining doses to members of the public from
radioactive effluents as low as reasonably achievable. This program is
implemented through Section 7.0 of the Brunswick Steam Electric Plant Off-
Site Dose Calculation Manual. 5.5.5 Component Cyclic or Transient Limit Program Technical Specification 5.5.5, "Component Cyclic or Transient Limit," requires
controls be provided to track the UFSAR, Table 5.3.3-2 cyclic and transient
occurrences to ensure that components are maintained within design limits.
The program is implemented by the following procedure:
0ENP-44. 5.5.6 Inservice Testing Program Technical Specification 5.5.6, "Inservice Testing Program," requires controls
be established for inservice testing of ASME Code Class 1, 2, and 3, components. This program is implemented by the following:
0ENP-17 and the applicable procedures that implement ASME OM Code
requirements.
5.5.7 Ventilation
Filter Testing Program (VFTP)
Technical Specification 5.5.7, "Ventilation Filter Testing Program (VFTP),"
requires testing of the Engineered Safety Feature filter ventilation systems for
the following Technical Specification systems:
Control Room Emergency Ventilation System and Standby Gas Treatment
System. (continued)
Programs and Manuals
5.0 Brunswick
Unit 2 5.0-3 Revision No. 45
5.0 PROGRAMS
AND MANUALS
5.5.7 Ventilation
Filter Testing Program (VFTP)
(continued)
The program is implemented by the following procedures:
2PT-15.1.1A, 2PT-15.1.1B, 2PT-15.1.2A, 2PT-15.1.2B, 0PT-17.0, and
0PT-21.1 In addition, laboratory analysis required by Technical Specification 5.5.7.c
must be completed within 31 days after removal of a representative carbon sample. 5.5.8 Explosive Gas and Storage Tank Radioactivity Monitoring Program Technical Specification 5.5.8, "Explosive Gas and Storage Tank Radioactivity
Monitoring Program," requires controls be provided for potentially explosive gas mixtures contained in the Main Condenser Offgas Treatment System and
the quantity of radioactivity contained in the unprotected outdoor storage
tanks. The program is implemented by ODCMS 7.3.6, "Liquid Holdup
Tanks," ODCMS 7.3.12, "Explosive Gas Mixtures," and procedures
0E&RC-1000 and 0E&RC-1222. 5.5.9 Diesel Fuel Oil Testing Program Technical Specification 5.5.9, "Diesel Fuel Oil Testing Program," requires
testing requirements be provided for new fuel oil and stored fuel oil and
includes sampling requirements and acceptance criteria. The program is
implemented by the following procedures:
0E&RC-1010, 0E&RC-1142, 0E&RC-1141, 0E&RC-1138, and
0E&RC-1020.
(continued)
Programs and Manuals
5.0 Brunswick
Unit 2 5.0-4 Revision No. 45
5.0 PROGRAMS
AND MANUALS (continued)
5.5.10 Technical Specification Bases Control Program Technical Specification 5.5.10, "Technical Specification Bases Control
Program," requires means be provided for processing changes to the Bases
of the Technical Specifications. The program is implemented by the following
procedure:
0AP-019. 5.5.11 Safety Function Determination Program Technical Specification 5.5.11, "Safety Function Determination Program,"
requires means be provided to ensure a loss of function is detected and
appropriate actions taken. The program is implemented by Appendix F of the
Technical Requirements Manual. 5.5.12 Primary Containment Leakage Rate Testing Program Technical Specification 5.5.12, "Primary Containment Leakage Rate Testing
Program," requires implementation of leakage rate testing of the primary
containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B as modified by approved exem ptions. The program is implemented by the following:
0PT-20.3, 0PT-20.3b, 0PT-20.3c, 0PT-20.5, 0PT-20.5.1, 0ENP-16.4, and
0ENP-16.8.
(continued)
Programs and Manuals
5.0 Brunswick
Unit 2 5.0-5 Revision No. 62
5.0 PROGRAMS
AND MANUALS (continued)
5.5.13 Control Room Envelope Habitability Program Technical Specification 5.5.13, "Control Room Envelope Habitability
Program," requires controls be established and testing performed to ensure
habitability of the control room envelope is maintained following a radiological
event, hazardous chemical release, or a smoke challenge. The program is
implemented by the following:
0ENP-54 0MST-CREV22
0OI-01.01
0PT-23.1.2
0PT-23.1.3
0PT-46.4 0PT-26.0 5.5.14 Configuration Risk Management Program The Configuration Risk Management Program (CRMP) provides a
proceduralized risk-informed assessment to manage the risk associated with
equipment inoperability. The program applies to Technical Specification
structures, systems, or components for which a risk-informed allowed outage
time has been granted (i.e., Technical Specification 3.8.1, Condition B). The
program shall include the following elements:
- a. Provisions for the control and implementation of a Level 1 at-power internal events PRA-informed methodology. The assessment shall be
capable of evaluating the applicable plant configuration. (0AP-025) b. Provisions for performing an assessment prior to entering the Limiting Condition for Operation (LCO) Action for preplanned activities.
(0AP-025) c. Provisions for performing an assessment after entering the LCO Action for unplanned entry into the LCO Action. (0AP-025)
(continued)
Programs and Manuals
5.0 Brunswick
Unit 2 5.0-6 Revision No. 45
5.0 PROGRAMS
AND MANUALS
5.5.14 Configuration Risk Management Program (continued) d. Provision for assessing the need for additional actions after the discovery of additional equipment out of service conditions while in the
LCO Action. (0AP-025) e. Provisions for considering other applicable risk significant contributors such as Level 2 issues and external events, qualitatively or
quantitatively. (0AP-025, ADM-NGGC-0101, 0AI-068, and 0PEP-02.6) 5.5.15 Inservice Inspection Program This program provides controls for inservice inspection of ASME Code
Class 1, 2, and 3 components and their supports, and Class MC (i.e., metal
containment) and CC (i.e., concrete containment) components. This program
is implemented by the following:
0ENP-16 and the applicable procedures that implement ASME Section XI
requirements.
TRMS Applicability B 3.0 Brunswick Unit 2 B 3.0-1 Revision No. 23 B 3.0 TECHNICAL REQUIREMENTS MANUAL SPECIFICATION (TRMS) APPLICABILITY
BASES TRMSs TRMS 3.0.1 through TRMS 3.0.5 establish the general requirements applicable to all Specifications and apply at all times, unless otherwise
stated. TRMS 3.0.1 TRMS 3.0.1 establishes the Applicability statement within each individual TRMS as the requirement for when the TRMS is required to be met (i.e.,
when the unit is in the MODES or other specified conditions of the
Applicability statement of each TRMS).
TRMS 3.0.2 TRMS 3.0.2 establishes that upon discovery of a failure to meet a TRMS, the associated COMPENSATORY MEASURES shall be met. The
Completion Time of each Required Compensatory Measure for a
COMPENSATORY MEASURES Condition is applicable from the point in
time that a COMPENSATORY MEASURES Condition is entered. The
Required Compensatory Measures establish those remedial measures
that must be taken within specified Completion Times when the
requirements of a TRMS are not met. This TRMS establishes that:
- a. Completion of the Required Compensatory Measures within the specified Completion Times constitutes compliance with a TRMS;
and b. Completion of the Required Compensatory Measures is not required when a TRMS is met within the specified Completion
Time, unless otherwise specified.
There are two basic types of Required Compensatory Measures. The
first type of Required Compensatory Measure specifies a time limit in
which the TRMS must be met. This time limit is the Completion Time to
restore an inoperable system or component to OPERABLE status or to
restore variables to within specified limits. If this type of Required
Compensatory Measure is not completed within the specified Completion
Time, a shutdown may be required to place the unit in a MODE or
condition in which the TRMS is not applicable. (Whether stated as a
Required Compensatory (continued)
TRMS Applicability B 3.0 Brunswick Unit 2 B 3.0-2 Revision No. 26
BASES TRMS 3.0.2 Measure or not, correction of the entered Condition is a compensatory (continued) measure that may always be considered upon entering COMPENSATORY MEASURES.) The second type of Required
Compensatory Measure specifies the remedial measures that permit
continued operation of the unit that is not further restricted by the
Completion Time. In this case, compliance with the Required
Compensatory Measures provides an acceptable level of safety for
continued operation.
Completing the Required Compensatory Measures is not required when a
TRMS is met or is no longer applicable, unless otherwise stated in the
individual TRMSs.
The nature of some Required Compensatory Measures of some
Conditions necessitates that, once the Condition is entered, the Required
Compensatory Measures must be completed even though the associated
Condition no longer exists. The individual TRMS's COMPENSATORY
MEASURES specify the Required Compensatory Measures where this is
the case. An example of this is in TRMS 3.21, "Snubbers."
The Completion Times of the Required Compensatory Measures are also
applicable when a system or com ponent is removed from service
intentionally. The reasons for intentionally relying on the
COMPENSATORY MEASURES include, but are not limited to, performance of Tests, preventive maintenance, corrective maintenance, or investigation of operational problems. Entering COMPENSATORY
MEASURES for these reasons must be done in a manner that does not
compromise safety. Intentional entry into COMPENSATORY
MEASURES should not be made for operational convenience.
Alternatives that would not result in redundant equipment being
inoperable should be used instead. Doing so limits the time both
subsystems/divisions of a safety function are inoperable. Individual
TRMSs may specify a time limit for performing a TR when equipment is
removed from service or bypassed for testing. In this case, the
Completion Times of the Required Compensatory Measures are
applicable when this time limit expires, if the equipment remains removed
from service or bypassed.
When a change in MODE or other specified condition is required to
comply with Required Compensatory Measures, the unit may enter a
MODE or other specified condition in which another TRMS becomes
applicable. In this case, the (continued)
TRMS Applicability B 3.0 Brunswick Unit 2 B 3.0-3 Revision No. 23 BASES TRMS 3.0.2 Completion Times of the associated Required Compensatory (continued) Measures would apply from the point in time that the new TRMS becomes applicable and the COMPENSATORY MEASURES
Condition(s) are entered.
TRMS 3.0.3 Not used.
TRMS 3.0.4 TRMS 3.0.4 establishes limitations on changes in MODES or other specified conditions in the Applicability when a TRMS is not met. It
precludes placing the unit in a MODE or other specified condition stated
in that Applicability (e.g., Applicability desired to be entered) when the
following exist:
- a. Unit conditions are such that the requirements of the TRMS would not be met in the Applicability desired to be entered; and b. Continued noncompliance with the TRMS requirements, if the Applicability were entered, would result in the unit being required
to exit the Applicability desired to be entered to comply with the
Required Compensatory Measures.
Compliance with Required Compensatory Measures that permit
continued operation of the unit for an unlimited period of time in a MODE
or other specified condition provides an acceptable level of safety for
continued operation. This is without regard to the status of the unit before
or after the MODE change. Therefore, in such cases, entry into a MODE
or other specified condition in the Applicability may be made in
accordance with the provisions of the Required Compensatory Measures.
The provisions of this Specification should not be interpreted as
endorsing the failure to exercise the good practice of restoring systems or
components to OPERABLE status before unit startup.
The provisions of TRMS 3.0.4 shall not prevent changes in MODES or
other specified conditions in the Applicability that are required to comply
with COMPENSATORY MEASURES. In addition, the provisions of
TRMS 3.0.4 shall not prevent changes in MODES or other specified
conditions in the Applicability that result from any unit shutdown.
(continued)
TRMS Applicability B 3.0 Brunswick Unit 2 B 3.0-4 Revision No. 23 BASES TRMS 3.0.4 Exceptions to TRMS 3.0.4 are stated in the individual Tests.
(continued) Exceptions may apply to all the COMPENSATORY MEASURES or to a specific Required Compensatory Measure of a TRMS.
Tests do not have to be performed on the associated inoperable
equipment (or on variables outside the specified limits), as permitted by
TR 3.0.1. Therefore, changing MODES or other specified conditions
while in a COMPENSATORY MEASURES Condition, either in
compliance with TRMS 3.0.4 or where an exception to TRMS 3.0.4 is
stated, is not a violation of TR 3.0.1 or TR 3.0.4 for those Tests that do
not have to be performed due to the associated inoperable equipment.
However, TRs must be met to ensure OPERABILITY prior to declaring
the associated equipment OPERABLE (or variable within limits) and
restoring compliance with the affected TRMS.
TRMS 3.0.5 TRMS 3.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been removed from service or declared inoperable to comply with COMPENSATORY MEASURES. The
sole purpose of this TRMS is to provide an exception to TRMS 3.0.2 (e.g.,
to not comply with the applicable Required Compensatory Measure(s)) to
allow the performance of TRs to demonstrate:
- a. The OPERABILITY of the equipment being returned to service; or
- b. The OPERABILITY of other equipment.
The administrative controls ensure the time the equipment is returned to
service in conflict with the requirements of the COMPENSATORY
MEASURES is limited to the time absolutely necessary to perform the
allowed TRs. This TRMS does not provide time to perform any other
preventive or corrective maintenance.
An example of demonstrating the OPERABILITY of the equipment being
returned to service is taking an inoperable channel or trip system out of
the tripped condition after it has been tripped to comply with Required
Compensatory Measures since it must be untripped to perform the TRs.
An example of demonstrating the OPERABILITY of other equipment is
taking an inoperable channel or trip system out of the tripped condition to
prevent the trip function from (continued)
TRMS Applicability B 3.0 Brunswick Unit 2 B 3.0-5 Revision No. 23 BASES TRMS 3.0.5 occurring during the performance of a TR on another channel in the (continued) other trip system. A simila r example of demonstrating the OPERABILITY of other equipment is taking an inoperable channel or trip system out of
the tripped condition to permit the logic to function and indicate the
appropriate response during the performance of a TR on another channel
in the same trip system.
TR Applicability B 3.0 Brunswick Unit 2 B 3.0-6 Revision No. 23 B 3.0 TEST REQUIREMENT (TR) APPLICABILITY
BASES TRs TR 3.0.1 through TR 3.0.4 establish the general requirements applicable to all TRMSs and apply at all times, unless otherwise stated.
TR 3.0.1 TR 3.0.1 establishes the requirement that TRs must be met during the MODES or other specified conditions in the Applicability for which the
requirements of the TRMS apply, unless otherwise specified in the
individual TRs. This TRMS is to ensure that Tests are performed to verify
the OPERABILITY of systems and components, and that variables are
within specified limits. Failure to meet a Test within the specified
Frequency, in accordance with TR 3.0.2, constitutes a failure to meet a
TRMS.
Systems and components are assumed to be OPERABLE when the
associated TRs have been met. Nothing in this TRMS, however, is to be
construed as implying that systems or components are OPERABLE
when:
- a. The systems or components are known to be inoperable, although still meeting the TRs; or b. The requirements of the Test(s) are known to be not met between required Test performances.
Tests do not have to be performed when the unit is in a MODE or other
specified condition for which the requirements of the associated TRMS
are not applicable, unless otherwise specified.
Tests, including Tests invoked by Required Compensatory Measures, do
not have to be performed on inoperable equipment because the
COMPENSATORY MEASURES define the remedial measures that apply.
Tests have to be met and performed in accordance with TR 3.0.2, prior to
returning equipment to OPERABLE status.
(continued)
TR Applicability B 3.0 Brunswick Unit 2 B 3.0-7 Revision No. 23 BASES TR 3.0.1 Upon completion of maintenance, appropriate post maintenance testing is (continued) required to declare equipment OPERABLE. This includes ensuring applicable Tests are not failed and their most recent performance is in
accordance with TR 3.0.2. Post maintenance testing may not be possible
in the current MODE or other specified conditions in the Applicability due
to the necessary unit parameters not having been established. In these
situations, the equipment may be considered OPERABLE provided
testing has been satisfactorily completed to the extent possible and the
equipment is not otherwise believed to be incapable of performing its
function. This will allow operation to proceed to a MODE or other
specified condition where other necessary post maintenance tests can be
completed.
TR 3.0.2 TR 3.0.2 establishes the requirements for meeting the specified Frequency for Tests and any Required Compensatory Measure with a
Completion Time that requires the periodic performance of the Required
Compensatory Measure on a "once per..." interval.
TR 3.0.2 permits a 25% extension of the interval specified in the
Frequency. This extension facilitates Test scheduling and considers plant
operating conditions that may not be suitable for conducting the Test (e.g., transient conditions or other ongoing Test or maintenance
activities).
The 25% extension does not significantly degrade the reliability that
results from performing the Test at its specified Frequency. This is based
on the recognition that the most probable result of any particular Test
being performed is the verification of conformance with the TRs.
As stated in TR 3.0.2, the 25% extension also does not apply to the initial
portion of a periodic Completion Time that requires performance on a "once per..." basis. The 25% extension applies to each performance after
the initial performance. The initial performance of the Required
Compensatory Measure, whether it is a particular Test or some other
remedial action, is considered a single compensatory measure with a
single Completion Time. One reason for not allowing the 25% extension
to this Completion (continued)
TR Applicability B 3.0 Brunswick Unit 2 B 3.0-8 Revision No. 23 BASES TR 3.0.2 Time is that such a compensatory measure may verify that no loss of (continued) function has occurred by checking the status of redundant or diverse components or accomplishes the function of the inoperable equipment in
an alternative manner.
The provisions of TR 3.0.2 are not intended to be used repeatedly merely
as an operational convenience to extend Test intervals (other than those
consistent with refueling intervals) or periodic Completion Time intervals
beyond those specified.
TR 3.0.3 TR 3.0.3 establishes the flexibility to defer declaring affected equipment inoperable or an affected variable outside the specified limits when a Test
has not been completed within the specified Frequency. A delay period
of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to perform the Test.
TR 3.0.3 also provides a time limit for completion of Tests that become
applicable as a consequence of MODE changes imposed by Required
Compensatory Measures.
(continued)
TR Applicability B 3.0 Brunswick Unit 2 B 3.0-9 Revision No. 23 BASES TR 3.0.3 Failure to comply with specified Frequencies for TRs is expected to be an (continued) infrequent occurrence. Use of the delay period established by TR 3.0.3 is a flexibility which is not intended to be used as an operational
convenience to extend Test intervals.
If a Test is not completed within the allowed delay period, then the
equipment is considered inoperable or the variable is considered outside
the specified limits and the Completion Times of the Required
Compensatory Measures for the applicable TRMS Conditions begin
immediately upon expiration of the delay period. If a Test is failed within
the delay period, then the equipment is inoperable, or the variable is
outside the specified limits and the Completion Times of the Required
Compensatory Measures for the applicable TRMS Conditions begin
immediately upon the failure of the Test.
Completion of the Test within the delay period allowed by this TRMS, or
within the Completion Time of the COMPENSATORY MEASURES, restores compliance with TR 3.0.1.
TR 3.0.4 TR 3.0.4 establishes the requirement that all applicable TRs must be met before entry into a MODE or other specified condition in the Applicability.
This TRMS ensures that system and component OPERABILITY
requirements and variable limits are met before entry into MODES or
other specified conditions in the Applicability for which these systems and
components ensure safe operation of the unit.
However, in certain circumstances failing to meet a TR will not result in
TR 3.0.4 restricting a MODE change or other specified condition change.
When a system, subsystem, division, component, device, or variable is
inoperable or outside its specified limits, the associated TR(s) are not
required to be performed, per TR 3.0.1, which states that Tests do not
have to be performed on inoperable equipment. When equipment is
inoperable, TR 3.0.4 does not apply to the associated TR(s) since the
requirement for the TR(s) to be performed is removed. Therefore, failing
to perform the Test(s) within the specified Frequency does not result in a (continued)
TR Applicability B 3.0 Brunswick Unit 2 B 3.0-10 Revision No. 23 BASES TR 3.0.4 TR 3.0.4 restriction to changing MODES or other specified conditions of (continued) the Applicability. However, since the TRMS is not met in this instance, TRMS 3.0.4 will govern any restrictions that may (or may not) apply to
MODE or other specified condition changes.
The provisions of TR 3.0.4 shall not prevent changes in MODES or other
specified conditions in the Applicability that are required to comply with
COMPENSATORY MEASURES. In addition, the provisions of TR 3.0.4
shall not prevent changes in MODES or other specified conditions in the
Applicability that result from any unit shutdown.
The precise requirements for performance of TRs are specified such that
exceptions to TR 3.0.4 are not necessary. The specific time frames and
conditions necessary for meeting the TRs are specified in the Frequency, in the Test, or both. This allows performance of Tests when the
prerequisite condition(s) specified in a Test procedure require entry into
the MODE or other specified condition in the Applicability of the
associated TRMS prior to the performance or completion of a Test. A
Test that could not be performed until after entering the TRMS
Applicability would have its Frequency specified such that it is not "due" until the specific conditions needed are met. Alternately, the Test may be
stated in the form of a Note as not required (to be met or performed) until
a particular event, condition, or time has been reached. Further
discussion of the specific formats of TRs' annotation is found in TRMS
Section 1.4, Frequency.
Control Rod Drive Housing Support B 3.1 Brunswick Unit 2 B 3.1-1 Revision No. 23 B 3.1 CONTROL ROD DRIVE HOUSING SUPPORT
BASES The control rod housing support restricts the outward movement of a control rod to less than
3 inches in the event of a housing failure. The amount of rod reactivity which could be added by
this small amount of rod withdrawal is less than a normal withdrawal increment and will not contribute to any damage to the primary cool ant system. The support is not required when there is no pressure to act as a driving force to rapidly eject a drive housing.
Brunswick Unit 2 B 3.2-1 Revision No. 23 B 3.2 Not used.
Control Rod Block Instrumentation B 3.3 Brunswick Unit 2 B 3.3-1 Revision No. 23 B 3.3 CONTROL ROD BLOCK INSTRUMENTATION
BASES The Control Rod Block Functions are provided with the trip logic arranged so that a trip in any
one of the inputs will result in a rod block.
Specified test intervals and allowed out-of-service times were established based on the
reliability analyses documented in GE reports NEDC-30851P-A, Supplement 1, "Technical
Specification Improvement Analysis for BWR Control Rod Block Instrumentation,"
October 1988, NEDC-32410P-A, "Nuclear Measurement Analysis and Control Power Range
Neutron Monitor (NUMAC-PRNM) Retrofit Plus Option III Stability Trip Function," October 1995, and NEDC-32410P-A, Supplement 1, "Nuclear Measurement Analysis and Control Power
Range Neutron Monitor (NUMAC PRNM) Plus Option III Stability Trip Function,"
November 1997.
CHANNEL CALIBRATIONS of the Average Power Range Monitors Functions 1.a and 1.d are
electronic.
Accident Monitoring Instrumentation B 3.4 Brunswick Unit 2 B 3.4-1 Revision No. 60 B 3.4 ACCIDENT MONITORING INSTRUMENTATION
BASES The OPERABILITY of the post-accident monitoring instrumentation ensures that sufficient
information is available on selected plant param eters to monitor and assess important variables following an accident. This capability is consistent with the recommendations of Regulatory
Guide 1.97, "Instrumentation for Light Water-Cooled Nuclear Power Plants to Assess Plant
Conditions During and Following an Accident," December 1975, and NUREG-0578, "TMI-2
Lessons Learned Task Force Status Report and Short-Term Recommendations."
To support removal to the Drywell and Suppression Chamber H 2 and O 2 Analyzer from the Technical Specifications, the H 2 portion of the analyzer will be maintained as Regulatory Guide 1.97, Category 3, instrumentation. The O 2 portion of the analyzer will be maintained as Regulatory Guide 1.97, Category 2, instrumentation. However, consistent with the rulemaking
to revise 10 CFR 50.44 (i.e., the final rule published in 68 FR 54123) neither the H 2 portion or the O 2 portion of the analyzer need to be qualified in accordance with 10 CFR 50.49. Rather, as committed to in Reference 1 and approved in Reference 2, the Drywell and Suppression
Chamber H 2 and O 2 Analyzer will be capable of diagnosing beyond design-basis accidents.
The H 2 and O 2 portions of each overall Drywell and Suppression Chamber H 2 and O 2 Analyzer are primarily separate from one another such that there are many failure modes that would only result in either the H 2 or O 2 portion of the system being inoperable and not affect the operability of the other portion of the overall analyzer. Each portion has a dedicated analyzer such that
each overall Drywell and Suppression Chamber H 2 and O 2 Analyzer has internal to it an H 2 analyzer and an O 2 analyzer. TRM Table 3.4-2 lists the Analyzers as applicable instruments; each of these analyzers provides an output to both a front panel display on the analyzer and to
a recorder. Either of these indications may be used to satisfy the monitoring criteria should the
other experience a failure, assuming accuracy is maintained.
One channel of Turbine Building or Stack Ventilation Monitoring consists of all three ranges (low, mid, and high) of the monitoring system.
REFERENCES
- 1. Letter from Cornelius J. Gannon to the U. S. Nuclear Regulatory Commission (Serial:
BSEP 04-0098), "Request for License Amendments - Deletion of Hydrogen and Oxygen
Analyzer Requirements Consolidated Li ne Item Improvement Process (TSTF-447, Revision 1)," dated July 26, 2004. 2. Letter from U.S. Nuclear Regulator Commission to Mr. C. J. Gannon, "Issuance of Amendments RE: Elimination of Require ments for Hydrogen and Oxygen Monitors Using The Consolidated Line Item Improvement Process (TAC Nos. MC3866 and
MC3867)," dated February 2, 2005.
Chloride Intrusion Monitors B 3.5 Brunswick Unit 2 B 3.5-1 Revision No. 23 B 3.5 CHLORIDE INTRUSION MONITORS
BASES The chloride intrusion monitors provide adequate warning of any leakage in the condenser or
hotwell so that actions can be taken to mitigate the consequences of such intrusion in the
reactor coolant system. With only a minimum number of instruments available, increased
sampling frequency provides adequate information for the same purpose. Chloride intrusion
can be detected if any of the Functions in Table 3.5-1 have their required channels OPERABLE.
Bus Power Monitors B 3.6 Brunswick Unit 2 B 3.6-1 Revision No. 31 B 3.6 BUS POWER MONITORS
BASES The Emergency Core Cooling System (ECCS) and Reactor Core Isolation Cooling (RCIC)
System Bus Power Monitors are provided to monito r the availability of power to logic system.
The bus power monitors are required to be O PERABLE when the instrumentation they support is required to be OPERABLE (e.g., bus power monitors associated with High Pressure Coolant
Injection (HPCI) System and RCIC System inst rumentation are required to be OPERABLE in MODE 1 and MODES 2 and 3 with reactor steam dome pressure > 150 psig to support the
HPCI and RCIC functions and are also required to be OPERABLE in MODES 1, 2, and 3 to
support the primary containment isolation functions associated with HPCI and RCIC
instrumentation). The RHR, Core Spray System, Low Pressure Coolant Injection (Residual
Heat Removal System), HPCI and RCIC System Bus Power Monitors each consist of one
instrument channel per bus. This instrumentation provides a monitoring/alarm function only.
The ECCS and RCIC System Bus Power Monitors will be tested at regularly scheduled
intervals.
The TRMS is modified by a Note to indicate that the annunciator function may be removed from
operation for performance of troubleshooting for up to 30 minutes provided no work is being
performed on the associated power supplies. Upon completion of the troubleshooting, or
expiration of the 30 minute allowance, the annunciator must be returned to operation or the
applicable Condition entered and Required Compensatory Measures taken. Appropriate
compensatory actions should be determined and implemented during the loss of annunciator
function. Since the loss of detection capability is of short duration, no work is allowed on the
associated power supplies, and appropriate compensatory actions are determined and
implemented, there is a minimal increase in the probability of an undetected loss of ECCS
power during the 30 minute troubleshooting allowance.
ADS Inhibit Switch B 3.7 Brunswick Unit 2 B 3.7-1 Revision No. 23 B 3.7 AUTOMATIC DEPRESSURIZATION SYSTEM (ADS) INHIBIT SWITCH
BASES ADS Inhibit Switches are provided to permit the operator to prevent automatic actuation of the
ADS. Both switches must be actuated to prevent automatic blowdown. Automatic
depressurization may not be appropriate if reactor vessel level is recovering or during ATWS
events. During ATWS events, depressurization would lead to power increases from cold water
injection, void collapse, and boron dilution. In MODE 1 and in MODES 2 and 3 with reactor
steam dome pressure > 150 psig, the ADS Inhibit Switches must be in the automatic position to
ensure that ADS automatic actuation capability is maintained.
Suppression Chamber Water Temperature Instrumentation B 3.8 Brunswick Unit 2 B 3.8-1 Revision No. 31 B 3.8 SUPPRESSION CHAMBER WATER TEMPERATURE INSTRUMENTATION
BASES The suppression chamber water temperature moni toring system performs a dual function. It provides for accident monitoring as recommended by Regulatory Guide 1.97. This system is also designed to meet the acceptance criteria of NUREG-0661, Appendix A in monitoring
average suppression chamber water temperature during normal operating conditions.
The TRMS is modified by a Note to indicate that the annunciator function may be removed from
operation for performance of troubleshooting for up to 30 minutes provided the associated
function maintains monitoring capability. Upon completion of the troubleshooting, or expiration
of the 30 minute allowance, the annunciator must be returned to operation or the applicable
Condition entered and Required Compensatory Measures taken. Appropriate compensatory
actions should be determined and implemented during the loss of annunciator function. This
Note is based on the availability of the associated monitor and appropriate compensatory
actions to identify changes in suppression pool temperature. The monitor availability and
compensatory actions ensure that the 30 minute troubleshooting allowance does not
significantly reduce the probability of identifying changing conditions to allow appropriate
response.
Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-1 Revision No. 47 B 3.9 SEISMIC MONITORING INSTRUMENTATION
BASES BACKGROUND Seismic Monitoring Instrumentati on is required to promptly determine the response to nuclear power plant features important to safety in the event
of an earthquake. This capability is required to allow for a comparison of
the measured response to that used in the design basis of the plant.
Comparison of this data is needed to determine whether the plant can
continue to be operated safely as required by 10 CFR 100, Appendix A (Ref. 2).
Reference 2 requires that two earthquake levels be considered in the
design of safety related structur es, systems and components (SSCs).
Consequently, the Seismic Monitoring Instrumentation is designed to
monitor for vibratory ground motions exceeding either of these levels.
One of these levels, the Operating Basis Earthquake (OBE), is that
earthquake which could reasonably be expected to occur at the site
during the operating life of the plant. SSCs necessary for continued plant
operation without undue risk to the health and safety of the public are
designed to remain functional following an OBE. The other earthquake
level, the Safe Shutdown Earthquake (SSE), is that earthquake which is
based upon the maximum (i.e., most severe) earthquake potential for the
area in which the plant is sited. SSCs necessary to assure the integrity of
the reactor pressure boundary, the capability to shutdown the reactor (and maintain it in a shutdown condition), and the capability to prevent or
mitigate the consequences of accidents which could result in potential
offsite exposures are designed to remain functional following an SSE.
The Seismic Monitoring Instrumentation consists of passive peak shock
recorders, triaxial accelerometers, and a central recording panel. The
central recorder panel is located in the Main Control Room and has a
central recorder for seismic data acquisition and storage, a personal
computer, monitor, a printer for display of recorded data, an annunciator
instrument that provides local indicator lights and control room indication, and a 25 minute uninterruptible power supply. Lights on the panel identify
system triggering and indicate if the OBE has been exceeded based on
an analysis of the data collected in the basement of the Reactor Building (elevation -17 feet).
The earthquake data is collected in three orthogonal directions which
coincide with the major axes of the analytical model used in the seismic
analysis of the plant structures. The central recorder is connected to the
triaxial accelerometers.
(continued)
Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-2 Revision No. 47 BASES BACKGROUND When a very low "g" level threshold (0.01 g) has been exceeded at the (continued) reactor building accelerometer (elevation -17 foot), the system alerts the operator by actuating an event indication annunciator in the main control
room and initiates the recording functions of all the accelerometers until
termination of the event.
There are two triaxial accelerometers which input to the central recorder, each of which measures the absolute acceleration as a function of time in
three orthogonal directions. These accelerometers are located in the
reactor building (elevation -17 feet) and near the top of the containment
structure (elevation +89 feet).
During a ground motion event, where the acceleration exceeds the
seismic threshold, seismic data is stored in the central recorder which can
be later viewed and printed by means of the personal computer, monitor, and printer located at the panel. The recorded seismic data is then used
to facilitate the analysis of structural loads during the seismic event.
Passive monitoring is provided by three triaxial peak shock recorders
which record the absolute peak acceleration in three orthogonal directions
coinciding with the major axes of the analytical model of the structure.
These peak shock recorders are located in the equipment drain tank area
of reactor building basement (elevation -17 feet), the reactor building
RHR heat exchanger support (elevation +20 feet), and the reactor
building refueling area (elevation +117 feet).
APPLICABLE The function of the Seismic Monitoring Instrumentation is to monitor DESIGN BASES seismic activity above a low "g" level, and to record seismic data for comparison to design bases spectra. The Brunswick Plant was originally
constructed with seismic monitoring instrumentation which corresponded
with the recommendations of NRC Safety Guide 12. Although the
Brunswick Plant's licensing basis remains Safety Guide 12, the current
instrumentation is designed to meet the requirements of 10 CFR 100, Appendix A (Ref. 2) and is consistent with specific portions of the
recommendations of Regulatory Guide 1.12, "Instrumentation for
Earthquakes" (Ref. 3).
For Brunswick Plant, the site ground response spectra are based on
earthquakes with peak horizontal ground accelerations of 0.08 g and
0.16 g, for an OBE and an SSE respectively. The vertical ground
acceleration is assumed to be two-thirds of the respective horizontal
acceleration. SSCs designated Seismic Category I are designed to
remain functional following an SSE.
(continued)
Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-3 Revision No. 47 BASES APPLICABLE When an earthquake occurs, it may not be known immediately how DESIGN BASES severe the effects of the earthquake are on plant equipment. The triaxial (continued) accelerometers provide time-history data on the seismic input to containment. The passive triaxial peak shock recorders record peak
event acceleration information that can be used to supplement the data
gathered by the triaxial accelerometers. Response spectra are generated
from the time-history data at the control station in the main control room
for comparison to design basis data.
The Seismic Monitoring Instrumentation only provides information
regarding seismic activity during a seismic event and is not considered in
any design basis accident or transient nor does it provide any function to
mitigate an accident or its consequences.
TRMS Seismic Monitoring Instrumentation is required to promptly determine the magnitude of a seismic event and evaluate the response of those
features important to safety. The Seismic Monitoring Instrumentation
listed in Table 3.9-1, including the associated main control room alarm, must be OPERABLE to ensure that the capability of detecting and
comparing the observed spectra response of a seismic event to that used
in the design basis for the plant is maintained.
APPLICABILITY The potential for a seismic event exists at all times. For example, an
earthquake could occur while moving irradiated fuel in the secondary
containment with the core fully offloaded. Therefore, this TRMS is
applicable even when fuel is not loaded in the core.
COMPENSATORY A Note has been provided to modify the COMPENSATORY MEASURES MEASURES related to seismic monitoring instruments. Section 1.3, Completion Times, specifies that once a Condition has been entered, subsequent
divisions, subsystems, components, or variables expressed in the
Condition discovered to be inoperable or not within limits will not result in
separate entry into the Condition. Section 1.3 also specifies that
Required Compensatory Measures of the Condition continue to apply for
each additional failure, with Completion Times based on initial entry into
the Condition. However, the Required Compensatory Measures for
inoperable seismic monitoring instrumentation provide appropriate
compensatory measures for separate inoperable instruments. As such, a
Note has been provided that allows separate Condition entry for each
inoperable seismic monitoring instrument.
(continued)
Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-4 Revision No. 47 BASES COMPENSATORY A.1 MEASURES (continued) With one or more seismic monitoring instruments inoperable, the ability to monitor vibratory ground motion and determine its effects on safety
related SSCs is degraded. Because of the diversity of sensor locations
available to provide monitoring signals, an allowable out of service time of
31 days is acceptable to permit restoration of any inoperable instrument
to OPERABLE status.
B.1 If the seismic monitoring instrument is not restored to OPERABLE status, plant operation may continue provided a Special Report outlining the
cause of the inoperability and the plans for restoring the instrument to
OPERABLE status is prepared and submitted to the NRC within 14 days.
The 14 day Completion Time provides an appropriate period of time to
develop the recovery plan and is consistent with the original licensing
basis reporting requirements for the seismic monitoring instrumentation.
C.1, C.2, and C.3 If a seismic event having a vibratory ground motion of 0.08 g or greater
occurs at the site, actuated instruments must be restored to a ready
status to permit monitoring of any subsequent ground motion.
Additionally, the data collected from the instruments must be reviewed
against the dynamic stress assumptions in the plant design basis.
Some seismic instruments (i.e., the passive triaxial peak shock
recorders), once actuated, are not capable of recording a subsequent
event, rendering them inoperable until they have been reset or replaced (i.e., replacement of the recording plates). Since seismic events are typically followed by several aftershocks, it is necessary to return
actuated instruments to an OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (Required
Compensatory Measure C.1) to assure that the severity of subsequent aftershocks can be evaluated. Seismic monitoring instrument calibration
may also be affected by the sudden ground motion of an earthquake. An
instrument's calibration may have shifted outside of allowable limits, depending on the severity of the seismic event. Therefore, Required
Compensatory Measure C.2 requires that a CHANNEL CALIBRATION
per TR 3.9.3 be performed on each actuated instrument within 10 days
following the initiating event (e.g., the initiating seismic event and
associated aftershocks) to verify that the affected instruments are still
properly calibrated.
(continued)
Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-5 Revision No. 47 BASES COMPENSATORY C.1, C.2, and C.3 (continued)
MEASURES (continued) In order to validate the analytical model and to determine the magnitude of the stresses that were applied to safety related SSCs during the event, the data from the seismic monitoring instruments must be retrieved and
analyzed. The information derived from this analysis must be
incorporated into a Special Report per Required Compensatory
Measure C.3. The Special Report shall describe the magnitude and
frequency spectrum of the event and describe the effect of the event on
safety related SSCs at the station. The data analysis and Special Report
must be completed within 14 days of the initiating event.
Condition C is modified by a Note requiring Required Compensatory
Measures C.2 and C.3 to be completed whenever the Condition is
entered. The Note emphasizes the need to perform the evaluation of the
effects of the seismic event. Restoration of instrument OPERABILITY
alone per Required Compensatory Measure C.1 is insufficient because
higher than analyzed stresses may have occurred and may have affected
safety-related SSCs. Additionally, the Note ensures that the calibration of
actuated seismic instrumentation has not been affected by the event.
TEST As noted at the beginning of the TRs, the TRs for each Seismic REQUIREMENTS Monitoring Instrumentation Func tion are located in the TRs column of Table 3.9-1.
TR 3.9.1 Performance of the CHANNEL CHECK once every 31 days ensures that
a gross failure of instrumentation has not occurred. A CHANNEL CHECK
is normally a comparison of the parameter indicated on one instrument to
a similar parameter on other instruments. It is based on the assumption
that instruments monitoring the same parameter should read
approximately the same value. Significant deviations between the
instruments could be an indication of excessive instrument drift or
something even more serious. A CHANNEL CHECK will detect gross
instrument failure; thus, it is key to verifying the instrumentation continues
to operate properly between each CHANNEL CALIBRATION. This
CHANNEL CHECK is fulfilled by the absence of a system health warning
indication.
Agreement criteria are determined by the plant staff, based on a
combination of the instrument uncertainties, including indication and
readability. If an instrument is outside the criteria, it may be an indication
that the instrument has drifted outside its limit.
(continued)
Seismic Monitoring Instrumentation B 3.9 Brunswick Unit 2 B 3.9-6 Revision No. 47 BASES TEST TR 3.9.1 (continued)
REQUIREMENTS (continued) The Frequency is based on operating experience that demonstrates instrument failure is rare and is consistent with the recommendations of
Reference 3. The CHANNEL CHECK supplements less formal, but more
frequent, checks of instruments during normal operational use of the
displays associated with the instruments required by the TRMS.
TR 3.9.2 A CHANNEL FUNCTIONAL TEST is performed on each required
instrument to ensure that the instrument channel will perform the intended
function. A successful test of the required contact(s) of an instrument
channel relay may be performed by the verification of the change of state
of a single contact of the relay. This clarifies what is an acceptable
CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because
all of the other required contacts of the relay are verified by other
Technical Specifications and non-Technical Specifications tests at least
once per refueling interval with applicable extensions. Any setpoint
adjustment shall be consistent with the assumptions of the current plant
specific setpoint methodology.
The Frequency of 184 days is consistent with the recommendations of
Reference 3.
TR 3.9.3 CHANNEL CALIBRATION is a complete check of the instrument loop and
the sensor. This test verifies the instrument responds to the measured
parameter within the necessary range and accuracy. CHANNEL
CALIBRATION leaves the instrument adjusted to account for instrument
drifts between successive calibrations, consistent with the plant specific
setpoint methodology.
The Frequency of 24 months is consistent with the recommendations of
Reference 3.
REFERENCES 1. UFSAR Section 3.7.4. 2. 10 CFR 100, Appendix A.
- 3. Regulatory Guide 1.12, "Instrumentation for Earthquakes."
Intake Canal High Water Level Instrumentation B 3.10 Brunswick Unit 2 B 3.10-1 Revision No. 31
B 3.10 INTAKE CANAL HIGH WATER LEVEL INSTRUMENTATION
BASES To ensure that operators are alerted to a rising water level in the intake canal, a level indicator
is provided with a sensor installed in the Class I service water intake structure and a recording
indicator in the control room. The level indicator will provide an alarm in the control room when
water in the intake canal reaches elevation 14.5 ft.
The TRMS is modified by a Note to indicate that the annunciator function may be removed from
operation for performance of troubleshooting for up to 30 minutes provided a method to monitor
water level is maintained. Upon completion of the troubleshooting, or expiration of the 30
minute allowance, the annunciator must be returned to operation or the applicable Condition
entered and Required Compensatory Measures taken. Appropriate compensatory actions
should be determined and implemented during the loss of annunciator function. This Note is
based upon appropriate compensatory actions being taken to identify changes in the intake
canal level during the 30 minute troubleshooting allowance.
Primary Containment Isolation Instrumentation B 3.11 Brunswick Unit 2 B 3.11-1 Revision No. 23 B 3.11 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION
BASES This specification ensures the effectiveness of the instrumentation by prescribing the trip settings for isolation of the reactor systems. When necessary, one channel may be inoperable
for brief intervals to conduct required testing. The setpoints are established at a level away
from the normal operating range to prevent inadver tent actuation of the systems involved.
Specified test intervals and allowed out-of-service times were established based on the
reliability analysis documented in GE report NEDC-31677P-A, "Technical Specification
Improvement Analysis for BWR Isolation Actuati on Instrumentation," July 1990, as modified by 0G90-579-32A, Letter to Millard L. Wohl (NRC) from W. P Sullivan and J. F. Klapproth (GE),
"Implementation Enhancements to Technical Specification Changes Given in Isolation Actuation
Instrumentation Analysis," June 25, 1990 and supplemented by GE letter report
GENE-A31-00001-02, "assessment of Brunswick Nuclear Plant Isolation Actuation
Instrumentation Against NEDC-31677P-A Bounding Analyses," August 1994.
The Main Steam Line Tunnel Temperature-High (except for Main Steam Isolation Valve Pit
instruments) Function and the Turbine Building Area Temperature-High Function are each
capable of isolating valves in Group 1 except for valves B32-F019 and B32-F020.
CREV System Instrumentation B 3.12 Brunswick Unit 2 B 3.12-1 Revision No. 57 B 3.12 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM INSTRUMENTATION BASES BACKGROUND One of the principal design objectives of the Control Building Heating, Ventilation and Air
Conditioning (CBHVAC) System is to permit continuous occupancy of the control room
emergency zone under normal operating conditions and under the postulated design basis
events throughout the life of the plant. The Control Building HVAC System must function to
provide protection to the operators for three type events: a radiation event, up to and including
a Design Basis Accident (e.g., Main Steam Line Break [MSLB] Accident, Refueling Accident, Control Rod Drop Accident, or Loss of Coolant Accident [LOCA]), a toxic gas event (complete
rupture of the 55 ton chlorine tank car located near the service water building, or a slow leak
lasting for an extended period of time), and an ex ternal smoke event. These events form the basis for the design of the Control Room Emer gency Ventilation (CREV) System function of the CBHVAC System. The radiation protection f unction of the CREV System is addressed in
Technical Specifications.
During an external smoke event, the CBHVAC Syst em is required to automatically isolate and enter the radiation/smoke protection mode on a smoke detection signal from one of the two
Control Building Intake air duct smoke detectors. Upon receipt of a smoke detection signal, the
CBHVAC System is automatically realigned to the emergency mode of operation. The normal
fresh air inlet closes, and, at approximately the same time, the emergency air filtration units
begin operation, recirculating control room air and providing filtered makeup air to minimize
smoke build-up and provide positive pre ssure in the control room envelope.
In the event of a chlorine release, the CBHVAC System enters a full recirculation mode (chlorine protection mode), with no outdoor air intake. The emergency filtration trains do not start, since
they do not effectively remove chlorine and may be damaged by the presence of chlorine.
Protection for chlorine gas events "overrides" any concurrent, ongoing, and any subsequent
radiation or smoke initiation signals. The override design offers protection to operations
personnel in the control room by providing protection against potentially fatal chlorine gas
releases. This protection is required at any time the chlorine tank car is within the exclusion
area.
The CREV System is designed to meet the criteria of General Design Criterion (GDC) 19 (Reference 1). In addition, the system is designed using the guidance of Regulatory
Guide 1.95, Revision 1 (Reference 2). Commitments have also been made to design chlorine
detection and isolation logic to single failure criteria, with approved exceptions (Reference 3, Section 3.6).
(continued)
CREV System Instrumentation B 3.12 Brunswick Unit 2 B 3.12-2 Revision No. 23 BASES (continued)
TRMS OPERABILITY of the CREV System instrumentat ion ensures that the control room operators will be protected from hazards external to the control room, consistent with the assumptions in
the various analyses, through the prompt detection and initiation of the necessary protective
actions of the system.
APPLICABILITY The instrumentation associated with the chlorine protection mode of the CREV System is
required to be OPERABLE to automatically detect and initiate the internal recirculation mode of
operation any time the chlorine tank car is within the exclusion area.
The instrumentation associated with the external smoke protection function of the CREV
System is required to be OPERABLE to automatic ally detect and initiate the radiation/smoke protection mode of operation during the same conditions as the radiation protection function.
This ensures that habitability of the control room is maintained during times when a radiological
release could potentially occur.
COMPENSATORY MEASURES Chlorine Protection
The chlorine detection/isolation instrumentation is organized into two trip systems, with one trip
system (remote) located near the chlorine tank car and the other located in the control building
intake plenum (local). Each trip system contains two trip subsystems, with two detectors (one from each division) in each trip subsystem. Both trip subsystems in each trip system are
required to be OPERABLE any time the chlorine tank car is within the exclusion area to ensure
adequate protection for the control room under postulated toxic gas events.
The chlorine detectors in each trip system are arranged in a one-out-of-two taken-twice
configuration. One detector from each of the trip subsystems in a trip system must actuate to
initiate the automatic detection/isolation function. The loss of a single chlorine detector means
that the CREV System reliability is reduced because a single failure in the remaining
OPERABLE trip subsystem detector could result in reduced or lost system capability. The 7 day
out of service time is based on the low probability of a design basis chlorine gas event and a
single active failure occurring during this time period, and the capability of the remaining
detectors to provide the required isolation capabilities. The out of service time is consistent with
the out of service time allowed for loss of redundancy at the system level.
(continued)
CREV System Instrumentation B 3.12 Brunswick Unit 2 B 3.12-3 Revision No. 57 BASES COMPENSATORY MEASURES (continued)
The loss of both detectors in any trip subsystem means that the automatic protection function of
the chlorine detection/isolation system is lost.
Placing the CBHVAC System in the chlorine protection mode, through the use of control switches (as opposed to injection of a chlorine
injection signal) to close the appropriate dampers, ensures that the control room envelope is
protected, while at the same time allowing a valid radiation or smoke signal to initiate
appropriate protective actions. Operation in this mode is not limited in duration provided that
either trip system remains functional to ensure that the override function of the chlorine
protection mode is not lost.
Smoke Protection
Automatic detection/isolation of the control room envelope in response to an external smoke
event is dependent on the response of one of two Control Building Intake air duct smoke
detectors.
With both of the Control Building Intake air duct smoke detectors inoperable, the automatic
detection/isolation function of the external smoke protection system is lost. Placing the
CBHVAC System in the radiation/smoke protec tion mode is a suitable compensatory action to ensure that the automatic external smoke protection function is not lost.
TEST REQUIREMENTS Chlorine Protection
The CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the
entire channel will perform the intended function. The Control Building HVAC DBD (Reference 3) defines the specific actions to be satisfied by the chlorine isolation
instrumentation. The monthly frequency of the CHANNEL FUNCTIONAL TEST is consistent
with the testing frequencies performed by other utilities with this type of instrumentation.
(continued)
CREV System Instrumentation B 3.12 Brunswick Unit 2 B 3.12-4 Revision No. 23 BASES TEST REQUIREMENTS (continued)
The CHANNEL CALIBRATION of the trip units provides a check of the instrument loop and the
sensor when the sensor is replaced. The test verifies the calibration of the existing sensor prior
to removal and performs an installation calibration of the new sensor, including a complete
CHANNEL CALIBRATION with the new sensor installed, to verify the channel responds to the
measured parameter within the necessary range and accuracy. The CHANNEL CALIBRATION leaves the channel adjusted to ensure consistenc y with the system assumptions (Reference 3).
The chlorine detectors use an amperometric sensor consisting of a platinum cathode and silver
anode joined by an electrolytic salt bridge, all enclosed in a permeable membrane. This design
eliminates the majority of the maintenance required on previous detectors. The detectors have been in service at other facilities and have provided reliable service. The annual replacement
and calibration are based on a manufacturer recommendation. The adequacy of the
replacement interval has been confirmed through discussions with other utilities.
Smoke Protection
The CHANNEL FUNCTIONAL TEST for the Smoke protection instrumentation is consistent with
the testing performed in accordance with the existing fire detection instrumentation
requirements.
REFERENCES
- 1. 10 CFR 50, Appendix A, General Design Criterion 19, Control Room.
- 2. Regulatory Guide 1.95, Revision 1, Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release. 3. BNP Design Basis Document (DBD)-37, Control Building Heating, Ventilation, and Air Conditioning System.
RCS Chemistry B 3.13 Brunswick Unit 2 B 3.13-1 Revision No. 23 B 3.13 REACTOR COOLANT SYSTEM (RCS) CHEMISTRY
BASES The reactor water chemistry limits are established to prevent damage to the reactor materials in
contact with the coolant. Chloride limits are specified to prevent stress corrosion cracking of the
stainless steel. The effect of chloride is not as great when the oxygen concentration in the
coolant is low; thus, the higher limit on chlorides is permitted during full power operation. During
shutdown and refueling operations, the temperature necessary for stress corrosion to occur is
not present.
Conductivity measurements are required on a cont inuous basis since changes in this parameter are an indication of abnormal conditions. When the conductivity is within limits, the pH, chlorides, and other impurities affecting conductivity must also be within their acceptable limits.
With the conductivity outside the limits, additional samples must be examined to ensure that the
chlorides are not exceeding the limits.
The Test Requirements provide adequate assurance t hat concentrations in excess of the limits will be detected in sufficient time to take corrective action.
In order to reduce personnel radiation exposure, chemical decontamination of portions of the
Reactor Coolant System may be performed during shutdown. During the chemical
decontamination process, the injection of chemical solvents may cause the Reactor Coolant
System conductivity and chloride measurements to increase above the limits. The solvents that are selected for use in performing the chemical decontamination process are selected and
evaluated to ensure their chemical reactivity will not adversely impact components or the
structural integrity of the Reactor Coolant System. Because decontamination activities are performed at temperatures and pressures significantly less than normal operating temperatures, the chemical reactivity of these solvents will not increase the likelihood of stress corrosion
occurring nor affect those stress corrosion cracks that may already be present.
Structural Integrity 3.14 Brunswick Unit 2 B 3.14-1 Revision No. 65 B 3.14 STRUCTURAL INTEGRITY
BASES BACKGROUND The inservice inspection and testing programs for ASME Code Class 1, 2, 3, MC, and CC components ensure that the structural integrity and
operational readiness of these components will be maintained at an
acceptable level throughout the life of the plant. These programs are in accordance with Section XI of the ASME Boiler and Pressure Vessel
Code and applicable Addenda as required by 10 CFR Part 50.55a(g)
(Ref. 1) except where specific written relief has been granted by the
Commission pursuant to 10 CFR Part 50.55a(g)(6)(i).
TRMS For plant systems and components to be OPERABLE, structural integrity of these systems and components must be maintained in conformance with American Society of Mechanical Engineers (ASME) Code Section XI (Ref. 2), for those parts of a system that are subject to ASME Section XI
Code requirements.
This requirement applies to all ASME Section XI Code Class 1, 2, and 3
piping and components. In addition to piping and components, structural
support components such as pipe hangers, support steel, base plates, welds, bolts, etc. are considered part of the scope of this TRMS. Non-Section XI-Code-classed components are not part of the scope of this
TRMS.
Snubbers are not considered part of the scope of this TRMS. Snubbers
are addressed in TRMS 3.21.
For components with degraded material properties or relevant conditions as defined in ASME Section XI, the criteria for structural integrity are contained or referenced in Section XI. Alternative evaluation criteria may
be used to determine structural integrity, when approved by the NRC.
NRC expectations for structural integrity and operability of components
are described in NRC Inspection Manual 0326, Appendix C (Ref. 3). The
table below, which is found in Appendix C of NRC Inspection Manual
Chapter 0326, summarizes the NRC accepted methods available for
evaluating structural integrity of flaws in components including supports, classified as ASME Code Class 1, Class 2, and Class 3 components.
(continued)
Structural Integrity 3.14 Brunswick Unit 2 B 3.14-2 Revision No. 65 BASES TRMS (continued)
Pipe Class/
Energy ASME Code Section XI/
Construction Code NRC Approved Alternative e.g., RG approved Code Case Code Case N-513 (1) GL 90-05 Class 1/HE (2) X X Class 2/HE X X Class 2/ME (3) X X X Class 3/HE X X X Class 3/ME X X X X (1) Refer to NRC Regulatory Guide 1.147 for the latest revision acceptable to the NRC, and any conditions placed upon the code case. (2) HE - High Energy - Maximum oper ating temperature greater than 200°F or maximum operating pressure greater than 275 psig. (3) ME - Moderate Energy - Maximum operating temperature equal to or less than 200°F or maximum operating pressure equal to or less than
275 psig.
APPLICABILITY The components monitored by the Inservice Inspection Program have functions required for shutting down the reactor, maintaining the
shutdown condition, and mitigating the consequences of an accident.
Therefore, their structural integrity is required anytime there is fuel in the
reactor (i.e., MODES 1, 2, 3, 4, and 5). This requirement applies to all ASME Section XI Code Class 1, 2 ,and 3 piping and components, and to all ASME Section XI MC and CC components. This requirement does not
apply to piping and components that were designed and built to ASME
Section III Code or ANSI B31.1 requirements, that are not subject to ASME Section XI Code Class 1, 2, or 3 inservice inspection requirements (i.e., non-Code-Class components).
COMPENSATORY A Note has been provided to m odify the Compensatory Measures related MEASURES to structural integrity. Section 1.3, Completion Times, specifies once a Condition has been entered, subsequent divisions, subsystems, components or variables expressed in the Condition, discovered to be
inoperable or not within limits, will not result in separate entry into the (continued)
Structural Integrity 3.14 Brunswick Unit 2 B 3.14-3 Revision No. 65 BASES COMPENSATORY Condition. Section 1.3 also specifies Technical Requirements Manual MEASURES Required Compensatory Measures of the Condition continue to apply for (continued) each additional failure, with Completion Times based on initial entry into the Condition. However, the Technical Specification Required Actions and
TRM Required Compensatory Measures for systems provide appropriate compensatory measures for separate structural integrity conditions. As
such, a Note has been provided that allows separate Condition entry for
each structural integrity condition.
A.1 Upon initial discovery, supplemental NDE may be required to fully
characterize the degraded condition. Preliminary judgments regarding
structural integrity may be expressed considering the available
information and the expectation that a final determination of structural
integrity will result once all characterization, evaluation, and
documentation are complete.
During the time frame of these investigations, no Technical Requirements
Manual Specification is considered not met. The condition should be
immediately entered in the Corrective Action Program.
Condition A is modified by a Note, which requires that a structural
integrity evaluation must be completed.
If the indication is found to impact the structural integrity or
OPERABILITY/functionality of the component, system, or structure, or if
the evaluation of the indication has not been completed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time is deemed appropriate for providing a
reasonable amount of time to perform the necessary evaluations.
(continued)
Structural Integrity 3.14 Brunswick Unit 2 B 3.14-4 Revision No. 65 BASES COMPENSATORY A.1 (continued)
MEASURES There is no indeterminate state of operability. If, at any time, information
becomes available that negates a previous determination regarding
structural integrity, then the Technical Requirements Manual Specification
for structural integrity is considered not met and the appropriate Condition
shall be entered based on the Code Class of the affected component, system, or structure.
B.1, B.2, and B.3 When ASME Class 1 components do not meet ASME Code or
construction code acceptance standards, the requirements of an NRC
endorsed ASME Code Case, or an NRC approved alternative, then an
immediate operability determination cannot conclude a reasonable
expectation of operability exists and the affected component shall either
be isolated or the associated system, structure, or component shall be
declared inoperable and the associated TS Action statement or TRM
Required Compensatory Measure entered.
Satisfaction of Code acceptance standards is the minimum necessary for
operability of Class 1 pressure boundary components because of the
importance of the safety function being provided.
TS LCO 3.4.4, RCS Operational Leakage, does not permit any reactor
coolant pressure boundary leakage. Upon discovery of leakage from a
Class 1 pressure boundary component (pipe wall, valve body, pump
casing, etc.), the component must be immediately declared inoperable.
C.1.1, C.1.2, C.2, and C.3 When ASME Class 2 or Class 3 components do not meet ASME Code or
construction code acceptance standards, the requirements of an NRC
endorsed ASME Code Case, or an NRC approved alternative, then a
determination must be made of whether the nonconforming condition
results in a TS/TRM-required SCC or a TS/TRM-required support SSC
being inoperable. In order to determine the component is
OPERABLE/functional under an immediate operability determination, the
degradation mechanism must be readily apparent. To be readily
apparent, the degradation mechanism must be discernable from visual (continued)
Structural Integrity 3.14 Brunswick Unit 2 B 3.14-5 Revision No. 65 BASES COMPENSATORY C.1.1, C.1.2, C.2, and C.3 (continued)
MEASURES examination (such as external corrosion or wear), or there must be
substantial operating experience with the identified degradation
mechanism in the affected system. In addition, detailed non-destructive
examination data may be necessary to determine that a component is
OPERABLE/functional under an immediate operability determination.
If flaw examination and characterization, and engineering analysis, cannot be completed within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the component should be declared
inoperable as specified in Required Compensatory Measure C and the
appropriate TS Action statement or TRM Required Compensatory
Measure entered. There is no indeterminate state of operability. NRC
regulations (Ref. 1) require that the structural integrity of ASME Code
Class 1, 2, and 3 components be maintained in accordance with the
ASME Code or construction code acceptance standards. If a structural
integrity concern is discovered in a Class 2 or Class 3 component while
conducting an inservice inspection, maintenance activity, or during facility
operation, corrective measures must be taken to restore structural
integrity before continuing or resuming operation in MODES 1, 2, or 3.
The affected component must be restored to ASME Code or construction
code acceptance standards by the end of the next refueling outage.
D.1, D.2, and D.3 When ASME Class MC or Class CC components do not meet acceptance
standards, the requirements of an NRC endorsed ASME Code Case, or
an NRC approved alternative, then a determination of whether the
degraded or nonconforming condition results in a TS/TRM-required SSC
or a TS/TRM-required support SCC being inoperable/non-functional must
be made.
Structural support components are required to be OPERABLE/functional
to support operability of related support functions. Examples of structural
degradation are concrete cracking and spalling, excessive deflection or
deformation of the steel containment liner, or missing/damaged pressure
boundary bolts. If the Code Class MC or Class CC structure is degraded, the structure's capability of performing its specified function shall be
assessed. As long as the identified degradation does not result in
exceeding acceptance limits specified in applicable design codes and
standards referenced in the design basis documents, the affected
structure is either OPERABLE or functional.
(continued)
Structural Integrity B 3.14 Brunswick Unit 2 B 3.14-6 Revision No. 65 BASES COMPENSATORY D.1, D.2, and D.3 (continued)
MEASURES NRC regulations (Ref. 1) require that the structural integrity of ASME
Code Class MC and CC components be maintained in accordance with
the ASME Code or construction code acceptance standards. If a
structural integrity concern is discovered in a Class MC or CC component
while conducting an inservice inspection, maintenance activity, or during
facility operation, corrective measures must be taken to restore structural
integrity before continuing or resuming operation in MODES 1, 2, or 3.
The affected component must be restored to ASME Code or construction
code acceptance standards by the end of the next refueling outage.
E.1 If the evaluation of operability/functionality cannot be completed within the
required Completion Time, the component shall be declared
inoperable/nonfunctional and the appropriate TS LCOs and TRMS
entered. TEST TR 3.14 REQUIREMENTS The structural integrity of ASME Section XI Code Class 1, 2, 3, MC, and
CC components is ensured by the successful completion of the Inservice
Inspection Program and by visual inspections of components for evidence
of deterioration or breach of integrity. This ensures that the structural
integrity of these components will be maintained in accordance with the
provisions of the Program.
The Frequencies for the TR is defined in the Inservice Inspection
Program. The testing and frequency for components in the Inservice
Inspection Program are consistent with the requirements of References 1
and 2. (continued)
Structural Integrity B 3.14 Brunswick Unit 2 B 3.14-7 Revision No. 65 BASES (continued)
REFERENCES 1. 10 CFR 50.55a(g), Inservice Inspection Requirements. 2. ASME Code,Section XI, 2001 Edition with 2003 Addenda
- 3. NRC Inspection Manual Chapter 0326, Operability Determinations and Functionality Assessments for Conditions Adverse to Quality
and Safety. 4. NRC Generic Letter 90-05, Guidance for Performing Temporary Non-code Repairs of ASME Code Class 1, 2, and 3 Piping. 5. NRC Regulatory Guide 1.147, Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1. 6. UFSAR Section 3.2, Classification of Structures, Systems, and Components. 7. 0BNP-TR-001, Inservice Inspection Technical Report
- 8. AD-OP-ALL-0105, Operability Determinations and Functionality Assessments.
Brunswick Unit 2 B 3.15-1 Revision No. 23 B 3.15 Not used.
Service Water System OPERABILITY-Shutdown B 3.16 Brunswick Unit 2 B 3.16-1 Revision No. 58 B 3.16 SERVICE WATER SYSTEM OPERABILITY-SHUTDOWN
BASES For Mode 4 and 5 conditions, the Service Water System is designed to provide cooling water for
the removal of heat from equipment such as the emergency diesel generators, the Reactor
Building Closed Cooling Water (RBCCW) System and the Residual Heat Removal Service
Water (RHRSW) System. The Service Water Syst em provides cooling water for the service water pump motors. During the initial stage (0 - 10 minutes) of an event (DBA on the opposite
unit, loss of shutdown cooling, a loss of coolant inventory, etc.) potentially combined with a Loss
of Offsite Power (LOOP), the Service Water System must automatically provide cooling water to the emergency diesel generators. Following the first 10 minute period, shutdown cooling loads
must be supplied. The Service Water System also provides flow to the Turbine Building Closed
Cooling Water System, the Chlorination System, lube water to the Circulating Water Pumps, and fill to the Circulating Water System.
The Service Water System design allows either (or both) unit's nuclear header to supply diesel
generator cooling water when required. The phrase "site nuclear service water pump" refers to
any nuclear service water pump on either unit. Other pump designations refer to the specific
unit under discussion. The four nuclear service water pumps on site, two per unit, are each on
a separate emergency bus so that a single failure could prevent only one nuclear service water
pump from operating.
The OPERABILITY requirements are structured to ensure that the Service Water System is capable of automatically supplying sufficient cooling water for the diesel generators assuming
no operator action for the first 10 minutes following an event, and that at least one service water
pump for the shutdown unit is available to supply the shutdown cooling loads after the first ten
minutes following an event. The event includes consideration of a LOOP and/or a single active
failure. For the specific alignments associated with header maintenance, plant procedures
document required administrative controls and valve operability requirements needed to ensure that these objectives are met.
The four nuclear service water pumps are pow ered from separate emergency buses. The three conventional service water pumps on each unit are on separate emergency buses. For each
unit, two of the conventional pumps are on the same emergency buses as the two unit nuclear
service water pumps. The loss of one nuclear pump and one conventional pump on the unit
due to a single failure of one emergency bus has been accounted for in the OPERABILITY
requirements. However, conventional service water pump OPERABILITY will be more strictly defined in cases where only one nuclear pump and one conventional pump are available for
operation. Therefore, with one unit nuclear service water pump and one conventional service
water pump available, the conventional servic e water pump must be powered from a separate emergency bus to be considered OPERABLE.
(continued)
Service Water System OPERABILITY-Shutdown B 3.16 Brunswick Unit 2 B 3.16-2 Revision No. 58 BASES (continued)
In MODES 4 and 5, a conventional pump may be considered OPERABLE when only the
applicable header discharge valve is OPERABLE. This allows maintenance on the conventional
and nuclear headers without reducing Service Water System OPERABILITY. However, a
conventional pump aligned to the nuclear header is not considered to meet the requirements for
an OPERABLE nuclear pump since it is not automatically powered and restarted on the diesel
generators following an accident signal.
In MODES 4 and 5, with a DBA in the opposite unit, two nuclear service water pumps from one
or both units are capable of supplying sufficient flow to cool all four emergency diesel
generators under worst-case scenarios while also supplying flow to other potential flow paths (vital header loads, cross-header leakage, and pump strainer backwash flow). To prohibit any
single failure from preventing the supply of service water to the diesel generators during the first
10 minutes following a DBA, at least three nuclear service water pumps per site are required
while in MODE 4 or 5.
In MODES 4 and 5, one unit service water pump, nuclear or conventional, is capable of
supplying additional required safety-related and shutdown equipment. To prohibit any single
failure from preventing the supply of service water after the first 10 minutes following an event, at least two OPERABLE unit service water pumps, nuclear or conventional, are required while in
MODES 4 or 5. When only one header is available, an event with failure of one division of
emergency power can result in the need for manual actions in the reactor building to reposition
valves as the decay heat removal function is being restored.
The allowed out-of service times and Compensatory Measures established are conservative.
Although the probability and consequences of an event are reduced in MODES 4 and 5, the
Compensatory Measures for the nuclear service water pumps for a unit in MODE 4 or 5 are
based on the assumption that the other unit is in MODE 1, 2, or 3. Specific Compensatory
Measures have not been established for both units in MODES 4 or 5 since the
COMPENSATORY MEASURES for one unit in MODE 4 or 5 are more conservative.
In MODES 4 and 5, a LOCA is not considered credible and core decay heat loads are reduced.
As such, availability of service water for vital header loads is not needed. However, in
MODES 4 and 5, the availability of service water is required to support cooling for decay heat
removal systems. Therefore, the OPERABILITY requirements for the unit service water pumps apply for nuclear or conventional pumps. With one OPERABLE unit service water pump, the
applicable decay heat removal systems remain OPERABLE. However, to minimize the
possibility of loss of these systems due to loss of the single pump, the out of service time for one OPERABLE unit service water pump is set at 7 days. For no OPERABLE unit service
water pumps, the applicable decay heat removal systems must be declared inoperable.
(continued)
Service Water System OPERABILITY-Shutdown B 3.16 Brunswick Unit 2 B 3.16-3 Revision No. 58 BASES (continued)
In MODES 4 and 5, Condition A allows one unit to operate with the nuclear service water
header inoperable for up to 14 days provided that: a) two nuclear service water pumps are OPERABLE on the other unit, b) both units' nuclear service water header valves are administratively controlled as required to ensure cooling water to the diesel generators, c) the Service Water System conventional header is OPERABLE with two unit conventional service water pumps OPERABLE, and d) administrative controls are established to isolate OPERABLE conventional service water pumps and required loads from the inoperable nuclear header.
Considering any additional single failure, this requirement ensures at least one OPERABLE
nuclear service water pump to supply the diesel generators during the first 10 minutes after an
event and one OPERABLE conventional service water pump to supply the unit shutdown
cooling loads. By requiring administrative control of applicable valves, the Required Compensatory Measure minimizes the risk of inadvertent valve action that could reduce cooling
water flow to the diesel generators or result in flow diversion that could affect CSW flow to
essential loads.
Service Water System-Shutdown Operations B 3.17 Brunswick Unit 2 B 3.17-1 Revision No. 23 B 3.17 SERVICE WATER SYSTEM-SHUTDOWN OPERATIONS
BASES This Specification permits securing the Serv ice Water System conventional header when the nuclear header is out of service and is required to permit flange installation in Service Water
System header cross-connect piping.
CREV System-Smoke Protection Mode B 3.18 Brunswick Unit 2 B 3.18-1 Revision No. 23 B 3.18 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM-SMOKE PROTECTION MODE BASES BACKGROUND One of the principal design objectives of the Control Building Heating, Ventilation and Air
Conditioning (CBHVAC) System is to permit continuous occupancy of the control room
emergency zone under normal operating conditions and under the postulated design basis
events throughout the life of the plant. The Control Building HVAC System must function to
provide protection to the operators for three type events: a radiation event, up to and including
a Design Basis Accident (e.g., Main Steam Line Break [MSLB] Accident, Refueling Accident, Control Rod Drop Accident, or Loss of Coolant accident [LOCA]), a toxic gas event (complete
rupture of the 55 ton chlorine tank car located near the service water building, or a slow leak
lasting for an extended period of time), and an ex ternal smoke event. These events form the basis for the design of the Control Room Emer gency Ventilation (CREV) System function of the CBHVAC System. The radiation protection func tion of CREV System is addressed in Technical
Specifications.
The CREV System is designed to meet General De sign Criterion (GDC) 19 (Reference 1). In
addition, the system is designed using the guidance of Regulatory Guide 1.95, Revision 1 (Reference 2).
TRMS OPERABILITY of the CREV System ensures that the control room will remain habitable for
operations personnel during and following all credible hazard event scenarios external to the
control room, consistent with the assumptions in the various analyses. Two redundant
subsystems of the CREV System are required to be OPERABLE to ensure that at least one is
available, assuming a single failure disables the other subsystem. The CREV System is
considered OPERABLE when the individual components necessary to control operator
exposure are OPERABLE in both subsystems. For the smoke protection mode, a subsystem is considered OPERABLE when its associated: 1. Fan is OPERABLE,
- 2. HEPA filter and charcoal adsorbers are not excessively restricting flow and are capable of performing their filtration functions, and 3. Ductwork and dampers are OPERABLE, and when air circulation exists (as required in Reference 3, Section 3.1).
(continued)
CREV System-Smoke Protection Mode B 3.18 Brunswick Unit 2 B 3.18-2 Revision No. 23 BASES TRMS (continued) Two additional OPERABILITY requirements apply to all modes of CREV System operation. The
CBHVAC Control Air System must be OPERABLE to support damper operation. In addition, the control room envelope must be maintained, including the integrity of the walls, floors, ceilings, ductwork, and access doors. The control room envelope includes the electronic equipment rooms, the central control room area, computer rooms, kitchen, restrooms, and the supply and
return ductwork up to and including the isolation dampers.
The following components, including their associated logic trains, actuation devices, and power
supplies, are non-redundant. Their OPERABILITY affects both trains of the CREV System.
These components are: control room (washr oom) exhaust isolation damper, control room normal make-up damper, and the control room emergency recirculation damper. In addition, the control room is not equipped with redundant outdoor air intakes (References 4 and 5).
The radiation/smoke protection mode of operation provides protection to the control room operators in the event of an external smoke event.
During an external smoke event, the CBHVAC Syst em is required to automatically isolate and enter the radiation/smoke protection mode on a smoke detection signal from the Control Room Envelope Smoke Protection Zone Function. Upon receipt of a smoke detection signal, the
CBHVAC System is automatically realigned to the emergency mode of operation. The normal
fresh air inlet closes, and, at approximately the same time, the emergency air filtration units
begin operation, recirculating control room air and providing filtered makeup air to minimize
smoke build-up and provide positive pre ssure in the control room envelope.
APPLICABILITY The applicabilities ensure that system is capable of performing the required smoke protection function when the potential for external hazards exist.
COMPENSATORY MEASURES With one emergency filtration subsystem i noperable, the inoperable subsystem must be restored to OPERABLE status within 7 days. With the unit in this condition, the remaining
subsystem is adequate to perform control room smoke protection. The loss of a single
emergency filtration unit means that the CREV System reliability is reduced because a single
failure in the OPERABLE subsystem could result in reduced or lost system capability. The
7 day out of service time is based on the low probability of an external smoke event and a single
failure in the OPERABLE subsystem occurring during this time period, and the capability of the
remaining subsystem to provide the required capabilities.
(continued)
CREV System-Smoke Protection Mode B 3.18 Brunswick Unit 2 B 3.18-3 Revision No. 23 BASES COMPENSATORY MEASURES (continued)
If the inoperable subsystem cannot be restored to OPERABLE status within the required 7 days, Required Compensatory Measures must be taken to return the subsystem to OPERABLE status and initiate a Condition Report.
The loss of both emergency filtration subsystems means that the smoke protection function is
lost. In this Condition, Required Compensatory Measures must be taken to return the
subsystems to OPERABLE status and initiate a Condition Report.
The Required Compensatory Measures are modified by a Note which eliminates the
requirement to initiate a Condition Report when equipment inoperability is due solely to planned
maintenance or performance of surveillance. The intent of initiation of a Condition Report is to
ensure that proper corrective actions are taken to restore inoperable equipment. When
equipment is inoperable due to planned maintenance or performance of surveillance testing, such corrective actions are not required. If, however, unexpected failures are identified during
performance of the maintenance or surveillance testing, a Condition Report shall be initiated.
TEST REQUIREMENTS The Test Requirement demonstrates functional capab ility of the system by verifying automatic emergency system initiation upon receipt of a smoke detection signal.
REFERENCES
- 1. 10 CFR 50, Appendix A, General Design Criterion 19, Control Room.
- 2. Regulatory Guide 1.95, Revision 1, Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chemical Release. 3. DBD-37, Design Basis Document for Control Building Heating, Ventilation, and Air Conditioning System. 4. NUS-3697, Revision 2, February 1983, Control Room Habitability Analysis.
- 5. NLU-83-673, TMI Action Item III.D.3.4-Control Room Habitability, NRC Safety Evaluation dated October 18, 1983.
CREV System-Chlorine Protection Mode B 3.19 Brunswick Unit 2 B 3.19-1 Revision No. 23 B 3.19 CONTROL ROOM EMERGENCY VENTILATION (CREV) SYSTEM-CHLORINE PROTECTION MODE BASES BACKGROUND One of the principal design objectives of the Control Building Heating, Ventilation and Air
Conditioning (CBHVAC) System is to permit continuous occupancy of the control room
emergency zone under normal operating conditions and under the postulated design basis
events throughout the life of the plant. The Control Building HVAC System must function to
provide protection to the operators for three type events: a radiation event, up to and including
a Design Basis Accident (e.g., Main Steam Line Break [MSLB] Accident, Refueling Accident, Control Rod Drop Accident, or Loss of Coolant Accident [LOCA]), a toxic gas event (complete
rupture of the 55 ton chlorine tank car located near the service water building, or a slow leak
lasting for an extended period of time), and an ex ternal smoke event. These events form the basis for the design of the Control Room Emer gency Ventilation (CREV) System function of the CBHVAC System. The radiation protection func tion of CREV System is addressed in Technical
Specifications.
The CREV System is designed to meet General De sign Criterion (GDC) 19 (Reference 1). In
addition, the system is designed using the guidance of Regulatory Guide 1.95, Revision 1 (Reference 2). Commitments have also been made to design the chlorine detection and
isolation logic to single failure criteria, with approved exceptions (Reference 3, Section 3.6).
TRMS OPERABILITY of the CREV System ensures that the control room will remain habitable for
operations personnel during and following all credible hazard event scenarios external to the
control room, consistent with the assumptions in the various analyses. Two redundant
subsystems of the CREV System are required to be OPERABLE to ensure that at least one is
available, assuming a single failure disables the other subsystem. The CREV System is
considered OPERABLE when the individual components necessary to control operator
exposure are OPERABLE in both subsystems. For the chlorine protection mode, a subsystem
is considered OPERABLE when: 1. The isolation dampers are OPERABLE, and
- 2. The logic components necessary to achieve automatic isolation are functional, as described in Reference 3, Section 3.1.
(continued)
CREV System-Chlorine Protection Mode B 3.19 Brunswick Unit 2 B 3.19-2 Revision No. 23 BASES (continued)
TRMS (continued) Two additional OPERABILITY requirements apply to all modes of CREV System operation. The
CBHVAC Control Air System must be OPERABLE to support damper operation. In addition, the control room envelope must be maintained, including the integrity of the walls, floors, ceilings, ductwork, and access doors. The control room envelope includes the electronic equipment rooms, the central control room area, computer rooms, kitchen, restrooms, and the supply and
return ductwork up to and including the isolation dampers.
The following components, including their associated logic trains, actuation devices, and power
supplies, are non-redundant. Their OPERABILITY affects both trains of the CREV System.
These components are: control room (washr oom) exhaust isolation damper, control room normal make-up damper, and the control room emergency recirculation damper. In addition, the control room is not equipped with redundant outdoor air intakes (References 4 and 5).
In the event of a chlorine release, the CBHVAC System enters a full recirculation mode (chlorine protection mode), with no outdoor air intake. The emergency filtration trains do not start, since
they do not effectively remove chlorine and may be damaged by the presence of chlorine.
Protection for chlorine gas events "overrides" any concurrent, ongoing, or subsequent radiation
or smoke initiation signals. The override design offers protection to operations personnel in the
control room by providing protection against potentially fatal chlorine gas releases. This
protection is required any time the chlorine tank car is within the exclusion area.
APPLICABILITY OPERABILITY of the chlorine protection mode of the CREV System is required any time the chlorine tank car is within the exclusion area. Analyses demonstrate that movement of the tank
car outside the exclusion area sufficiently reduces the threat of control room operator
incapacitation from a release of this chemical.
COMPENSATORY MEASURES With the chlorine protection mode inoperable for reasons other than inoperable chlorine
isolation instrumentation, the chlorine tank car must be removed from the exclusion area within
the next eight hours to ensure adequate protection for the operators. Chlorine gas protection is
not required with the tank car outside of the exclusion area. Eight hours is considered adequate
time to perform the necessary system alignments and to allow plant personnel to remove the
chlorine tank car from the site in an orderly manner.
(continued)
CREV System-Chlorine Protection Mode B 3.19 Brunswick Unit 2 B 3.19-3 Revision No. 23 BASES COMPENSATORY MEASURES (continued)
With the plant physically unable to remove the chlorine tank car from the site, Required
Compensatory Measures must be taken to return the chlorine protection mode to OPERABLE
status and initiate a Condition Report.
Compensatory Measure A.2.2 is modified by a Note which eliminates the requirement to initiate a Condition Report when equipment inoperability is due solely to planned maintenance or
performance of surveillance. The intent of initiation of a Condition Report is to ensure that
proper corrective actions are taken to restore inoperable equipment. When equipment is
inoperable due to planned maintenance or performance of surveillance testing, such corrective
actions are not required. If, however, unexpected failures are identified during performance of
the maintenance or surveillance testing, a Condition Report shall be initiated.
TEST REQUIREMENTS The Test Requirement demonstrates functional capabilit y of the system by verifying the override function of the chlorine protection function. Testing of the chlorine override function ensures
OPERABILITY of the chlorine protection mode of the CREV System by demonstrating the capability of the system to prevent the emergency filtration units from initiating during a chlorine
event.
REFERENCES
- 1. 10 CFR 50, Appendix A, General Design Criterion 19, Control Room.
- 2. Regulatory Guide 1.95, Revision 1, Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chemical Release. 3. DBD-37, Design Basis Document for Control Building Heating, Ventilation, and Air Conditioning System. 4. NUS-3697, Revision 2, February 1983, Control Room Habitability Analysis.
- 5. NLU-83-673, TMI Action Item III.D.3.4-Control Room Habitability, NRC Safety Evaluation dated October 18, 1983.
Flood Protection B 3.20 Brunswick Unit 2 B 3.20-1 Revision No. 23 B 3.20 FLOOD PROTECTION
BASES The limitation on flood protection ensures that facility protective actions will be taken and operation will be terminated in the event of flood conditions. The limit of elevation 17'6" Mean
Sea Level is based on the maximum elevation at which facility flood control measures provide protection to safety-related structures, systems, components, and equipment.
Snubbers B 3.21 Brunswick Unit 2 B 3.21-1 Revision No. 66 B 3.21 SNUBBERS
BASES All snubbers are required OPERABLE to ensure that the structural integrity of the Reactor
Coolant System and all other safety-related systems is maintained during and following a seismic or other event initiating dynamic loads. Snubbers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure
of the systems which they are installed, w ould have no adverse effect on any safety-related system.
A list of all required individual snubbers necessary for structural integrity, with detailed
information of snubber location and size and of system affected, shall be available at the plant
in accordance with Section 50.71(c) of 10 CFR Part 50. The accessibility of each snubber shall
be based upon the existing radiation levels and the expected time to perform a visual inspection
in each snubber location as well as other factors associated with accessibility during plant
operations (e.g., temperature, atmosphere, locations, etc.), and the recommendations of
Regulatory Guides 8.8 and 8.10. The addition or deletion of any hydraulic or mechanical
snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.
Amendments 241 and 269 (Reference 1) to Renewed Facility Operating Licenses DPR-71
and DPR-62 for Units 1 and 2, respectively, approved the addition of Technical Specification
Limiting Condition for Operation (LCO) 3.0.8 for snubbers. LCO 3.0.8 establishes conditions
under which systems are considered to remain capable of performing their intended safety
function when associated snubbers are not capable of providing their associated support
function(s). LCO 3.0.8 states that the supported system is not considered to be inoperable
solely due to one or more snubbers not capable of performing their associated support
function(s).
Compensatory Measure A applies when one or more snubbers are not capable of providing
their associated support function(s) to a single train or subsystem of a multiple train or
subsystem supported system or to a single tr ain or subsystem supported system. TRMS, Compensatory Measure A.1 requires an engineering evaluation to be performed on the
attached component to determine if the component is acceptable for continued operation. The
Completion Time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to restore the snubber(s) before declaring the
supported system inoperable. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time is reasonable based on the low
probability of a seismic event concurrent with an event that would require operation of the
supported system occurring while the snubber(s) are not capable of performing their associated
support function and due to the availability of the redundant train of the supported system.
(continued)
Snubbers B 3.21 Brunswick Unit 2 B 3.21-2 Revision No. 66 BASES (continued)
Compensatory Measure B applies when one or more snubbers are not capable of providing
their associated support function(s) to more than one train or subsystem of a multiple train or
subsystem supported system. Compensatory Measure B.1 requires an engineering evaluation to be performed on the attached component to determine if the component is acceptable for
continued operation. The Completion Time of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to restore the snubber(s) before declaring the
supported system inoperable. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Completion Time is reasonable based on the low
probability of a seismic event concurrent with an event that would require operation of the
supported system occurring while the snubber(s) are not capable of performing their associated
support function.
REFERENCES
- 1. Letter from Stewart N. Bailey (USNRC) to James Scarola (CP&L) dated February 15, 2007, Issuance of Amendment to Adopt TSTF-372 (TAC Nos. MD1371 and MD1372).
Sealed Source Contamination B 3.22 Brunswick Unit 2 B 3.22-1 Revision No. 23 B 3.22 SEALED SOURCE CONTAMINATION
BASES The limitation on removable contamination for sources requiring leak testing, including alpha
emitters, is based on 10 CFR 70.39(c) limits for plutonium. This limitation will ensure that leakage from by-product, source, and special nuclear material sources will not exceed allowable
intake values. Sealed sources are classified into three groups according to their damage to a
source in that group. Those sources which are frequently handled are required to be tested
more often than those which are not. Sealed sources that are continuously enclosed within a
shielded mechanism, i.e., sealed sources with radiation monitoring or boron measuring devices, are considered to be stored and need not be tested unless they are removed from the shielding
mechanism. Fission detectors associated with Local Power Range Monitors are considered to
be stored and continuously enclosed within a shielded mechanism when the fission detector is
enclosed in the associated detector housing tube provided the detector housing tube is not
breached.
Decay Time B 3.23 Brunswick Unit 2 B 3.23-1 Revision No. 23 B 3.23 DECAY TIME
BASES The minimum requirement for reactor subcriticality prior to fuel movement ensures that sufficient
time has elapsed to allow the radioactive decay of the short lived fission products. This decay
time is consistent with the assumptions used in the accident analyses.
Communications B 3.24 Brunswick Unit 2 B 3.24-1 Revision No. 23 B 3.24 COMMUNICATIONS
BASES The requirement for communications capability ensures that refueling station personnel can be
promptly informed of significant changes in the facility status or core reactivity condition during
movement of fuel within the reactor pressure vessel.
Crane and Hoist Operability B 3.25 Brunswick Unit 2 B 3.25-1 Revision No. 23 B 3.25 CRANE AND HOIST OPERABILITY
BASES The OPERABILITY requirements of the cranes and hoists used for movement of fuel
assemblies ensures that: 1) each has sufficient load capacity to lift a fuel element, and 2) the
core internals and pressure vessel are protected from excessive lifting force in the event they
are inadvertently engaged during lifting operations.
The fuel grapple hoist overload cutoff demonstration load of 1600 pounds is based on the
submerged fuel bundle loads of 650 pounds, the highest unloaded hoist cable-supported load of
approximately 660 pounds, and a tolerance for fuel bundle friction and load spikes of
290 pounds.
The fuel grapple hoist loaded interlock demonstration load of 750 pounds is based on the
highest unloaded hoist cable-supported load of approximately 660 pounds plus a tolerance for
load spikes of 90 pounds as sections are raised and lowered.
Crane Travel-Spent Fuel Storage Pool B 3.26 Brunswick Unit 2 B 3.26-1 Revision No. 23 B 3.26 CRANE TRAVEL-SPENT FUEL STORAGE POOL
BASES The restriction on movement of loads in excess of the weight specified provides some
assurance that with the failure of the lifting device the fuel pool would not be damaged to such a
degree that the irradiated fuel would be subjected to a loss-of-coolant.
Brunswick Unit 2 Revision No. 23 APPENDIX A RELOCATED ITEMS MATRIX
TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-1) Revision No. 23
ITS CTS Description General Location Specific Location 2.0 LA.2 6.7.1.b, 6.7.1.c, and
6.7.1.d Safety Limit Violations and the notification of the Vice
President-Brunswick Nuclear Plant along with submittal of
a report. UFSAR Section 13.5.1 3.0 LA.1 3.0.4 Discussion of intent of CTS 3.0.4 phrase "Exceptions to this Specification are stated in individual Specifications." Bases B 3.0: LCO 3.0.4 3.1.1 LA.1 4.1.1.a Detail of the method for performing the surveillance. Bases B 3.1.1: SR 3.1.1.1 3.1.2 LA.1 3.1.2 Action a Perform an analysis to determine and explain the cause of the reactivity difference. Bases B 3.1.2: Action A.1 3.1.3 LA.1 3.1.3.1 Actions a.1.b Details for method of disarming stuck control rods. Bases B 3.1.3: Actions A.1, A.2, A.3, and A.4 3.1.3 LA.1 3.1.3.1 Actions b.1.c
and b.2.a.
3.1.3.6 Action a.2 Details for method of disarming non-stuck control rods. Bases B 3.1.3: Actions C.1 and C.2 3.1.3 LA.2 4.1.3.6 Details of method of performing the control rod coupling integrity checks. Bases B 3.1.3: SR 3.1.3.5 3.1.3 LA.3 3.1.3.7 Action a Methods for determining the position of a control rod and
details of which control rod position switches are required. Bases B 3.1.3: SR 3.1.3.1 3.1.3 LA.4 3.1.3.6 Action a.2 Method of coupling a control rod. Bases B 3.1.3: Actions C.1 and
C.2 3.1.3 LA.5 4.1.1.b Unit 2 Detail of method of performing SDM. Bases B 3.1.3: Actions A.1, A.2, A.3, and A.4 3.1.4 LA.1 4.1.3.2, 4.1.3.3, and
4.1.3.4 Details of the method for performing control rod scram
time testing. Bases B 3.1.4: SR 3.1.4.1, SR 3.1.4.2, and
SR 3.1.4.4 3.1.4 LA.2 4.1.3.2.c Details of what constituted a representative sample of control rods to be tested. Bases B 3.1.4: SR 3.1.4.2 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-2) Revision No. 23
ITS CTS Description General Location Specific Location 3.1.5 LA.1 4.1.3.5 Details of the method of verifying OPERABILITY of control rod scram accumulators (not in alarmed condition). Bases B 3.1.5: SR 3.1.5.1 3.1.5 LC.1 4.1.3.5.a and 4.1.3.5.b Control rod scram accumulators, leak detectors, and
pressure detectors testing. UFSAR Section 3.9.4.1.2.4 3.1.7 LA.1 3.1.5 Details of what constitutes an OPERABLE Standby Liquid Control (SLC) System. Bases B 3.1.7: Background and LCO 3.1.7 LA.2 4.1.5.b.3 Details of the method for performing test that verifies SLC boron concentration. Bases B 3.1.7: SR 3.1.7.5 3.1.7 LA.2 4.1.5.c.1 Details of the method for performing test that verifies SLC flow of system to reactor. Bases B 3.1.7: SR 3.1.7.7 3.1.7 LA.3 4.1.5.c.3 SLC System relief valve setting. UFSAR Section 9.3.4.4 3.1.7 LA.5 Figure 3.1.5-1 Statement that boron concentration range in
Figure 3.1.5-1 supports a boron concentration of 660
ppm. Bases B 3.1.7: Applicable Safety Analysis 3.1.8 LA.1 4.1.3.1.1 Note
- Allowance for scram discharge volume vent and drain
valves to be closed intermittently under administrative
control during testing. Bases B 3.1.8: SR 3.1.8.1 None 3/4.1.3.8 LA.1 Requirement for CRD housing support to be in place. TRM TRMS 3.1 3.2.1 LA.1 3.2.1 The types of APLHGR limits, the methodology used to determine the limits, and the COLR location of the limits to
be used when hand calculations are required. Bases B 3.2.1: LCO 3.2.1 LA.2 3.2.1 Action Requirement to "initiate corrective action within 15 minutes and continue corrective action" to restore limit. Bases B 3.2.1: Action A.1 3.2.2 LA.1 3.2.2.1 Details that MPCR limits in the COLR are provided as a function of core flow, core power, and cycle average
exposure. Bases B 3.2.2: LCO 3.2.2 LA.2 3.2.2.1 Action Requirement to "initiate corrective action within 15 minutes and continue corrective action" to restore limit. Bases B 3.2.2: Action A.1 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-3) Revision No. 23
ITS CTS Description General Location Specific Location 3.2.2 LA.3 3.2.2.2 Details related to the determination of average control rod scram time (Tau) and the use of Tau in determining the
operating limits of MCPRs. UFSAR Section 4.4.1.5 3.3.1.1 LA.1 Table 2.2.1-1 Trip setpoints for associated instrumentation. TRM Appendix B: TRM Table 3.3.1.1-1 3.3.1.1 LA.2 Table 2.2.1-1
Note (a) Design details of IRM RPS instrumentation. Bases B 3.3.1.1: ASA/ LCO/ APP of Function 1.a 3.3.1.1 LA.2 Table 2.2.1-1
Notes (c) and (d) Design details of APRM RPS instrumentation. Bases B 3.3.1.1: ASA/ LCO/ APP of Functions 2.b and 2.c 3.3.1.1 LA.3 Table 2.2.1-1
Note (b) Note (b): APRM Neutron Flux - High, Startup Function is a
fixed point and is increased when the reactor mode switch
is placed in run position. UFSAR Section 7.6.1.1.4 3.3.1.1 LA.3 Table 2.2.1-1
Notes (e) and (f) Note (e): Main Steam Line Isolation Valve - Closure
Function is bypassed when not in the run mode.
Note (f): TSV - Closure and TCV Fast Closure Functions
are bypassed < 30% rated thermal power. UFSAR Section 7.2.1.1.4 3.3.1.1 LA.4 Table 2.2.1-1
Note (g) Vessel water levels are referenced to REFERENCE
LEVEL ZERO. Bases B 3.3.1.1: ASA/ LCO/ APP of Function 4 3.3.1.1 LA.5 3.3.1 Actions
- and **
Notes Details relating to placing channels in trip. Bases B 3.3.1.1: Actions A.1 and A.2; B.1 and B.2 3.3.1.1 LA.6 4.3.1.2 Details of the method for performing surveillances. Bases B 3.3.1.1: SR 3.3.1.1.15 3.3.1.1 LA.6 Table 4.3.1-1
Note (e) Details of the method for performing surveillances. Bases B 3.3.1.1: SR 3.3.1.1.3 3.3.1.1 LA.6 Table 4.3.1-1
Note (g) Details of the method for performing surveillances. Bases B 3.3.1.1: SR 3.3.1.1.8 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-4) Revision No. 23
ITS CTS Description General Location Specific Location 3.3.1.1 LA.7 Table 3.3.1-1
Note (b) Requirements associated with the removal of shorting
links. UFSAR Section 7.6.1.1.1.2.d 3.3.1.1 LA.8 Table 3.3.1-1
Note (c) Number of LPRM inputs for APRM OPERABILITY. Bases B 3.3.1.1: ASA/LCO/APP of APRM. 3.3.1.1 LA.9 Table 4.3.1-1
Note (h) Details on how to perform calibration of position switches. Bases B 3.3.1.1: SR 3.3.1.1.13 3.3.1.2 LA.1 4.3.5.4.b Details of the method for performing the surveillance. Bases B 3.3.1.2: LCO 3.3.1.2 LA.2 3/4.9.2 Details relating to SRM OPERABILITY. Bases B 3.3.1.2: LCO; SR 3.3.1.2.4 3.3.1.2 LA.3 3.9.2.c Removal of RPS shorting links. UFSAR Section 7.6.1.1.1.2.d 3.3.2.1 LA.1 Table 3.3.4-2 Trip setpoints for associated instrumentation. TRM Appendix B: TRM Table 3.3.2.1-1 3.3.2.1 LA.2 Table 4.3.1-1
Note (a) Details of the methods for performing the RBM CHANNEL
CALIBRATION. Bases B 3.3.2.1: SR 3.3.2.1.7 3.3.2.1 LA.3 3.1.4.1 Action d.2 Details relating to actions when an individual control rod is
bypassed on the RWM. Bases B 3.3.2.1: Actions C.1, C.2.1.1, C.2.1.2, and
C.2.2 3.3.2.1 LA.4 4.1.4.1.1 Details of the methods for performing RWM CHANNEL FUNCTIONAL TEST. Bases B 3.3.2.1: SR 3.3.2.1.2 and SR 3.3.2.1.3 3.3.2.1 R.1 3/4.3.4.1 3/4.3.4.3
3/4.3.4.4
3/4.3.4.5 Control Rod Block Instrumentation for APRM, IRM, SRM, and SDV LCO's and Surveillance Requirements. TRM TRMS 3.3 and Appendix C: TRM Table 3.3-2 3.3.3.1 LA.1 Table 3.3.5.3-
1 ACTION 81 The use of alternate methods of post accident monitoring. Bases B 3.3.3.1: Action B.1 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-5) Revision No. 23
ITS CTS Description General Location Specific Location 3.3.3.1 LA.2 Table 4.3.5.3-
1 Note (a) Details of the method for performing the surveillance. Bases B 3.3.3.1: SR 3.3.3.1.2 and SR 3.3.3.1.3 3.3.3.1 LA.3 3.6.6.4 Details relating to system design. Bases B 3.3.3.1: LCO for Function 9 3.3.3.1 LA.4 4.6.6.4 Details of the method for performing the surveillance. Bases B 3.3.3.1: SR 3.3.3.1.2 and SR 3.3.3.1.3 3.3.3.1 R.1 3/4.3.5.3 Accident Monitoring Instrumentation; Suppression Chamber Atmosphere Temperature,Drywell Radiation (Airborne radiation monitors),Safety/Relief Valve Position
Indication,Turbine Building Ventilation Monitor, Offgas
Stack Ventilation Monitor LCO's and Surveillance
Requirements. TRM TRMS 3.4 3.3.3.2 LA.1 3/4.3.5.2 Details relating to system design and operation. Bases B 3.3.3.2: LCO and Table B 3.3.3.2-1 3.3.4.1 LA.1 3/4.3.6.1 Trip setpoints for associated instrumentation. TRM Appendix B: TRM Table 3.3.4.1-1 3.3.4.1 LA.2 Table 3.3.6.1-
2 Note (a)
Vessel water levels are referenced to REFERENCE
LEVEL ZERO. Bases B 3.3.4.1: ASA/ LCO/ APP of Function a 3.3.5.1 LA.1 3/4.3.3 Trip setpoints for associated instrumentation. TRM Appendix B: TRM Table 3.3.5.1-1 3.3.5.1 LA.2 4.3.3.2 Details of methods of performing the LOGIC SYSTEM FUNCTIONAL TESTS. Bases B 3.3.5.1: SR 3.3.5.1.5 3.3.5.1 LA.3 Table 3.3.3-1
Function 2.c Reactor Vessel Shroud Level Function is a permissive for drywell spray. Bases B 3.3.5.1: ASA/ LCO/ APP of Function 2.e 3.3.5.1 LA.3 Table 3.3.3-1
Functions 4.e
and 4.f CS and RHR Pump Discharge Pressure-High Functions
are permissives for ADS. Bases B 3.3.5.1: ASA/ LCO/ APP of Functions 4.d, 4.e, 5.d, and 5.e 3.3.5.1 LA.4 Table 3.3.3-1
Function 2.d.1 Details associated with equipment started by the LPCI
Reactor Steam Dome Pressure-Low Function. Bases B 3.3.5.1: ASA/ LCO/ APP of Functions 1.c and 2.c TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-6) Revision No. 23
ITS CTS Description General Location Specific Location 3.3.5.1 LA.5 Table 3.3.3-1
Note (c) Detail which describes what equipment receives the HPCI
pump suction swap over signals. Bases B 3.3.5.1: ASA/ LCO/ APP of Functions 3.d and 3.e 3.3.5.1 LA.6 Table 3.3.3-1
ACTION 30,
item b Requirement to place all inoperable channels that do not
cause the trip function to occur in the tripped condition. Bases B 3.3.5.1: Actions B.1, B.2, and B.3 3.3.5.1 LA.7 Table 3.3.3-2
Note (b) Note (b): Reactor vessel water levels are referenced to
REFERENCE LEVEL ZERO. Bases B 3.3.5.1: ASA/ LCO/ APP of Functions 1.a and 2.a, 2.e, 3.a, 3.c, 4.a and 5.a, and 4.c and 5.c 3.3.5.1 LA.7 Table 3.3.3-2
Note (c) Note (c): Suppression chamber water level zero is the
torus centerline minus 1 inch. Bases B 3.3.5.1: ASA/ LCO/ APP of Function 3.e 3.3.5.1 R.1 3/4.3.3.1.e 3/4.3.3.2.f
3/4.3.3.3.e
3/4.3.3.4.g ECCS Actuation Instrumentation LCO and Surveillances
associated with:
Core Spray Bus Power Monitor;
LPCI Bus Power Monitor;
HPCI Bus Power Monitor; and
ADS Bus Power Monitor. TRM TRMS 3.6 3.3.5.1 R.2 3/4.3.3.4.a ADS Inhibit Switch LCO and Surveillance Requirements. TRM TRMS 3.7 3.3.5.2 LA.1 3/4.3.7 Trip setpoints for associated instrumentation. TRM Appendix B: TRM Table 3.3.5.2-1 3.3.5.2 LA.2 4.3.7.2 Details relating to the methods for performing the LOGIC SYSTEM FUNCTIONAL TEST. Bases B 3.3.5.2: SR 3.3.5.2.5 3.3.5.2 LA.3 Table 3.3.7-1
Notes (b) and (c) RCIC System design and operational details. Bases B 3.3.5.2: Background 3.3.5.2 LA.3 Table 3.3.7-1
Note (d) RCIC System design and operational details. Bases B 3.3.5.2: ASA/ LCO/
APP of Function 3 3.3.5.2 LA.4 Table 3.3.7-2
Note (a) Reactor vessel water levels are referenced to
REFERENCE LEVEL ZERO. Bases B 3.3.5.2: ASA/ LCO/
APP of Functions 1 and 2 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-7) Revision No. 23
ITS CTS Description General Location Specific Location 3.3.6.1 LA.1 3/4.3.2 Trip setpoints for associated instrumentation. TRM Appendix B: TRM Table 3.3.6.1-1 3.3.6.1 LA.2 4.3.2.2 Details relating to the method for performing LOGIC SYSTEM FUNCTIONAL TEST. Bases B 3.3.6.1: SR 3.3.6.1.7 3.3.6.1 LA.3
- Note to
3.3.2 Actions
Details of the method for performing Required Actions of
which trip system to trip. Bases B 3.3.6.1: Action A.1 3.3.6.1 LA.4 Table 3.3.2-1 Details relating to system design and operation. Bases B 3.3.6.1: ASA/LCO/APP of all Functions 3.3.6.1 LA.4 Table 3.3.2-1
Note (k) Details relating to system design and operation. Bases B 3.3.6.1: ASA/LCO/APP of Functions 3.e and 4.e 3.3.6.1 LA.5 Table 3.3.2-1
Function 1.e Requirement for bypassing the Condenser Vacuum-Low
Function when <500 psig. UFSAR Section 7.3.1.1.6.20 3.3.6.1 LA.7 Table 3.3.2-2
Note (a) Reactor vessel water levels are referenced to
REFERENCE LEVEL ZERO. Bases B 3.3.6.1: ASA/LCO/APP of Functions 1.a, 2.a, 5.g, and 6.b 3.3.6.1 R.1 3/4.3.2.4.a.5 3/4.3.2.4.b.5 HPCI and RCIC Bus Power Monitoring. TRM TRMS 3.6 3.3.6.1 R.2 3/4.3.2.1.d and 3/4.3.2.1.f Main Steam Line Tunnel and Turbine Bldg Area
Temperature Instrumentation for MSIV isolation function (except for MSIV pit). TRM TRMS 3.11 and Appendix C: TRM
Table 3.11-2 3.3.6.2 LA.1 3/4.3.2 Trip setpoints for associated instrumentation. TRM Appendix B: TRM Table 3.3.6.2-1 3.3.6.2 LA.2 4.3.2.2 Details relating to the method for performing the LOGIC SYSTEM FUNCTIONAL TEST. Bases B 3.3.6.2: SR 3.3.6.2.5 3.3.6.2 LA.3
- Note to
3.3.2 Actions
Details of the method for performing Required Actions of
which trip system to trip. Bases B 3.3.6.2: Action A.1 3.3.6.2 LA.4 Table 3.3.2-1 Details relating to system design and operation. Bases B 3.3.6.2: Background TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-8) Revision No. 23
ITS CTS Description General Location Specific Location 3.3.6.2 LA.5 Table 3.3.2-2
Note (a) Reactor vessel water levels are referenced to
REFERENCE LEVEL ZERO. Bases B 3.3.6.2: ASA/LCO/APP of Function 1 3.3.7.1 LA.1 3/4.3.5.5 Trip setpoints for associated instrumentation. TRM Appendix B: TRM Table 3.3.7.1-1 3.3.7.1 R.1 3/4.3.5.5.1 3/4.3.5.5.3 CREV System Chlorine Protection Instrumentation and
Smoke Protection Mode Instrumentation requirements. TRM TRMS 3.12 and Appendix C: TRM
Table 3.12-2 3.3.7.2 LA.1 3.3.8 Details relating to instrumentation OPERABILITY. Bases B 3.3.7.2: LCO 3.3.8.1 LA.1 3/4.3.3 Trip setpoints for associated instrumentation. TRM Appendix B: TRM Table 3.3.8.1-1 3.3.8.1 LA.2 4.3.3.2 Details relating to the methods for performing the LOGIC SYSTEM FUNCTIONAL TEST. Bases B 3.3.8.1: SR 3.3.8.1.4 3.3.8.1 LA.3 Table 3.3.3-1
Table 3.3.3-2 Details relating to system design (i.e number of channels
provided, etc.). Bases B 3.3.8.1: Background 3.3.8.1 LA.4 Table 3.3.3-2 Bases for 120V loss of power instrumentation trip setpoints and Allowable Values. TRM Appendix B: TRM Table 3.3.8.1-1 None 3/4.3.5.1 R.1 Seismic Monitoring Instrumentation Technical Specification. TRM TRMS 3.9 None 3/4.3.5.6 R.1 Chlorine Intrusion Monitors Technical Specification. TRM TRMS 3.5 and Appendix C: TRM
Table 3.5-2 None 3/4.3.5.8 R.1 Radioactive Liquid Effluent Monitoring Instrumentation Technical Specification. ODCM ODCMS 7.3.1 None 3/4.3.5.9 LC.1 Requirements for the Main Condenser Off-Gas Treatment
System Explosive Gas Moni toring System (Function G). ODCM ODCMS 7.3.2 None 3/4.3.5.9 R.1 Radioactive Gaseous Effluent Monitoring Instrumentation Technical Specification. ODCM ODCMS 7.3.2 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-9) Revision No. 27
ITS CTS Description General Location Specific Location 3.4.2 LA.1 4.4.1.2.2 Requirements that each jet pump be operable prior to entering OPERATIONAL CONDITION 2 and at least once
per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter with THERMAL POWER less
than or equal to 25% of RTP. UFSAR Deleted in Section 3.9.5.4 per LDCR 04FSAR-038. 3.4.3 LA.1
- footnote to
3.4.2 Details
relating to lift setting pressures of the safety/relief valves. Bases B 3.4.3: SR 3.4.3.1 3.4.4 LA.1 4.4.3.2 Details of the methods for performing the Reactor Coolant System leakage surveillance. Bases B 3.4.4: SR 3.4.4.1 3.4.6 LA.1 Table 4.4.5-1 Item 5 Requirements for isotopic analysis for xenon and krypton. UFSAR Section 11.1.2 3.4.9 LA.1 3.4.6.1.c Limitations on the maximum RCS temperature change in any one hour period during inservice leak and hydrostatic
testing operations above the heatup and cooldown limit curves. Bases B 3.4.9: Actions C.1 and C.2 3.4.9 LA.2 4.4.6.1.3 Requirements for reactor material irradiation surveillance specimen location, removal and examination. UFSAR Section 5.3.1.6 3.4.9 LA.2 Table 4.4.6.1.3-1 Requirements for reactor material irradiation surveillance
specimen location, removal and examination. UFSAR Table 5-8 3.4.9 LA.3 3.4.1.3.c and 3.4.1.3 Action Operational limits during single recirculation loop
operation. UFSAR Section 5.4.1.2.2 3.4.9 LA.4 3.4.6.1 Action Details of method for determining RCS is acceptable for continued operation. Bases B 3.4.9: Actions A.1 and A.2; C.1 and C.2 3.4.9 LA.5 3.4.1.3.a Details of method for performing the recirculation pump startup temperature differential verification (specific RCS
location to monitor temperature). Bases B 3.4.9: SR 3.4.9.4 and SR 3.4.9.5 None 3/4.4.4 R.1 Reactor Coolant System Chemistry Technical Specification. TRM TRMS 3.13 None 3/4.4.8 R.1 Reactor Coolant System Structural Integrity Technical Specification. TRM TRMS 3.14 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-10) Revision No. 23
ITS CTS Description General Location Specific Location 3.5.1 LA.1 3.5.1, 3.5.3.1 and 3.5.3.2 Details relating to system OPERABILITY. Bases B 3.5.1: Background 3.5.1 LA.2 4.5.1.c.1, 4.5.3.1.d,
and 4.5.3.2.c Details of methods for performing Surveillances. Bases B 3.5.1: SR 3.5.1.9 3.5.1 LA.2 4.5.2.a Details of methods for performing Surveillances. Bases B 3.5.1: SR 3.5.1.10 3.5.1 LA.2 4.5.2.b Details of methods for performing Surveillances. Bases B 3.5.1: SR 3.5.1.11 3.5.1 LA.2 4.5.3.1.c.1 and 4.5.3.2.d Details of methods for performing Surveillances. Bases B 3.5.1: SR 3.5.1.6, SR 3.5.1.7, and
SR 3.5.1.8 3.5.1 LA.3 4.5.1.c.3 Verification of automatic transfer of HPCI suction valves. Bases B 3.5.1: SR 3.5.1.9 3.5.1 LA.4 4.5.1.c.2 Lower value of the HPCI turbine steam pressure range. Bases B 3.5.1: SR 3.5.1.6, SR 3.5.1.7, and
SR 3.5.1.8 3.5.1 LC.1 4.5.3.1.c.2 Core Spray Header Delta Pressure Alarm Instrumentation Surveillance Requirements. UFSAR Section 7.3.3.1.3.7 3.5.2 LA.1 3.5.3.1, 3.5.3.2, and
3.5.4 Details
relating to system OPERABILITY. Bases B 3.5.2: LCO 3.5.2 LA.2 4.5.3.1.c.1, 4.5.3.1.d.
4.5.3.2.b, and
4.5.3.2.c Details relating to methods for performing surveillances. Bases B 3.5.2: SR 3.5.2.3, SR 3.5.2.5, SR 3.5.2.6, and SR 3.5.2.7 3.5.3 LA.1 3.7.4 Details relating to system OPERABILITY. Bases B 3.5.3: Background 3.5.3 LA.2 4.7.4.a.1 Details relating to methods for performing surveillances. Bases B 3.5.3: SR 3.5.3.1 3.5.3 LA.2 4.7.4.c.1 (including
Note +) Details relating to methods for performing surveillances. Bases B 3.5.3: SR 3.5.3.5 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-11) Revision No. 23
ITS CTS Description General Location Specific Location 3.5.3 LA.2 4.7.4.b and 4.7.4.c.2 Details relating to methods for performing surveillances. Bases B 3.5.3: SR 3.5.3.3 and SR 3.5.3.4 3.5.3 LA.3 4.7.4.c.3 Verification of automatic transfer of the RCIC pump suction. Bases B 3.5.3: SR 3.5.3.5 3.6.1.1 LA.1 1.0 Details of Primary Containment Integrity definition. Bases B 3.6.1.1: Background 3.6.1.2 LA.1 3.6.1.3.a Details comprising OPERABILITY of the air lock. Bases B 3.6.1.2: LCO 3.6.1.3 LA.1 4.6.3.4 Details relating to methods for performing surveillances. Bases B 3.6.1.3: SR 3.6.1.3.7 3.6.1.3 LA.2 4.6.6.2.b.2 Details of the methods for performing surveillances. Bases B 3.6.1.3: SR 3.6.1.3.6 3.6.1.4 LA.1 4.6.1.6 Details of the methods for performing the drywell average air temperature surveillance. Bases B 3.6.1.4: SR 3.6.1.4.1 3.6.1.5 LA.1 3.6.4.2.b Details relating to the OPERABILITY of the Nitrogen Backup System. Bases B 3.6.1.5: Background 3.6.1.5 LA.2 4.6.4.2.1.a.1
and 4.6.4.2.1.a.2 Details of the method for performing surveillances. Bases B 3.6.1.5: SR 3.6.1.5.3 3.6.1.5 LA.2 4.6.4.2.1.b.1
and 4.6.4.2.1.b.2 Details of the method for performing surveillances. Bases B 3.6.1.5: SR 3.6.1.5.4 3.6.1.5 LA.2 4.6.4.2.2.c Details of the method for performing surveillances. Bases B 3.6.1.5: SR 3.6.1.5.6 3.6.1.5 LA.3 4.6.4.2.1.b.3 Details of visual inspection of reactor building-to-suppression chamber vacuum breakers. UFSAR Section 6.2.1.6.2 3.6.1.6 LA.2 4.6.4.1.b Details of the methods for performing surveillances. Bases B 3.6.1.6: SR 3.6.1.6.2 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-12) Revision No. 23
ITS CTS Description General Location Specific Location 3.6.1.6 LA.2 4.6.4.1.c Details of the methods for performing surveillances. Bases B 3.6.1.6: SR 3.6.1.6.1 3.6.2.3 LA.1 3.6.2.2 Details relating to system OPERABILITY. Bases B 3.6.2.3: Background and LCO 3.6.3.2 LA.1 3.6.6.2 Details relating to system OPERABILITY. Bases B 3.6.3.2: LCO 3.6.3.2 LA.2 4.6.6.2.b.1 Details of the methods for performing surveillances. Bases B 3.6.3.2: SR 3.6.3.2.3 3.6.4.1 LA.1 1.0 Details of Secondary Containment Integrity definition. Bases B 3.6.4.1: LCO B 3.6.4.2: LCO; Actions
A.1 and A.2; Action B.1
B 3.6.4.3: LCO 3.6.4.2 LA.1 4.6.5.1.a and
4.6.5.2.a Cycling of each automatic Secondary Containment
Isolation Damper. UFSAR Section 6.2.3.4 3.6.4.2 LA.2 4.6.5.2.c.1 Details of the performance of isolation time verification. Bases B 3.6.4.2: SR 3.6.4.2.1 3.6.4.3 LA.1 3.6.6.1 Details relating to system design. Bases B 3.6.4.3: Background 3.6.4.3 LA.2 4.6.6.1.a Details of the methods for performing standby gas treatment subsystem operating surveillance. Bases B 3.6.4.3: SR 3.6.4.3.1 3.6.4.3 LA.3 4.6.6.1.a Details of performance of standby gas treatment subsystem surveillance with heaters "on automatic
control." Bases B 3.6.4.3: SR 3.6.4.3.1 3.7.1 LA.1 3.7.1.1 Details relating to system OPERABILITY. Bases B 3.7.1: LCO 3.7.1 LA.2 4.7.1.1.b Requirements for testing RHRSW pump flow. UFSAR Section 9.2.1.4 3.7.2 LA.1 3.7.1.2 Details relating to system OPERABILITY. Bases B 3.7.2: LCO TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-13) Revision No. 23
ITS CTS Description General Location Specific Location 3.7.2 LA.2 3.7.1.2 Requirements and Actions relating to system OPERABILITY in non-operating MODES (i.e., MODES 4
and 5). Bases and TRM B 3.4.8: LCO;
B 3.9.7: LCO;
B 3.9.8: LCO;
TRMS 3.16 3.7.3 LA.1 3.7.2 Details relating to system OPERABILITY. Bases B 3.7.3: LCO 3.7.3 LA.2 4.7.2.a Details of the methods for performing surveillances. Bases B 3.7.3: SR 3.7.3.1 3.7.3 LA.2 4.7.2.d.2 Details of the methods for performing surveillances. Bases B 3.7.3: SR 3.7.3.4 3.7.3 R.1 3/4.7.2 CREV smoke protection mode requirements.
TRM TRMS 3.18 3.7.3 R.1 3/4.7.2 CREV chlorine protection mode requirements.
TRM TRMS 3.19 3.7.5 LA.1 3.11.2.7 and 4.11.2.7.2 Details defining the radioactivity involved, methods for
performing the surveillance, and methods for determining
when an increase has occurred. Bases B 3.7.5: SR 3.7.5.1 3.7.5 LA.2 4.11.2.7.1 Requirements to monitor the radioactivity rate of noble gases at the main condenser. ODCM ODCMS Table 7.3.2-1, Function 6 3.7.7 LA.1 3.9.9 Action Discussion of crane operation with loads. UFSAR Sections 9.1.4.1 and 9.1.4.2.3.2 3.7.7 LA.2 3.9.9 Action Details of the method for performing action to place equipment in a safe condition. Bases B 3.7.7: Action A.1 None 3/4.7.3 R.1 Flood Protection Technical Specification.
TRM TRMS 3.10 and TRMS 3.20 None 3/4.7.5 LA.1 Snubber Technical Specification.
TRM TRMS 3.21 None 3/4.7.6 R.1 Sealed Source Contamination Technical Specification. TRM TRMS 3.22 3.8.1 LA.1 4.8.1.1.2.d.1 Requirements to inspect DGs in accordance with procedures prepared in accordance with manufacturer's
recommendations. UFSAR Section 8.3.1.1.6.6 3.8.1 LA.2 4.8.1.1.2.a.4 Note
- Details associated with manually starting the DG for
surveillances. Bases B 3.8.1: SR 3.8.1.2 and SR 3.8.1.7 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-14) Revision No. 25
ITS CTS Description General Location Specific Location 3.8.1 LA.3 4.8.1.1.2.d.6 Specific load value for the auto-connected loads. UFSAR Section 8.3.1.1.6.6 and Table 8-7 3.8.1 LA.4 3.8.1.1.a and 3.8.1.1.b Details relating to system design. Bases B 3.8.1: Background 3.8.4 LA.1 3.8.2.3.a and 3.8.2.3.b Details relating to system OPERABILITY. Bases B 3.8.4: Background and LCO 3.8.4 LA.3 4.8.2.3.2.d.1 Details of the DC loads and the licensed service duration for battery service test. UFSAR Section 8.3.2.1.4 3.8.4 LA.4 4.8.2.3.2.d.2 Details requiring battery charger to be demonstrated capable of recharging its associated battery after
completion of the battery service test. UFSAR Section 8.3.2.1.4 3.8.7 LA.1 3.8.2.1, 4.8.2.1,
3.8.2.3, 4.8.2.3.1, 3.8.2.4.1, and
4.8.2.4.1.1 Details relating to system design and OPERABILITY. Bases B 3.8.7: Background; LCO; Table B 3.8.7-1 3.8.7 LA.1 3.8.2.4.1
- Note Details relating to system design and OPERABILITY. Bases B 3.8.7: Actions B.1, B.2, B.3, and B.4 3.8.7 LA.2 3.8.2.4.1 Actions b.1
and b.3 Details of the methods for performing verification of power
availability. Bases B 3.8.7: Actions B.1, B.2, B.3, and B.4 3.8.8 LA.1 3.8.2.2 and 3.8.2.4.2 Details relating to AC and DC electrical power distribution
system design and OPERABILITY. Bases B 3.8.7: Table B 3.8.7-1 3.9.5 LA.1 4.1.3.5.a Details of the method of verifying OPERABILITY of the control rod accumulators. Bases B 3.9.5: SR 3.9.5.1 and SR 3.9.5.2 3.9.5 LC.1 4.1.3.5.a and 4.1.3.5.b Control rod scram accumulators, leak detectors, and
pressure detectors testing. UFSAR Section 3.9.4.1.2.4 None 3/4.9.4 LA.1 Decay Time Technical Specification.
TRM TRMS 3.23 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-15) Revision No. 23
ITS CTS Description General Location Specific Location None 3/4.9.5 R.1 Communications Technical Specification.
TRM TRMS 3.24 None 3/4.9.6 R.1 Crane and Hoist OPERABILITY Technical Specification. TRM TRMS 3.25 None 3/4.9.7 R.1 Crane Travel - Spent Fuel Storage Pool Technical Specification. TRM TRMS 3.26 3.10.2 LA.1 Table 1.2 Note # Details of the method used to verify control rods remain
fully inserted (by verification using a second licensed
operator or other technically qualified member of the unit
technical staff.). Bases B 3.10.2: SR 3.10.2.1 and SR 3.10.2.2 3.10.4 LA.1 3/4.9.10.1.d Details of the recommended procedures for disarming control rods. Bases B 3.10.4: SR 3.10.4.1, SR 3.10.4.2, SR 3.10.4.3, and SR 3.10.4.4 3.10.5 LA.1 3/4.9.10.1.d Details of the recommended procedures for disarming control rods. Bases B 3.10.5: SR 3.10.5.1, SR 3.10.5.2, SR 3.10.5.3, SR 3.10.5.4, and
SR 3.10.5.5 None 3/4.10.5 LA.1 The requirements for OPERABILITY of the Plant Service Water system in non-operating MODES (i.e., MODES 4
and 5). Bases and TRM B 3.4.8: LCO;
B 3.9.7: LCO;
B 3.9.8: LCO;
TRMS 3.17 None 3/4.11.1.1 R.1 Liquid Effluents Concentration Technical Specification. ODCM ODCMS 7.3.3 None 3/4.11.1.2 R.1 Dose Liquid Effluents Technical Specification. ODCM ODCMS 7.3.4 None 3/4.11.1.3 R.1 Liquid Radwaste Treatment System Technical
Specification. ODCM ODCMS 7.3.5 None 3/4.11.2.1 R.1 Gaseous Effluents Technical Specification. ODCM ODCMS 7.3.7 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-16) Revision No. 25
ITS CTS Description General Location Specific Location None 3/4.11.2.2 R.1 Dose Noble Gases Technical Specification. ODCM ODCMS 7.3.8 None 3/4.11.2.3 R.1 Dose Iodine-131, Iodine-133, Tritium, and Radionuclides
in Particulate Form Technical Specification. ODCM ODCMS 7.3.9 None 3/4.11.2.4 R.1 Gaseous Radwaste Treatment System Technical
Specification. ODCM ODCMS 7.3.10 None 3/4.11.2.5 R.1 Ventilation Exhaust Treatment System Technical
Specification. ODCM ODCMS 7.3.11 None 3/4.11.2.8 R.1 Drywell Venting or Purging Technical Specification. ODCM ODCMS 7.3.13 None 3/4.11.3 R.1 Solid Radioactive Waste Technical Specification. UFSAR Section 12.5.3.8 None 3/4.11.4 R.1 Total Dose (40 CFR PART 190) Technical Specification. ODCM ODCMS 7.3.14 None 3/4.12.1 R.1 Radiological Environmental Monitoring Program Technical Specification. ODCM ODCMS 7.3.15 None 3/4.12.2 R.1 Land Use Census Technical Specification. ODCM ODCMS 7.3.16 None 3/4.12.3 R.1 Interlaboratory Comparison Program Technical Specification. ODCM ODCMS 7.3.17 4.0 LA.1 5.1.2 and
5.1.3 Details
of the low population zone and site boundary. UFSAR Section 2.1.1.3 4.0 LA.2 5.2 Configurations, design temperatures and pressures, and volumes of the Primary Containment. UFSAR Section 6.2.1 and Table 6-3 4.0 LA.2 5.4 Configurations, design temperatures and pressures, and volumes of the Reactor Coolant System. UFSAR Section 5.3.3.7 and Table 6-5 4.0 LA.3 5.3.1 Details of specific fuel types that can be inserted in the reactor core. UFSAR Section 4.2.2 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-17) Revision No. 25
ITS CTS Description General Location Specific Location 4.0 LA.5 5.5 Location of meteorological tower. UFSAR Section 2.2.1.3 and Figure 2-2 4.0 LA.6 5.1.6.3 Details of uncertainties included in k eff calculations associated with the fuel racks. UFSAR Section 9.1.2.3.2 4.0 LA.7 5.6.1.1 Corrected temperature for new fuel k-infinity values. UFSAR Section 9.1.1.3 4.0 LA.7 5.6.1.2.a and 5.6.1.2.b Corrected temperature for irradiated fuel k-infinity values. UFSAR Section 9.1.2.3.2 5.1 LA.1 6.1.1 and 6.5.2.7 Compliance details relating to plant specific position titles. UFSAR Section 13.1.2.2 5.2 LA.1 Table 6.2.2-1 Details of the minimum shift crew requirements. UFSAR Table 13-1 5.2 LA.2 6.2.2.d Details of operator license requirements. UFSAR Section 13.1.2.2 5.2 LA.3 6.2.2.g Details that require Core Alterations to be supervised by either a licensed Senior Reactor Operator or Senior
Reactor Operator Limited to Fuel Handling. UFSAR Section 13.1.2.2 5.2 LA.4 6.2.1.b, 6.2.1.c, 6.2.2.e, and
6.2.4.1 Compliance details relating to plant specific position titles. UFSAR Section 13.1.2.2 5.3 LA.1 6.3.1 Compliance details relating to plant specific position titles. UFSAR Section 13.1.2.2 5.4 LA.1 6.8.1.i Guidance of procedures to be used covering Quality Assurance for effluent and environmental monitoring.
QA Program
Description UFSAR Chapter 17, Appendix A, Section 1.1.1 5.4 LA.2 6.8.2 Details of procedure reviews and approvals for temporary changes. QA Program
Description UFSAR Chapter 17, Appendix A, Section 1.1.2 5.4 LA.3 6.8.1.h Requirements for Process Control Program implementation procedures.
QA Program
Description UFSAR Section 17.3.1.7 TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-18) Revision No. 25
ITS CTS Description General Location Specific Location 5.5 LA.1 6.8.3.2 Details of In-Plant Radiation Monitoring Program. UFSAR Section 12.5.3.3 5.5 LA.2 5.7 Details of the components governed by Component Cyclic or Transient Limit Program. UFSAR Table 5-11 5.5 LA.3 4.0.5 Details of the Inservice Inspection Program associated with Generic Letter 88-01. UFSAR Section 5.2.3.4.2.4 5.5 LA.3 4.0.5 Details of the Inservice Inspection Program for Class 1 components.. UFSAR Section 5.2.4 5.5 LA.3 4.0.5 Details of the Inservice Inspection Program for Class 2 and 3 components. UFSAR Section 6.6 5.5 LA.4 4.0.5 Details of the Inservice Testing Program. UFSAR Section 3.9.6 5.5 LA.5 4.6.6.1.b.2, 4.6.6.1.c, 4.7.2.b.2,and
4.7.2.c Details of the methods for implementing testing of the
SGTS and CREV filter system laboratory analysis. TRM Section 5.5.7 5.5 LA.6 3/4.11.1.4 Details of the methods for implementing requirements for Liquid Holdup Tanks. ODCM ODCMS 7.3.6 5.5 LA.6 3/4.11.2.6 Details of the methods for implementing requirements for Explosive Gas Mixtures. ODCM ODCMS 7.3.12 5.5 LA.7 4.8.1.1.2.c References to ASTM Standards and acceptance criteria for diesel fuel oil. Bases B 3.8.3: SR 3.8.3.2 5.6 LA.1 6.9.1.1, 6.9.1.2, and
6.9.1.3 Details associated with Startup Report. UFSAR Section 13.4.2.1 5.6 LA.2 6.9.3.1.a Details associated with individual specifications addressing the Core Operating Limits Report. Bases B 3.2.1: ASA and LCO TRM APPENDIX A - RELOCATED ITEMS MATRIX (page A-19) Revision No. 23
ITS CTS Description General Location Specific Location 5.6 LA.2 6.9.3.1.b Details associated with individual specifications addressing the Core Operating Limits Report. Bases B 3.2.2: ASA and LCO 5.7 LA.1 6.12.2 Compliance details relating to plant specific titles. UFSAR Section 13.1.2.2 None 6.4 LA.1 Details contained on training and replacement training for the unit staff. UFSAR Section 13.2.2 None 6.5 LA.1 Details of procedures, modification, or Operating License/Technical Specification reviews and approvals for
changes. QA Program
Description UFSAR Chapter 17, Appendix A, Sections
1.1.3, 1.1.4, 1.2, 1.3, 1.4, and 1.5 None 6.5 LA.2 Details of review and audit activities.
QA Program Description UFSAR Chapter 17, Appendix A, Sections 1.6, 1.7, 1.8, and 1.9 None 6.6 LA.2 Details of reportable events reviews.
QA Program Description UFSAR Chapter 17, Appendix A, Section 2.0 None 6.10 LA.1 Details of record retention.
QA Program Description UFSAR Chapter 17, Appendix A, Section 3.0 None 6.11 LA.1 Details of the radiation protection program. UFSAR Section 12.5.3 None 6.14 LA.1 Details of the process control program. UFSAR Section 12.5.3.8
Brunswick Unit 2 Revision No. 23 APPENDIX B TECHNICAL SPECIFICATION (TS) INSTRUMENT LIST
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-1 Revision No. 23 APPENDIX B TECHNICAL SPECIFICATION (TS) INSTRUMENT LIST
PURPOSE This appendix provides instrument tables to aid in complying with the requirements of the
instrument TS (TS Section 3.3, "INSTRUMENTATION"), TS 3.4.4, "RCS Operational
LEAKAGE," and TS 3.4.5, "RCS Leakage Detection Instrumentation." This appendix does not
define OPERABILITY for individual channels. For OPERABILITY of instrument channels, refer
to the Bases of the associated TS, the Updated Final Safety Analysis Report, or the associated Design Basis Document.
Each table in the TS Instrument List corresponds to the associated instrumentation TS. For
example; TRM Table 3.3.1.1-1, "Reactor Protecti on System Instrumentation" corresponds to TS 3.3.1.1, "Reactor Protection System (RPS) Instrumentation." Each TS Instrument List Table
includes the applicable instrument number(s) associated with each TS instrument function and
the nominal trip setpoint associated with each TS instrument function, where applicable.
Each TS instrument function with a nominal trip setpoint value specified is considered to be
properly adjusted when the "as left" value of the instrumentation is in compliance with the "as-
left" tolerance specified in the surveillance test. Additionally, the "as-found" value must be in
compliance with the Allowable Value specified in the TS. A detailed description of the
methodology used to calculate each instrument nominal trip setpoint, including explicit
uncertainties, is provided in the associated setpoint calculation.
For Nominal Trip Setpoints that are specified in units of inches, the zero reference value is
defined in the associated TS Bases except where noted.
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-2 Revision No. 44 TRM Table 3.3.1.1-1 (page 1 of 2) Reactor Protection System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
NOMINAL TRIP SETPOINT
- a. Neutron Flux-High
C51-IRM-A, B, C, D, E, F, G, H C72-K14A, B, C, D, E, F, G, H
117/125 divisions of full
scale
- b. Inop C51-IRM-A, B, C, D, E, F, G, H C72-K14A, B, C, D, E, F, G, H
NA
- 2. Average Power Range Monitors
- a. Neutron Flux-High (Setdown)
C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11
15% RTP
- b. Simulated Thermal Power-High
C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11
0.55W + 61.1% RTP (a) and 115.8% RTP c. Neutron Flux-High
C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11
117.4% RTP
- d. Inop C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11
NA
- e. 2-Out-of-4 Voter
C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11
NA
- f. OPRM Upscale C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11 NA(c) 3. Reactor Vessel Steam Dome Pressure-High
B21-PT-N023A, B, C, D B21-PTM-N023A-1, B-1, C-1, D-1 C72-K14A, B, C, D, E, F, G, H
1060 psig
- 4. Reactor Vessel Water Level-Low Level 1
B21-LT-N017A-1, B-1, C-1, D-1 B21-LTM-N017A-1, B-1, C-1, D-1 C72-K14A, B, C, D, E, F, G, H
166 inches
(continued)
(a) [0.55 (W - W) + 61.1% RTP] when reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating." The setpoint value of W is defined in plant procedures.
(b) Nominal Trip Setpoint is referenced from valve full open position.
(c) See COLR for OPRM period based detection algorithm (PBDA) setpoint limits.
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-3 Revision No. 23 TRM Table 3.3.1.1-1 (page 2 of 2) Reactor Protection System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
NOMINAL TRIP SETPOINT 5. Main Steam Isolation Valve-Closure
B21-F022A, B, C, D B21-F028A, B, C, D C72-K14A, B, C, D, E, F, G, H
1.25 inches of stem travel (b) 6. Drywell Pressure-High
C72-PT-N002A, B, C, D C72-PTM-N002A-1, B-1, C-1, D-1 C72-K14A, B, C, D, E, F, G, H
1.7 psig
- 7. Scram Discharge Volume Water Level-High
C12-LSH-N013A, B, C, D C12-LSH-4516A, B, C, D C72-K14A, B, C, D, E, F, G, H
104 gallons
- 8. Turbine Stop Valve-Closure
MS-ZS-SVRP-1, 2, 3, 4 C72-K14A, B, C, D, E, F, G, H
0.625 inches of stem travel (b) 9. Turbine Control Valve Fast Closure, Control Oil Pressure-Low
EHC-PSL-1756, 1757, 1758, 1759 C72-K14A, B, C, D, E, F, G, H
600 psig
- 10. Reactor Mode Switch-Shutdown Position
C72-CS-S1
NA
- 11. Manual Scram
C72-PB-S3A, B
NA
(b) Nominal Trip Setpoint is referenced from valve full open position.
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-4 Revision No. 44 TRM Table 3.3.1.2-1 (page 1 of 1) Source Range Monitor Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
- 1. Source Range Monitor
C51-SRM-A, B, C, D
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-5 Revision No. 23 TRM Table 3.3.2.1-1 (page 1 of 1) Control Rod Block Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
NOMINAL TRIP SETPOINT
- 1. Rod Block Monitor
- a. Low Power Range-Upscale
C51-RBMA-AR21 C51-RBMB-AR22
(a)
- b. Intermediate Power Range-Upscale
C51-RBMA-AR21 C51-RBMB-AR22
(a)
- c. High Power Range-Upscale
C51-RBMA-AR21 C51-RBMB-AR22
(a)
- d. Inop C51-RBMA-AR21 C51-RBMB-AR22
NA
2-C12-CNV-5516 19.1% rated steam flow
- 3. Reactor Mode Switch-Shutdown Position
C72-CS-S1 NA (a) Nominal Trip Setpoints specified in the COLR.
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-6 Revision No. 23 TRM Table 3.3.2.2-1 (page 1 of 1) Feedwater and Main Turbine High Water Level Trip Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
NOMINAL TRIP SETPOINT
- 1. Feedwater Pumps
- a. Reactor Vessel Water Level-High
C32-LT-N0O4A, B, C C32-LY-K602A - A1, B1, A4 C32-LY-K602C - A1, B1, A4 C32-LY-K602E - A1, B1, A4 C32-LC-R602A, B
206 inches
- 2. Main Turbine
- a. Reactor Vessel Water Level-High
C32-LT-N0O4A, B, C C32-LY-K602A - A1, B1, A4 C32-LY-K602C - A1, B1, A4 C32-LY-K602E - A1, B1, A4 C32-LC-R602A, B
206 inches
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-7 Revision No. 39 TRM Table 3.3.3.1-1 (page 1 of 1) Post Accident Monitoring Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
- 1. Reactor Vessel Pressure
- a. -150 inches to +150 inches
- b. 0 inches to +210 inches
- c. +150 inches to +550 inches
- 3. Suppression Chamber Water Level
- 4. Suppression Chamber Water Temperature
- 5. Suppression Chamber Pressure
- 6. Drywell Pressure
- 7. Drywell Temperature
- 8. PCIV Position
- 9. (Not Used.)
- 10. Drywell Area Radiation
B21-PI-R605A, B
B21-LI-R610, B21-LR-R615
B21-LI-R604A, B
B21-LI-R605A, B
CAC-LI-2601-1, CAC-LR-2602
CAC-TR-4426-1A CAC-TR-4426-2A CAC-TY-4426-1, 2
CAC-PI-1257-2A, B
CAC-PI-4176, CAC-PR-1257-1
CAC-TR-4426-1A, B CAC-TR-4426-2A, B CAC-TY-4426-1, 2
See TRM Table 3.3.3.1-2, "Primary Containment Isolation Valve Position Indication."
D22-RI-4195 OR D22-RI-4196 OR D22-RR-4195 AND D22-RI-4197 OR D22-RI-4198 OR D22-RR-4197
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-8 Revision No. 23 TRM Table 3.3.3.1-2 (page 1 of 5) Primary Containment Isolation Valve Position Indication VALVE NUMBER VALVE DESCRIPTION LOCATION OF DISPLAY 2-B21-F016 MAIN STEAM LINE DRAIN INBOARD ISOLATION H12-P601 2-B21-F019 MAIN STEAM LINE DRAIN OUTBOARD ISOLATION H12-P601 2-B21-F022A INBOARD MSIV A H12-P601 2-B21-F022B INBOARD MSIV B H12-P601 2-B21-F022C INBOARD MSIV C H12-P601 2-B21-F022D INBOARD MSIV D H12-P601 2-B21-F028A OUTBOARD MSIV A H12-P601 2-B21-F028B OUTBOARD MSIV B H12-P601 2-B21-F028C OUTBOARD MSIV C H12-P601 2-B21-F028D OUTBOARD MSIV D H12-P601 2-B21-F032A FEEDWATER SUPPLY LINE A ISOLATION H12-P603 2-B21-F032B FEEDWATER SUPPLY LINE B ISOLATION H12-P603 2-B32-FO19 SAMPLE LINE INBOARD ISOLATION H12-P603 2-B32-F020 SAMPLE LINE OUTBOARD ISOLATION H12-P603 2-B32-V22 RECIRC PUMP 2A SEAL INJECTION H12-P603 2-B32-V30 RECIRC PUMP 2B SEAL INJECTION H12-P603 2-CAC-SV-1200B CAC-AT-1261 INBOARD SAMPLE INLET XU-2 2-CAC-SV-1205E CAC-AT-4409 PRIMARY CONTAINMENT INBOARD SAMPLE XU-2 2-CAC-SV-1209A CAC-AT-4409 PRIMARY CONTAINMENT INBOARD SAMPLE XU-2 2-CAC-SV-1209B CAC-AT-4409 PRIMARY CONTAINMENT INBOARD SAMPLE XU-2 2-CAC-SV-1211E CAC-AT-1262 INBOARD SAMPLE RETURN XU-2 2-CAC-SV-1211F CAC-AT-1262 INBOARD SAMPLE INLET XU-2 2-CAC-SV-1213A CAC-AT-4409 TORUS INBOARD SAMPLE XU-2 2-CAC-SV-1215E CAC-AT-4409 INBOARD SAMPLE RETURN XU-2 2-CAC-SV-1218A CAC-AT-4410 TORUS INBOARD SAMPLE XU-2 2-CAC-SV-1225B COMMON INBOARD SAMPLE RETURN XU-2 2-CAC-SV-1227A CAC-AT-4410 PRIMARY CONTAINMENT INBOARD SAMPLE XU-2 2-CAC-SV-1227B CAC-AT-4410 PRIMARY CONTAINMENT INBOARD SAMPLE XU-2 2-CAC-SV-1227C
CAC-AT-1260 INBOARD SAMPLE INLET XU-2 (continued)
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-9 Revision No. 23 TRM Table 3.3.3.1-2 (page 2 of 5) Primary Containment Isolation Valve Position Indication VALVE NUMBER VALVE DESCRIPTION LOCATION OF DISPLAY 2-CAC-SV-1227E CAC-AT-4410 PRIMARY CONTAINMENT INBOARD SAMPLE XU-2 2-CAC-SV-1231B CAC-AT-4410 INBOARD SAMPLE RETURN XU-2 2-CAC-SV-1260 CAC-AT-1260 OUTBOARD SAMPLE INLET XU-2 2-CAC-SV-1261 CAC-AT-1261 OUTBOARD SAMPLE INLET XU-2 2-CAC-SV-1262 CAC-AT-1262 OUTBOARD SAMPLE INLET XU-2 2-CAC-SV-3439 CAC-AT-1262 OUTBOARD SAMPLE RETURN XU-2 2-CAC-SV-3440 COMMON OUTBOARD SAMPLE RETURN XU-2 2-CAC-SV-4409-1 CAC-AT-4409 TORUS OUTBOARD SAMPLE XU-51 2-CAC-SV-4409-2 CAC-AT-4409 PRIMARY CONTAINMENT OUTBOARD SAMPLE XU-51 2-CAC-SV-4409-3 CAC-AT-4409 PRIMARY CONTAINMENT OUTBOARD SAMPLE XU-51 2-CAC-SV-4409-4 CAC-AT-4409 PRIMARY CONTAINMENT OUTBOARD SAMPLE XU-51 2-CAC-SV-4410-1 CAC-AT-4410 TORUS OUTBOARD SAMPLE XU-51 2-CAC-SV-4410-2 CAC-AT-4410 PRIMARY CONTAINMENT OUTBOARD SAMPLE XU-51 2-CAC-SV-4410-3 CAC-AT-4410 PRIMARY CONTAINMENT OUTBOARD SAMPLE XU-51 2-CAC-SV-4410-4 CAC-AT-4410 PRIMARY CONTAINMENT OUTBOARD SAMPLE XU-51
2-CAC-SV-4540 CAC-AT-4409 OUTBOARD SAMPLE RETURN XU-51 2-CAC-SV-4541 CAC-AT-4410 OUTBOARD SAMPLE RETURN XU-51 2-CAC-V4 INBOARD PRIMARY CONTAINMENT N2 INERTING INLET XU-51 2-CAC-V5 SUPPRESSION POOL N2 INLET XU-51 2-CAC-V6 DRYWELL N2 INLET XU-51 2-CAC-V7 INBOARD SUPPRESSION POOL PURGE EXHAUST XU-51 2-CAC-V8 OUTBOARD SUPPRESSION POOL PURGE EXHAUST XU-51 2-CAC-V9 INBOARD DRYWELL PURGE EXHAUST XU-51 2-CAC-V10 OUTBOARD DRYWELL PURGE EXHAUST XU-51 2-CAC-V15 PRIMARY CONTAINMENT PURGE AIR INLET XU-51 2-CAC-V16 REACTOR BUILDING TO SU PPRESSION CHAMBER VACUUM BREAKER XU-51 2-CAC-V17 REACTOR BUILDING TO SU PPRESSION CHAMBER VACUUM BREAKER XU-51 2-CAC-V22 SUPPRESSION POOL 2" EXHAUST XU-51 2-CAC-V23 DRYWELL 2" EXHAUST XU-51 2-CAC-V49 DRYWELL HEAD INBOARD PURGE EXHAUST XU-51 2-CAC-V50 DRYWELL HEAD OUTBOARD PURGE EXHAUST XU-51 2-CAC-V55 DRYWELL CAD N2 INJECTION SOLENOID XU-51 2-CAC-V56
DRYWELL CAD N2 INJECTION SOLENOID XU-51 (continued)
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-10 Revision No. 23 TRM Table 3.3.3.1-2 (page 3 of 5) Primary Containment Isolation Valve Position Indication VALVE NUMBER VALVE DESCRIPTION LOCATION OF DISPLAY 2-CAC-V160
SUPPRESSION POOL CAD N2 INJECTION INLET
XU-51 2-CAC-V161 DRYWELL CAD N2 INJECTION INLET XU-51 2-CAC-V162 SUPPRESSION POOL CAD N2 INJECTION INLET XU-51 2-CAC-V163 DRYWELL CAD N2 INJECTION INLET XU-51 2-CAC-V172 SUPPRESSION POOL PURGE EXHAUST SOLENOID XU-51 2-CAC-V216 HARDENED WETWELL VENT OUTBOARD ISOLATION XU-51 2-C51-J004A A TIP BALL VALVE AND SHEAR VALVE ASSEMBLY H12-P607 2-C51-J004B B TIP BALL VALVE AND SHEAR VALVE ASSEMBLY H12-P607 2-C51-J004C C TIP BALL VALVE AND SHEAR VALVE ASSEMBLY H12-P607 2-C51-J004D D TIP BALL VALVE AND SHEAR VALVE ASSEMBLY H12-P607 2-E11-F007A MINIMUM FLOW BYPASS VALVE A TO SUPPRESSION POOL H12-P601 2-E11-F007B MINIMUM FLOW BYPASS VALVE B TO SUPPRESSION POOL H12-P601 2-E11-F008 SHUTDOWN COOLING OUTBOARD SUCTION H12-P601 2-E11-F009 SHUTDOWN COOLING INBOARD SUCTION THROTTLE H12-P601 2-E11-F011A RHR HEAT EXCHANGER 2A DRAIN TO SUPPRESSION POOL H12-P601 2-E11-F011B RHR HEAT EXCHANGER 2B DRAIN TO SUPPRESSION POOL H12-P601 2-E11-F015A LPCI A INBOARD INJECTION H12-P601 2-E11-F015B LPCI B INBOARD INJECTION H12-P601 2-E11-F016A DRYWELL SPRAY A OUTBOARD ISOLATION H12-P601 2-E11-F016B DRYWELL SPRAY B OUTBOARD ISOLATION H12-P601 2-E11-F017A LPCI A OUTBOARD INJECTION H12-P601 2-E11-F017B LPCI B OUTBOARD INJECTION H12-P601 2-E11-F020A RHR PUMP 2A AND 2C TORUS SUCTION H12-P601 2-E11-F020B RHR PUMP 2B AND 2D TORUS SUCTION H12-P601 2-E11-F021A DRYWELL SPRAY A INBOARD ISOLATION H12-P601 2-E11-F021B DRYWELL SPRAY B INBOARD ISOLATION H12-P601 2-E11-F024A SUPPRESSION POOL COOLING A ISOLATION H12-P601 2-E11-F024B SUPPRESSION POOL COOLING B ISOLATION H12-P601 2-E11-F027A SUPPRESSION POOL SPRAY A ISOLATION H12-P601 2-E11-F027B SUPPRESSION POOL SPRAY B ISOLATION H12-P601 2-E11-F028A SUPPRESSION POOL SPRAY A ISOLATION H12-P601 2-E11-F028B SUPPRESSION POOL SPRAY B ISOLATION H12-P601 (continued)
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-11 Revision No. 23 TRM Table 3.3.3.1-2 (page 4 of 5) Primary Containment Isolation Valve Position Indication VALVE NUMBER VALVE DESCRIPTION LOCATION OF DISPLAY 2-E11-F103A
RHR HEAT EXCHANGER 2A OUTBOARD VENT
H12-P601 2-E11-F103B RHR HEAT EXCHANGER 2B OUTBOARD VENT H12-P601 2-E21-F001A SUPPRESSION POOL A SUCTION H12-P601 2-E21-FO01B SUPPRESSION POOL B SUCTION H12-P601 2-E21-FO04A CORE SPRAY PUMP 2A OUTBOARD INJECTION H12-P601 2-E21-FO04B CORE SPRAY PUMP 2B OUTBOARD INJECTION H12-P601 2-E21-FO05A CORE SPRAY PUMP 2A INBOARD INJECTION H12-P601 2-E21-FO05B CORE SPRAY PUMP 2B INBOARD INJECTION H12-P601 2-E21-FO15A CORE SPRAY FULL FLOW TEST BYPASS H12-P601 2-E21-FO15B CORE SPRAY FULL FLOW TEST BYPASS H12-P601 2-E21-FO31A CORE SPRAY MINIMUM FLOW BYPASS H12-P601 2-E21-FO31B CORE SPRAY MINIMUM FLOW BYPASS H12-P601 2-E41-F002 HPCI STEAM SUPPLY INBOARD ISOLATION H12-P601 2-E41-F003 HPCI STEAM SUPPLY OUTBOARD ISOLATION H12-P601 2-E41-F006 HPCI INJECTION H12-P601 2-E41-F012 HPCI MINIMUM FLOW BYPASS TO SUPPRESSION POOL H12-P601 2-E41-F042 HPCI SUPPRESSION POOL SUCTION H12-P601 2-E41-F075 HPCI TURBINE EXHAUST VACUUM BREAKER H12-P601 2-E41-F079 HPCI TURBINE EXHAUST VACUUM BREAKER H12-P601 2-E51-F007 RCIC STEAM SUPPLY INBOARD ISOLATION H12-P601 2-E51-F008
RCIC STEAM SUPPLY OUTBOARD ISOLATION H12-P601 (continued)
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-12 Revision No. 24 TRM Table 3.3.3.1-2 (page 5 of 5) Primary Containment Isolation Valve Position Indication VALVE NUMBER VALVE DESCRIPTION LOCATION OF DISPLAY 2-E51-F013
RCIC INJECTION
H12-P601 2-E51-F019 RCIC MINIMUM FLOW BYPASS TO SUPPRESSION POOL H12-P601 2-E51-F031 RCIC SUPPRESSION POOL SUCTION H12-P601 2-E51-F062 RCIC TURBINE EXHAUST VACUUM BREAKER H12-P601 2-E51-F066 RCIC TURBINE EXHAUST VACUUM BREAKER H12-P601 2-G16-F003 DRYWELL FLOOR DRAIN INBOARD ISOLATION H12-P601 2-G16-F004 DRYWELL FLOOR DRAIN OUTBOARD ISOLATION H12-P601 2-G16-F019 DRYWELL EQUIPMENT DRAIN INBOARD ISOLATION H12-P601 2-G16-F020 DRYWELL EQUIPMENT DRAIN OUTBOARD ISOLATION H12-P601 2-G31-F001 RWCU INLET INBOARD ISOLATION H12-P601 2-G31-F004 RWCU INLET OUTBOARD ISOLATION H12-P601 2-G31-F042 RWCU RETURN TO REACTOR H12-P603 2-RCC-SV-1222B RECIRC PUMP 2A COOLER OUTLET SAMPLE XU-2 2-RCC-SV-1222C RECIRC PUMP 2B COOLER OUTLET SAMPLE XU-2 2-RCC-V28 RBCCW DRYWELL DISCHARGE HEADER ISOLATION XU-2 2-RCC-V52 RBCCW DRYWELL SUPPLY HEADER ISOLATION XU-2 2-RNA-SV-5251 BACKUP NITROGEN SUPPLY TO DRYWELL ISOLATION VALVE - DIVISION II XU-51 2-RNA-SV-5253 BACKUP NITROGEN SUPPLY TO DRYWELL ISOLATION VALVE - DIVISION I XU-51 2-RNA-SV-5261 NON-INTERRUPTIBLE REACTOR INSTRUMENT AIR SOLENOID XU-51 2-RNA-SV-5262 NON-INTERRUPTIBLE REACTOR INSTRUMENT AIR SOLENOID XU-51 2-RXS-SV-4186 LIQUID SAMPLE RETURN INBOARD ISOLATION XU-75 2-RXS-SV-4187 LIQUID SAMPLE RETURN OUTBOARD ISOLATION XU-79 2-RXS-SV-4188 GAS SAMPLE RETURN INBOARD ISOLATION XU-75 2-RXS-SV-4189
GAS SAMPLE RETURN OUTBOARD ISOLATION XU-79 TRM TS Instrument List Appendix B
Brunswick Unit 2 B-13 Revision No. 23 TRM Table 3.3.3.2-1 (page 1 of 1) Remote Shutdown Monitoring Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
- 1. Reactor Vessel Pressure
- 3. Suppression Chamber Water Level
- 4. Suppression Chamber Water Temperature
- 5. Drywell Pressure
- 6. Drywell Temperature
- 7. Residual Heat Removal System Flow
C32-PI-3332, C32-PT-3332
B21-LT-N017D-3, B21-LSH-N017D-3 B21-LI-3331, B21-LI-R604BX, B21-LT-3331, B21-LT-N026B
CAC-LI-3342, CAC-LT-3342
CAC-TR-778-6 or CAC-TR-778-7
CAC-PI-3341, CAC-PT-3341
CAC-TR-778-1 or CAC-TR-778-3 or CAC-TR-778-4
E11-FT-3338, E11-FI-3338, E11-FY-3338
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-14 Revision No. 23 TRM Table 3.3.4.1-1 (page 1 of 1) Anticipated Transient Without Scram Recirculation Pump Trip Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
NOMINAL TRIP SETPOINT
- 1. Reactor Vessel Water Level-Low Level 2
B21-LT-N024A-2, B-2 B21-LT-N025A-2, B-2 B21-LTM-N024A-2, B-2 B21-LTM-N025A-2, B-2
105 inches
- 2. Reactor Vessel Steam Dome Pressure-High
B21-PT-N045A, B, C, D B21-PTM-N045A, B, C, D
1137.8 psig
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-15 Revision No. 23 TRM Table 3.3.5.1-1 (page 1 of 2) Emergency Core Cooling System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
NOMINAL TRIP SETPOINT
- 1. Core Spray System
- a. Reactor Vessel Water Level-Low Level 3
B21-LT-N031A, B, C, D B21-LTS-N031A-4, B-4, C-4, D-4
45 inches
- b. Drywell Pressure-High
E11-PT-N011A, B, C, D E11-PTS-N011A-2, B-2, C-2, D-2
1.7 psig
- c. Reactor Steam Dome Pressure-Low
B21-PT-N021A, B, C, D, B21-PTS-N021A-2, B-2, C-2, D-2
410 psig
- d. Core Spray Pump Start-Time Delay Relay
E21-K16A, B STR/2A-1, STR/2A-2 STR/2B-1, STR/2B-2
15 seconds
- 2. Low Pressure Coolant Injection (LPCI) System
- a. Reactor Vessel Water Level-Low Level 3
B21-LT-N031A, B, C, D B21-LTS-N031A-4, B-4, C-4, D-4
45 inches
- b. Drywell Pressure-High
E11-PT-N011A, B, C, D E11-PTM-N011A-1, B-1, C-1, D-1
1.7 psig
- c. Reactor Steam Dome Pressure-Low
B21-PT-N021A, B, C, D B21-PTS-N021A-2, B-2, C-2, D-2
410 psig
- d. Reactor Steam Dome Pressure-Low (Recirculation Pump Discharge Valve Permissive)
B21-PT-N021A, B, C, D B21-PTM-N021A-1, B-1, C-1, D-1
310 psig
- e. Reactor Vessel Shroud Level
B21-LT-N036, B21-LT-N037 B21-LTM-N036-1, B21-LTM-N037-1
-47.4 inches
- f. RHR Pump Start-Time Delay Relay
STR/2A-1, STR/2A-2, STR/2B-1, STR/2B-2, STR/1A-3, STR/1A-4, STR/1B-3, STR/1B-4
10 seconds
- 3. High Pressure Coolant Injection (HPCI) System
- a. Reactor Vessel Water Level-Low Level 2
B21-LT-N031A, B, C, D B21-LTS-N031A-2, B-2, C-2, D-2
105 inches
- b. Drywell Pressure-High
E11-PT-N011A, B, C, D E11-PTS-N011A-2, B-2, C-2, D-2
1.7 psig
(continued)
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-16 Revision No. 23 TRM Table 3.3.5.1-1 (page 2 of 2) Emergency Core Cooling System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
NOMINAL TRIP SETPOINT
- 3. High Pressure Coolant Injection (HPCI) System (continued)
- c. Reactor Vessel Water Level-High
B21-LT-N017 B-2, D-2 B21-LTM-N017 B-2, D-2
206 inches
- d. Condensate Storage Tank Level-Low
E41-LS-N0O2, E41-LS-N003
23 feet 5 inches
- e. Suppression Chamber Water Level-High
E41-LSH-N015A, B
-25 inches
- 4. Automatic Depressurization System (ADS) Trip System A
- a. Reactor Vessel Water Level-Low Level 3
B21-LT-N031B, D B21-LTS-N031B-3, D-3
45 inches
- b. ADS Timer
B21-TDPU-K5A
83 seconds
- c. Reactor Vessel Water Level-Low Level 1
B21-LT-N042B B21-LTM-N042B-1
166 inches
- d. Core Spray Pump Discharge Pressure-High
E21-PS-N008B E21-PS-N009B
115 psig
E11-PS-N016B, D E11-PS-N020B, D
115 psig
- 5. ADS Trip System B
- a. Reactor Vessel Water Level-Low Level 3
B21-LT-N031A, C B21-LTS-N031A-3, C-3
45 inches
- b. ADS Timer
B21-TDPU-K5B
83 seconds
- c. Reactor Vessel Water Level-Low Level 1
B21-LT-N042A B21-LTM-N042A-1
166 inches
- d. Core Spray Pump Discharge Pressure-High
E21-PS-N008A E21-PS-N009A
115 psig
115 psig
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-17 Revision No. 23 TRM Table 3.3.5.2-1 (page 1 of 1) Reactor Core Isolation Cooling System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
NOMINAL TRIP SETPOINT
- 1. Reactor Vessel Water Level-Low Level 2
B21-LT-N031A, B, C, D B21-LTM-N031A-1, B-1, C-1, D-1
105 inches
- 2. Reactor Vessel Water Level-High
B21-LT-N017A-2, C-2 B21-LTM-N017A-2, C-2
206 inches
- 3. Condensate Storage Tank Level-Low
E51-LSL-4463 E51-LSL-4464
23 feet 1 inch
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-18 Revision No. 28 TRM Table 3.3.6.1-1 (page 1 of 5) Primary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
NOMINAL TRIP SETPOINT
- 1. Main Steam Line Isolation
- a. Reactor Vessel Water Level-Low Level 3
B21-LT-N024A-1, B-1 B21-LT-N025A-1, B-1 B21-LTS-N024A-1-2, B-1-2 B21-LTS-N025A-1-2, B-1-2
45 inches
- b. Main Steam Line Pressure-Low
B21-PT-N015A, B, C, D B21-PTM-N015A-1, B-1, C-1, D-1
835 psig c. Main Steam Line Flow-High
B21-PDT-N006A, B, C, D B21-PDT-N007A, B, C, D B21-PDT-N008A, B, C, D B21-PDT-N009A, B, C, D B21-PDTM-N006A-1, B-1, C-1, D-1 B21-PDTM-N007A-1, B-1, C-1, D-1 B21-PDTM-N008A-1, B-1, C-1, D-1 B21-PDTM-N009A-1, B-1, C-1, D-1
137% rated steam flow
- d. Condenser Vacuum-Low
B21-PT-N056A, B, C, D B21-PTM-N056A-1, B-1, C-1, D-1
10 inches Hg vacuum
- e. Main Steam Isolation Valve Pit Temperature-High
B21-TS-N010A, B, C, D
190°F f. Main Steam Line Flow-High (Not in Run)
B21-PDTS-N006A-2 B21-PDTS-N007B-2 B21-PDTS-N008C-2 B21-PDTS-N009D-2
30% rated steam flow 2. Primary Containment Isolation
- a. Reactor Vessel Water Level-Low Level 1
B21-LT-N017A-1, B-1, C-1, D-1 B21-LTM-N017A-1, B-1, C-1, D-1
166 inches
- b. Drywell Pressure-High
C72-PT-N002A, B, C, D C72-PTM-N002A-1, B-1, C-1, D-1 E11-PT-N011A, B, C, D E11-PTS-N011A-2, B-2, C-2, D-2
1.7 psig
- c. Main Stack Radiation-High
2-D12-RM-80S
(a)
- d. Reactor Building Exhaust Radiation-High
D12-RM-K609A, B D12-RE-N010A, B
4 mR/hr (continued)
(a) Nominal Trip Setpoint established in accordance with the methodology in the Offsite Dose Calculation Manual.
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-19 Revision No. 23 TRM Table 3.3.6.1-1 (page 2 of 5) Primary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
NOMINAL TRIP SETPOINT
- 3. High Pressure Coolant Injection (HPCI) System Isolation
- a. HPCI Steam Line Flow-High
E41-PDTM-N004-1, E41-PDTM-N005-1 E41-PDTS-N004-2, E41-PDTS-N005-2
220% rated steam flow
- b. HPCI Steam Line Flow-High Time Delay Relay
E41-TDR-K33, E41-TDR-K43 5 seconds
- c. HPCI Steam Supply Line Pressure-Low
E41-PSL-N001A, B, C, D
115 psig
E41-PSH-N012A, B, C, D
7 psig
- e. Drywell Pressure-High
E11-PT-N011C, D E11-PTS-N011C-2, D-2
1.7 psig
- f. HPCI Steam Line Area Temperature-High B21-XY-5948A Ch. A5-2: E41-TE-3488 B21-XY-5948B Ch. A5-2: E41-TE-3489
165°F g. HPCI Steam Line Tunnel Ambient Temperature-High
B21-XY-5948A Ch. A2-2: E41-TE-3314 Ch. A5-1: E51-TE-N025C B21-XY-5948B Ch. A5-1: E51-TE-N025D
165°F 190°F 190°F
- h. HPCI Steam Line Tunnel Differential Temperature-High
B21-XY-5948A Ch. A6-1: E51-TE-N026C and E51-TE-N027C B21-XY-5948B Ch. A6-1: E51-TE-N026D and E51-TE-N027D
47°F
- i. HPCI Equipment Area Temperature-High
B21-XY-5948A Ch. A3-2: E41-TE-3316 Ch. A4-2: E41-TE-3318 Ch. A1-1: E41-TE-N030A B21-XY-5948B Ch. A2-2: E41-TE-3315 Ch. A3-2: E41-TE-3317 Ch. A4-2: E41-TE-3354 Ch. A1-1: E41-TE-N030B
165°F (continued)
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-20 Revision No. 23 TRM Table 3.3.6.1-1 (page 3 of 5) Primary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
NOMINAL TRIP SETPOINT
- 4. Reactor Core Isolation Cooling (RCIC) System Isolation
- a. RCIC Steam Line Flow-High
E51-PDTM-N017-1, E51-PDTM-N018-1 E51-PDTS-N017-2, E51-PDTS-N018-2
220% rated steam flow
- b. RCIC Steam Line Flow-High Time Delay Relay
E51-TDR-K32, E51-TDR-K12
5 seconds
- c. RCIC Steam Supply Line Pressure-Low
E51-PS-N019A, B, C, D
70
E51-PS-N012A, B, C, D
5 psig
- e. Drywell Pressure-High
E11-PT-N011A, B E11-PTS-N011A-2, B-2
1.7 psig
- f. RCIC Steam Line Area Temperature-High
B21-XY-5949A Ch. A6-4: E51-TE-3487 B21-XY-5949B Ch. A4-4: E51-TE-3320
165°F g. RCIC Steam Line Tunnel Ambient Temperature-High
B21-XY-5949A Ch. A3-4: E51-TE-3319 Ch. A3-3: E51-TE-N025A B21-XY-5949B Ch. A3-3: E51-TE-N025B
165°F 190°F 190°F
- h. RCIC Steam Line Tunnel and Area Temperature-High Time Delay B21-XY-5949A Ch. A3-3: E51-TE-N025A Ch. A3-4: E51-TE-3319 Ch. A4-3: E51-TE-N026A and E51-TE-N027A Ch. A6-4: E51-TE-3487 B21-XY-5949B Ch. A3-3: E51-TE-N025B Ch. A4-3: E51-TE-N026B and E51-TE-N027B Ch. A4-4: E51-TE-3320
27 minutes
- i. RCIC Steam Line Tunnel Differential Temperature-High
B21-XY-5949A Ch. A4-3: E51-TE-N026A and E51-TE-N027A B21-XY-5949B Ch. A4-3: E51-TE-N026B and E51-TE-N027B
47°F
(continued)
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-21 Revision No. 23 TRM Table 3.3.6.1-1 (page 4 of 5) Primary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
NOMINAL TRIP SETPOINT
- 4. RCIC System Isolation (continued)
- j. RCIC Equipment Area Temperature-High
B21-XY-5949A Ch. A4-4: E51-TE-3321 Ch. A5-4: E51-TE-3323 Ch. A1-3: E51-TE-N023A B21-XY-5949B Ch. A5-4: E51-TE-3322 Ch. A6-3: E51-TE-3355 Ch. A1-3: E51-TE-N023B
165°F k. RCIC Equipment Area Differential Temperature-High
B21-XY-5949A Ch. A2-3: E51-TE-N021A and E51-TE-N022A B21-XY-5949B Ch. A2-3: E51-TE-N021B and E51-TE-N022B
47°F
- 5. Reactor Water Cleanup (RWCU) System Isolation
- a. Differential Flow-High
B21-XY-5949B G31-FT-N012 G31-FT-N041 G31-FT-N036
43 gpm
- b. Differential Flow-High Time Delay
B21-XY-5949B G31-FT-N012 G31-FT-N041 G31-FT-N036
28.5 minutes
- c. Area Temperature-High
B21-XY-5949A Ch. A1-1: G31-TE-N016A Ch. A2-1: G31-TE-N016C Ch. A3-1: G31-TE-N016E B21-XY-5949B Ch. A1-1: G31-TE-N016B Ch. A2-1: G31-TE-N016D Ch. A3-1: G31-TE-N016F
140°F d. Area Ventilation Differential Temperature-High
B21-XY-5949A Ch. A4-1: G31-TE-N022A and G31-TE-N023A Ch. A5-1: G31-TE-N022C and G31-TE-N023C Ch. A6-1: G31-TE-N022E and G31-TE-N023E B21-XY-5949B Ch. A4-1: G31-TE-N022B and G31-TE-N023B Ch. A5-1: G31-TE-N022D and G31-TE-N023D Ch. A6-1: G31-TE-N022F and G31-TE-N023F
47°F
(continued)
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-22 Revision No. 48 TRM Table 3.3.6.1-1 (page 5 of 5) Primary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
NOMINAL TRIP SETPOINT
- 5. Reactor Water Cleanup (RWCU) System Isolation (continued)
- e. Piping Outside RWCU Rooms Area Temperature-High
B21-XY-5949A Ch. A1-2: G31-TE-5931 B21-XY-5949B Ch. A1-2: G31-TE-5932
115°F f. SLC System Initiation
C41A-S1 NA
- g. Reactor Vessel Water Level-Low Level 2
B21-LT-N024A-1, B-1 B21-LT-N025A-1, B-1 B21-LTM-N024A-1-1, B-1-1 B21-LTM-N025A-1-1, B-1-1
105 inches
- 6. RHR Shutdown Cooling System Isolation
- a. Reactor Steam Dome Pressure-High
B32-PS-N018A-1, B
130.8 psig
- b. Reactor Vessel Water Level- Low Level 1
- 7. Traversing In-Core Probe Isolation
- a. Reactor Vessel Water Level-Low Level 1
- b. Drywell Pressure-High
B21-LT-N017A-1, B-1, C-1, D-1 B21-LTM-N017A-1, B-1, C-1, D-1
B21-LT-N017A-1, B-1 B21-LTM-N017A-1, B-1
C72-PT-N002A, B C72-PTM-N002A-1, B-1 166 inches
166 inches
1.7 psig TRM TS Instrument List Appendix B
Brunswick Unit 2 B-23 Revision No. 23 TRM Table 3.3.6.2-1 (page 1 of 1) Secondary Containment Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
NOMINAL TRIP SETPOINT
- 1. Reactor Vessel Water Level-Low Level 2
B21-LT-N024A-1, B-1 B21-LT-N025A-1, B-1 B21-LTM-N024A-1-1, B-1-1 B21-LTM-N025A-1-1, B-1-1
105 inches
- 2. Drywell Pressure-High
C72-PT-N002A, B, C, D C72-PTM-N002A-1, B-1, C-1, D-1
1.7 psig
- 3. Reactor Building Exhaust Radiation-High
D12-RE-N010A, B D12-RM-K609A, B
4 mR/hr
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-24 Revision No. 34 TRM Table 3.3.7.1-1 (page 1 of 1) Control Room Emergency Ventilation System Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
NOMINAL TRIP SETPOINT
- 1. Control Building Air Intake Radiation-High
1-D22-RM-K600-1-2, 1-D22-RE-N001-1-2 1-D22-RM-K600-1-3, 1-D22-RE-N001-1-3
7 mR/hr 2. Unit 2 Secondary Containment Isolation - CREV Auto-Start
- a. Reactor Vessel Water Level-Low Level 2
- b. Drywell Pressure-High
B21-LT-N024A-1, B-1 B21-LT-N025A-1, B-1 B21-LTM-N024A-1-1, B-1-1 B21-LTM-N025A-1-1, B-1-1
C72-PT-N002A, B, C, D C72-PTM-N002A-1, B-1, C-1, D-1
105 inches
1.7 psig TRM TS Instrument List Appendix B
Brunswick Unit 2 B-25 Revision No. 23 TRM Table 3.3.7.2-1 (page 1 of 1) Condenser Vacuum Pump Isolation Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
NOMINAL TRIP SETPOINT
- 1. Main Steam Line Radiation-High
D12-RM-K603A, B, C, D
2.8 times
background radiation (mR/hr)
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-26 Revision No. 63 TRM Table 3.3.8.1-1 (page 1 of 1) Loss of Power Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
NOMINAL TRIP SETPOINT
- 1. 4.16 kV Emergency Bus Undervoltage (Loss of Voltage)
- a. Bus Undervoltage
Relay Type - IAV53K Device Number - 27/59E
3255 V (a) 93 V(b)(c) b. Time Delay
Relay Type - IAV53K Device Number - 27/59E
1.15 seconds (e) 2. 4.16 kV Emergency Bus Undervoltage (Degraded Voltage)
- a. Bus Undervoltage
Device Number - 27/DV
3732 V (a) 106.64 V (b)(d) b. Time Delay
Device Number - 27/DV
10 seconds
(a) Based on 4.16 kV bus voltage.
(b) Based on 120 V bus voltage.
(c) The Allowable Value based on 4.16 kV bus voltage is specified in the TS. The Allowable Value based on 120 V bus voltage is 89.0 V to 97.1 V.
(d) The Allowable Value based on 4.16 kV bus voltage is specified in the TS. The Allowable Value based on 120 V bus voltage is 105.9 V to 107.1 V.
(e) This is an inverse time delay relay. The time delay is inversely related to the ratio of reset voltage to setpoint voltage.
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-27 Revision No. 64 TRM Table 3.3.8.2-1 (page 1 of 1) Reactor Protection System (RPS) Electric Power Monitoring TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
NOMINAL TRIP SETPOINT
- 1. RPS Motor Generator Set Electric Power Monitoring Assembly a. Overvoltage
2-C72-EPA1, 2, 3, 4
125 V b. Undervoltage
2-C72-EPA1, 2, 3, 4 109 V
- c. Underfrequency
2-C72-EPA1, 2, 3, 4 57.7 Hz
- 2. RPS Alternate Power Supply Electric Power Monitoring Assembly
- a. Overvoltage
2-C72-EPA5, 6
125 V b. Undervoltage
2-C72-EPA5, 6 109 V
- c. Underfrequency
2-C72-EPA5, 6 57.7 Hz
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-28 Revision No. 23 TRM Table 3.4.4-1 (page 1 of 1) Reactor Coolant System Operational LEAKAGE TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
- 1. Drywell Floor Drain Sump Flow Monitor
G16-FQ-K601, G16-FYQ-K601, G16-FT-N003
- 2. Drywell Equipment Drain Sump Flow Monitor
G16-FQ-K603, G16-FYQ-K603, G16-FT-N013
TRM TS Instrument List Appendix B
Brunswick Unit 2 B-29 Revision No. 23 TRM Table 3.4.5-1 (page 1 of 1) Reactor Coolant System Leakage Detection Instrumentation TECHNICAL SPECIFICATION FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
- 1. Drywell Floor Drain Sump Flow Monitor
G16-FQ-K601, G16-FYQ-K601, G16-FT-N003
- 2. Primary Containment Atmosphere Particulate Monitor
CAC-AQH-1260-1 CAC-AQH-1262-1
- 3. Atmosphere Gaseous Radioactivity Monitor CAC-AQH-1260-3 CAC-AQH-1262-3
Brunswick Unit 2 Revision No. 23 APPENDIX C TECHNICAL REQUIREMENTS MANUAL (TRM) INSTRUMENT LIST
TRM TRM Instrument List Appendix C
Brunswick Unit 2 C-1 Revision No. 23 APPENDIX C TECHNICAL REQUIREMENTS MANUAL (TRM) INSTRUMENT LIST
PURPOSE This appendix provides instrument tables to aid in complying with the TRM instrumentation
requirements. This appendix does not define OPERABILITY for individual channels. For
OPERABILITY of instrument channels, refer to the Bases of the associated TRM Specification, the Updated Final Safety Analysis Report, or the associated Design Basis Document.
Each table in the TRM Instrument List corresponds to the associated TRM. For example; TRM
Table 3.3-2, "Control Rod Block Instrumentation," corresponds to TRM 3.3, "Control Rod Block
Instrumentation." Each TRM Instrument List Table includes the applicable instrument
number(s) associated with each TRM instrument function and the trip setpoint associated with
each TRM instrument function, where applicable.
Each TRM instrument function with a trip setpoint value specified is considered to be properly
adjusted when the "as left" value of the instrumentation is in compliance with the trip setpoint
specified in the TRM and in compliance with the "as-left" tolerance specified in the surveillance
test. Additionally, the "as found" value must be in compliance with the Allowable Value
specified in the TRM.
TRM TRM Instrument List Appendix C
Brunswick Unit 2 C-2 Revision No. 44 TRM Table 3.3-2 (page 1 of 1) Control Rod Block Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
TRIP SETPOINT
- 1. Average Power Range Monitors
- a. Simulated Thermal Power - High
C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11
0.55W + 53.5% RTP (a) and 108.0% RTP
- b. Inoperative
C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11
NA
- c. Downscale
C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11
2.4% RTP
- d. Simulated Thermal Power - High (Setdown)
C51-APRM1-AR51 C51-APRM2-AR31 C51-APRM3-AR41 C51-APRM4-AR11
12.0% RTP
- 2. Source Range Monitors
- a. Detector Not Full In
C51-SRM-A, B, C, D
NA
- b. Upscale
C51-SRM-A, B, C, D
1 X 10 5 cps c. Inoperative
C51-SRM-A, B, C, D
NA
- d. Downscale
C51-SRM-A, B, C, D
3 cps
- a. Detector Not Full In
C51-IRM-A, B, C, D C51-IRM-E, F, G, H
NA
- b. Upscale
C51-IRM-A, B, C, D C51-IRM-E, F, G, H
108/125 of full scale
- c. Inoperative
C51-IRM-A, B, C, D C51-IRM-E, F, G, H
NA
- d. Downscale
C51-IRM-A, B, C, D C51-IRM-E, F, G, H
3/125 of full scale
- 4. Scram Discharge Volume Water Level-High
C12-LSH-N013E
73 gallons (a) [(0.55(W - W) + 53.5 RTP] when Specification 3.3.1.1, Function 2.b, is reset for single loop operation per LCO 3.4.1, "Recirculation Loops Operating." The setpoint value of W is defined in plant procedures.
TRM TRM Instrument List
Appendix C
Brunswick Unit 2 C-3 Revision No. 61 TRM Table 3.4-2 (page 1 of 1)
Accident Monitoring Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
- 1. Suppression Chamber Atmosphere Temperature(b)
CAC-TE-1258-17 or 18 CAC-TY-4426-1 CAC-TR-4426-1A-5 or 1A-6 CAC-TE-1258-19 or 20 CAC-TY-4426-2 CAC-TR-4426-2A-5 or 2A-6
- 2. Drywell Radiation (c)
CAC-AR-1260
CAC-AQH-1260-1, 2, 3
CAC-AR-1262
CAC-AQH-1262-1, 2, 3
- 3. Safety/Relief Valve Position Indication
- a. Primary-Sonic
- b. Secondary-Temperature
B21-FY-4157 Thru 4167
B21-TR-R614 Points 1 Thru 11
- 4. Turbine Building Ventilation Monitor(d)
D12-RE-4563, D12-RR-4548-3
D12-RE-4562, D12-RR-4548-2
D12-RE-4561, D12-RR-4548-1 5. Offgas Stack Ventilation Monitor(d) D12-RE-4573, D12-RR-4599-2
D12-RE-4574, D12-RR-4599-1
D12-RE-4982, D12-RR-4599-3 6. Drywell and Suppression Chamber H 2 Analyzer (e) CAC-AT-4409-38, CAC-AR-4409-41/42 (Channel 3), CAC-AI-4409-32 CAC-AT-4410-38, CAC-AR-4410-41/42 (Channel 3), CAC-AI-4410-32 7. Drywell and Suppression Chamber O 2 Analyzer (e) CAC-AT-4409-37, CAC-AR-4409-41/42 (Channel 1), CAC-AI-4409-40 CAC-AT-4410-37, CAC-AR-4410-41/42 (Channel 1), CAC-AI-4410-40
(a) Not used (b) Also reference TS 3.3.3.1 and TRM 3.8 (c) Also reference TS 3.4.5 (d) Also reference ODCM 7.3.2 (e) An OPERABLE instrument shall consist of the AT instrument and either the AI instrument or the AR instrument.
TRM TRM Instrument List Appendix C
Brunswick Unit 2 C-4 Revision No. 28 TRM Table 3.5-2 (page 1 of 1) Chloride Intrusion Monitors TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
TRIP SETPOINT
CO-CR-24 CO-CIT-24A, CO-CIT-24B CO-CE-24-1, CO-CE-24-2, CO-CE-24-3, CO-CE-24-4
1.0 mhos/cm 2. Chloride Leak Detector in the Condensate Pump Discharge
- a. Wide Range Monitor
- b. Narrow Range Monitor
CO-CIS-3075-1
TS-CIT-863-3
2.0 mhos/cm 0.3 mhos/cm 3. Chloride Leak Detector in the Inlet to the Condensate Filter Demineralizer
CFD-CIT-1
0.3 mhos/cm 4. Chloride Leak Detector in the Inlet to the Deep Bed Demineralizer
CDD-CIT-1
0.3 mhos/cm TRM TRM Instrument List Appendix C
Brunswick Unit 2 C-5 Revision No. 23 TRM Table 3.6-2 (page 1 of 1) Bus Power Monitors TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
- 1. Core Spray System Bus Power Monitor
E21-K1A, E21-K1B
- 2. Low Pressure Coolant Injection (Residual Heat Removal System) Bus Power Monitor
E11-K106A, E11-K106B
- 3. High Pressure Coolant Injection System Bus Power Monitor
E41-K55, E41-K56
- 4. Automatic Depressurization System Bus Power Monitor
B21-K1A, B21-K1B
- 5. RCIC System Bus Power Monitor
E51-K42, E51-K43
TRM TRM Instrument List Appendix C
Brunswick Unit 2 C-6 Revision No. 23 TRM Table 3.7-1 (page 1 of 1) Automatic Depressurization System (ADS) Inhibit Switch TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
- 1. ADS Inhibit Switch A
B21-CS-S5A
- 2. ADS Inhibit Switch B
B21-CS-S5B
TRM TRM Instrument List Appendix C
Brunswick Unit 2 C-7 Revision No. 23 TRM Table 3.8-1 (page 1 of 1) Suppression Chamber Water Temperature Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
TRIP SETPOINT
- 1. Suppression Chamber Water Temperature
CAC-TE-4426-2 Thru 13, CAC-TY-4426-1, CAC-TR-4426-1A CAC-TE-4426-15 Thru 26, CAC-TY-4426-2, CAC-TR-4426-2A
95°F
TRM TRM Instrument List Appendix C
Brunswick Unit 2 C-8 Revision No. 47 TRM Table 3.9-2 (page 1 of 1) Seismic Monitoring Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
- 1. Passive Triaxial Peak Shock Recorders
- a. Reactor Building Basement/Equipment Drain Tank (-17' level)
2-ENV-XRH-823-1 b. Reactor Building RHR Heat Exchanger Support (+20' level)
- c. Reactor Building Refueling Area (+117' level)
2-ENV-XRH-823-2
2-ENV-XRH-823-3 2. Active Triaxial Accelerometers
- a. Reactor Building (+89' 4" level)
- b. Reactor Building (-17' level)
2-ENV-XT-823-2
2-ENV-XT-823-1
- 3. Active Seismic Recording System
- a. Control Room
2-ENV-XT-823
TRM TRM Instrument List Appendix C
Brunswick Unit 2 C-9 Revision No. 52 TRM Table 3.10-1 (page 1 of 1) Intake Canal High Water Level Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
- 1. Intake Canal High Water Level(a) 2-SCW-LT-285 2-SCW-LI-285 2-SCW-LR-285 2-SCW-LRA-285-1
(a) Also reference TS 3.7.2 and TRM 3.20
TRM TRM Instrument List Appendix C
Brunswick Unit 2 C-10 Revision No. 51 TRM Table 3.11-2 (page 1 of 1) Primary Containment Isolation Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
TRIP SETPOINT
- 1. Main Steam Line Tunnel Temperature-High
B21-TE-N011A, B, C, D B21-TE-N012A, B, C, D B21-TE-N013A, B, C, D
190°F 2. Turbine Building Area Temperature-High
B21-TE-3225A, B, C, D B21-TE-3226A, B, C, D B21-TE-3227A, B, C, D B21-TE-3228A, B, C, D B21-TE-3229A, B, C, D B21-TE-3230A, B, C, D B21-TE-3231A, B, C, D B21-TE-3232A, B, C, D
190°F TRM TRM Instrument List Appendix C
Brunswick Unit 2 C-11 Revision No. 57 TRM Table 3.12-2 (page 1 of 1)
Control Room Emergency Ventila tion System Instrumentation TRM FUNCTION APPLICABLE INSTRUMENT NUMBER(S)
TRIP SETPOINT
- 1. Chlorine Isolation
- a. Control Building Air Intake (Local)
1-X-AT-2977
2-X-AT-2977
1-X-AT-2977-1
2-X-AT-2977-1
5 ppm
- b. Chlorine Tank Car Area (Remote)
1-X-AT-2979
2-X-AT-2979
1-X-AT-2979-1
2-X-AT-2979-1
5 ppm
- 2. Control Room Envelope Smoke Protection
- a. Control Building Intake Air Duct Smoke Detectors
2-FP-CB-4-22
2-FP-CB-4-23
NA
Brunswick Unit 2 Revision No. 23 APPENDIX D PRIMARY CONTAINMENT ISOLATION VALVE (PCIV) LIST
Brunswick Unit 2 D-1 Revision No. 23 APPENDIX D PRIMARY CONTAINMENT ISOLATION VALVE (PCIV) LIST
PURPOSE This appendix provides two PCIV tables to aid in complying with the requirements of Technical
Specification (TS) 3.6.1.3, "Primary Containment Isolation Valves (PCIVs)."
TRM Table 3.6.1.3-1, "Primary Containment Isol ation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges," pr ovides a list of all isolation devices that are considered passive isolation devices and, with the exception of check valves and EFCVs, are normally closed while in MODE 1, 2, or 3. TRM Table 3.6.1.3-1 includes a reference to the
applicable TS Conditions and Surveillance Require ments. Manual valves and flanges that are locked, sealed, or otherwise secured in position are not required to be verified closed to meet
SR 3.6.1.3.1 or SR 3.6.1.3.2. Manual valves and flanges that are not locked, sealed, or otherwise secured in position are required to be verified closed to meet SR 3.6.1.3.1 or SR
3.6.1.3.2, as applicable.
TRM Table 3.6.1.3-2, "Power Operated and Automatic PCIVs," provides a list of all PCIVs that
are considered active isolation devices. TRM Table 3.6.1.3-2 includes a reference to the
applicable TS Conditions, Surveillance Requirements, the required Allowable Isolation Times, and primary containment Automatic Isolation Group, where applicable.
Brunswick Unit 2 D-2 Revision No. 26 TRM Table 3.6.1.3-1 (Page 1 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-B21-F008 REACTOR PRESSURE RIP VALVE TO B21-PS-N002 C SR 3.6.1.3.7 2-B21-F010A FEEDWATER LINE 'A' RPV INLET CHECK VALVE A, B NA 2-B21-F010B FEEDWATER LINE 'B' RPV INLET CHECK VALVE A, B NA 2-B21-F014A EFCV TO B21-PDT-N006A & B C SR 3.6.1.3.7 2-B21-F014B EFCV TO B21-PDT-N006A & B C SR 3.6.1.3.7 2-B21-F014C EFCV TO B21-PDT-N006C & D C SR 3.6.1.3.7 2-B21-F014D EFCV TO B21-PDT-N006C & D C SR 3.6.1.3.7 2-B21-F014E EFCV TO B21-PDT-N007A & B C SR 3.6.1.3.7 2-B21-F014F EFCV TO B21-PDT-N007A & B C SR 3.6.1.3.7 2-B21-F014G EFCV TO B21-PDT-N007C & D C SR 3.6.1.3.7 2-B21-F014H EFCV TO B21-PDT-N007C & D C SR 3.6.1.3.7 2-B21-F014J EFCV TO B21-PDT-N008A & B C SR 3.6.1.3.7 2-B21-F014K EFCV TO B21-PDT-N008A & B C SR 3.6.1.3.7 2-B21-F014L EFCV TO B21-PDT-N008C & D C SR 3.6.1.3.7 2-B21-F014M EFCV TO B21-PDT-N008C & D C SR 3.6.1.3.7 2-B21-F014N EFCV TO B21-PDT-N009A & B C SR 3.6.1.3.7 2-B21-F014P EFCV TO B21-PDT-N009A & B C SR 3.6.1.3.7 2-B21-F014R EFCV TO B21-PDT-N009C & D C SR 3.6.1.3.7 2-B21-F014S EFCV TO B21-PDT-N009C & D C SR 3.6.1.3.7 2-B21-F017 B21-F019 INBOARD TEST CONNECTION VALVE A, B NA 2-B21-F025A OUTBOARD B21-F028A INBOARD TEST VALVE A, B NA 2-B21-F025B OUTBOARD B21-F028B INBOARD TEST VALVE A, B NA 2-B21-F025C OUTBOARD B21-F028C INBOARD TEST VALVE A, B NA 2-B21-F025D OUTBOARD B21-F028D INBOARD TEST VALVE A, B NA 2-B21-F030A FEEDWATER LINE A INBOARD TEST VALVE A, B NA 2-B21-F030B FEEDWATER LINE B INBOARD TEST VALVE A, B NA 2-B21-F040
REACTOR LEVEL RIP VALVE TO B21-LT-3331 AND N027 C SR 3.6.1.3.7 (continued)
Brunswick Unit 2 D-3 Revision No. 23 TRM Table 3.6.1.3-1 (Page 2 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-B21-F042A REACTOR LEVEL RIP VALVE TO B21-LT-N024A-1 & 2 C SR 3.6.1.3.7 2-B21-F042B REACTOR LEVEL INSTRUMENT EFCV (X-69A) C SR 3.6.1.3.7 2-B21-F044A REACTOR LEVEL RIP VALVE TO B21-LT-N025A-1 & 2 C SR 3.6.1.3.7 2-B21-F044B REACTOR LEVEL INSTRUMENT EFCV (X-69B) C SR 3.6.1.3.7 2-B21-F046A REACTOR LEVEL RIP VALVE TO B21-LT-N017-1 & 2 C SR 3.6.1.3.7 2-B21-F046B REACTOR LEVEL INSTRUMENT EFCV (X-69C) C SR 3.6.1.3.7 2-B21-F047C PENETRATION X53-B EFCV C SR 3.6.1.3.7 2-B21-F047D REACTOR INSTRUMENT EFCV (X-83A) C SR 3.6.1.3.7 2-B21-F048A REACTOR LEVEL RIP VALVE TO B21-LT-N036, N017-1 C SR 3.6.1.3.7 2-B21-F048B REACTOR LEVEL INSTRUMENT EFCV (X-69D) C SR 3.6.1.3.7 2-B21-F049C PENETRATION X53-A EFCV C SR 3.6.1.3.7 2-B21-F049D REACTOR LEVEL EFCV B21-LT-N017A-1&2 C SR 3.6.1.3.7 2-B21-F050A JP-5 FLOW HI PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F050B JP-15 FLOW HI PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F050C JP-10 FLOW HI PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F050D JP-20 FLOW HI PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F052A JP-5 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F052B JP-15 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F052C JP-10 FLOW HI PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F052D JP 20 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F054 X-61B EFCV TO B21-PDT-N032 C SR 3.6.1.3.7 2-B21-F056 X-61A EFCV HIGH C SR 3.6.1.3.7 2-B21-F058A JP-1 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058B JP-11 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058C JP-2 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058D JP-12 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058E JP-3 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058F JP-13 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058G JP-4 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058H JP-14 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058L JP-6 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058M
JP-16 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 (continued)
Brunswick Unit 2 D-4 Revision No. 30 TRM Table 3.6.1.3-1 (Page 3 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-B21-F058N JP-7 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058P JP-17 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058R JP-8 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058S JP-18 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058T JP-9 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F058U JP-19 FLOW LO PRESSURE EFCV C SR 3.6.1.3.7 2-B21-F060 JP-11-20 FLOW HI PRESSURE EFCV TO CORE PLATE C SR 3.6.1.3.7 2-B21-IV-2149 EFCV (X-69E) CAPPED C SR 3.6.1.3.7 2-B21-IV-2196 E21-PDS-N004B REACTOR INSTRUMENT PENETRATION VALVE C SR 3.6.1.3.7 2-B21-IV-2455 EFCV TO B21-LT-N026A C SR 3.6.1.3.7 2-B21-IV-2456 EFCV TO B21-LT-N026B C SR 3.6.1.3.7 2-B21-V10 B21-F032A VALVE INBOARD BODY DRAIN VALVE A, B NA 2-B21-V13 B21-F032B VALVE INBOARD BODY DRAIN VALVE A, B NA 2-B21-V83 RPV FLANGE SEAL LEAK DETECTION TEST LINE C NA 2-B21-V160 B21-LT-N026B INSTRUMENT LINE INBOARD TEST VALVE C NA 2-B21-V161 B21-LT-N026A INSTRUMENT LINE INBOARD TEST VALVE C NA 2-B32-F005A RECIRC. PUMP 2A UPPER SEAL PRESSURE RIP VALVE C SR 3.6.1.3.7 2-B32-F005B RECIRC. PUMP 2B UPPER SEAL PRESSURE RIP VALVE C SR 3.6.1.3.7 2-B32-F006A RECIRC. PUMP 2A LOWER SEAL PRESSURE RIP VALVE C SR 3.6.1.3.7 2-B32-F006B RECIRC. PUMP 2B LOWER SEAL PRESSURE RIP VALVE C SR 3.6.1.3.7 2-B32-F021 SAMPLE LINE DRAIN ROOT VALVE A, B NA 2-B32-F039A LO PRESSURE RIP VALVE TO B32-PDT-N015A C SR 3.6.1.3.7 2-B32-F039B HI PRESSURE RIP VALVE TO B32-PDT-N015B C SR 3.6.1.3.7 2-B32-F039C HI PRESSURE RIP VALVE TO B32-PDT-N015A C SR 3.6.1.3.7 2-B32-F039D LO PRESSURE RIP VALVE TO B32-PDT-N015B C SR 3.6.1.3.7 2-B32-F041A LO PRESSURE RIP VALVE TO B32-FT-N014A & B C SR 3.6.1.3.7 2-B32-F041B LO PRESSURE RIP VALVE TO B32-FT-N024A & B C SR 3.6.1.3.7 2-B32-F041C LO PRESSURE RIP VALVE TO B32-FT-N014C & D C SR 3.6.1.3.7 2-B32-F041D
LO PRESSURE RIP VALVE TO B32-FT-N024C & D C SR 3.6.1.3.7 (continued)
Brunswick Unit 2 D-5 Revision No. 26 TRM Table 3.6.1.3-1 (Page 4 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-B32-F042A HI PRESSURE RIP VALVE TO B32-FT-N014A & B C SR 3.6.1.3.7 2-B32-F042B HI PRESSURE RIP VALVE TO B32-FT-N024A & B C SR 3.6.1.3.7 2-B32-F042C HI PRESSURE RIP VALVE TO B32-FT-N014C & D C SR 3.6.1.3.7 2-B32-F042D HI PRESSURE RIP VALVE TO B32-FT-N024C & D C SR 3.6.1.3.7 2-B32-F058A RIP VALVE B32-PS-N018A & B32-PS-N018A-1 C SR 3.6.1.3.7 2-B32-F058B RIP VALVE TO B32-PS-N018B C SR 3.6.1.3.7 2-B32-V24 RECIRC PUMP 2A SEAL INJECTION CHECK VALVE A, B NA 2-B32-V32 RECIRC PUMP 2B SEAL INJECTION CHECK VALVE A, B NA 2-B32-V97 EFCV B32-F006B INLET TEST VALVE C NA 2-B32-V98 EFCV B32-F005B INLET TEST VALVE C NA 2-B32-V99 EFCV B32-F006A INLET TEST VALVE C NA 2-B32-V100 EFCV B32-F005A INLET TEST VALVE C NA 2-B32-V105 LLRT VALVE FOR B32-V22 A, B NA 2-B32-V109 LLRT VALVE FOR B32-V30 A, B NA 2-CAC-IV-695 CAC-PT-4175 INSTRUMENT DRAIN VALVE C NA 2-CAC-IV-696 CAC-PSH-2684 INSTRUMENT DRAIN VALVE C NA 2-CAC-IV-899 CAC-PT-1257-2A INSTRUMENT DRAIN VALVE C NA 2-CAC-IV-933 CAC-PT-4176 INSTRUMENT DRAIN VALVE C NA 2-CAC-IV-934 CAC-PT-2685 INSTRUMENT DRAIN VALVE C NA 2-CAC-IV-940 CAC-PT-3341 INSTRUMENT DRAIN VALVE C NA 2-CAC-IV-1368 CAC-LT-2601 LOW PRESSURE INSTRUMENT CALIBRATION VALVE C NA 2-CAC-IV-1369 CAC-LT-2601 HIGH PRESSURE INSTRUMENT CALIBRATION VALVE C NA 2-CAC-IV-1473 CAC-LT-4177 HIGH PRESSURE INSTRUMENT CALIBRATION VALVE C NA 2-CAC-IV-1474 CAC-LT-4177 LOW PRESSURE INSTRUMENT CALIBRATION VALVE C NA 2-CAC-IV-1475 CAC-LG-4336 SUPPRESSION POOL LEVEL SIGHT GLASS LINE LOWER ISOLATION VALVE C NA 2-CAC-IV-1476 CAC-LG-4336 SUPPRESSION POOL LEVEL SIGHT GLASS LINE UPPER ISOLATION VALVE C NA 2-CAC-IV-1481 SURGE VOLUME RESERVOIR LEVEL GAUGE CAC-LG-5121 UPPER ISOLATION VALVE C NA 2-CAC-IV-1482 SURGE RESERVOIR LEVEL GAUGE CAC-LG-5120 UPPER ISOLATION VALVE C NA 2-CAC-IV-1492 CAC-LT-3342 LOW PRESSURE INSTRUMENT CALIBRATION VALVE C NA (continued)
Brunswick Unit 2 D-6 Revision No. 26 TRM Table 3.6.1.3-1 (Page 5 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-CAC-IV-1493 CAC-LT-3342 HIGH PRESSURE INSTRUMENT CALIBRATION VALVE C NA 2-CAC-IV-1494 CAC-LT-2602 LOW PRESSURE INSTRUMENT CALIBRATION VALVE C NA 2-CAC-IV-1495 CAC-LT-2602 HIGH PRESSURE INSTRUMENT CALIBRATION VALVE C NA 2-CAC-IV-2117 SURGE VOLUME RESERVOIR LEVEL GAUGE CAC-LG-5120 LOWER ISOLATION VALVE C NA 2-CAC-IV-2118 SURGE VOLUME RESERVOIR LEVEL GAUGE CAC-LG-5121 LOWER ISOLATION VALVE C NA 2-CAC-IV-2151 CAC-PT-5113 INSTRUMENT DRAIN VALVE C NA 2-CAC-LT-1216-6 CAC-LT-1216 HIGH PRESSURE INSTRUMENT DRAIN VALVE C NA 2-CAC-LT-1216-7 CAC-LT-1216 LOW PRESSURE INSTRUMENT DRAIN VALVE C NA 2-CAC-PDS-4222-6 CAC-PDS-4222 INSTRUMENT DRAIN VALVE C NA 2-CAC-PDS-4223-6 CAC-PDS-4223 INSTRUMENT DRAIN VALVE C NA 2-CAC-PT-1230-10 CAC-PT-1230 INSTRUMENT TEST VALVE C NA 2-CAC-PT-1257-2B-6 CAC-PT-1257-2B INSTRUMENT DRAIN VALVE C NA 2-CAC-V28 LINE 4-18-152 DRAIN VALVE A, B NA 2-CAC-V34 SUPPRESSION POOL PURGE EXHAUST LINE INBOARD DRAIN VALVE A, B NA 2-CAC-V41 CAC-X20A BEFORE SEAT DRAIN VALVE A, B NA 2-CAC-V44 CAC-X20B BEFORE SEAT DRAIN VALVE A, B NA 2-CAC-V53 CAC-V49 BEFORE SEAT DRAIN VALVE A, B NA 2-CAC-V54 CAC-V49 BEFORE SEAT DRAIN VALVE A, B NA 2-CAC-V79 DRYWELL PURGE EXHAUST LINE INBOARD DRAIN VALVE A, B NA 2-CAC-V81 DRYWELL HEAD PURGE LINE INBOARD DRAIN VALVE A, B NA 2-CAC-V164 CAD N2 INJECTION LINE VENT VALVE A, B NA 2-CAC-V166 SUPP POOL PURGE EXHAUST LINE VENT VALVE A, B NA 2-CAC-V169 CAD N2 INJECTION LINE VENT VALVE A, B NA 2-CAC-V179 TEST CONNECTION VALVE ON LINE CAC-734 C NA 2-CAC-V180 TEST CONNECTION VALVE ON LINE CAC-733 C NA 2-CAC-V183 SURGE VOLUME RESERVOIR LEVEL GAUGE CAC-LG-5777 ISOLATION VALVE C NA 2-CAC-V184 SURGE VOLUME RESERVOIR LEVEL GAUGE CAC-LG-5777 ISOLATION VALVE C NA 2-CAC-V185 SURGE VOLUME RESERVOIR LEVEL GAUGE CAC-LG-5776 ISOLATION VALVE C NA (continued)
Brunswick Unit 2 D-7 Revision No. 26 TRM Table 3.6.1.3-1 (Page 6 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-CAC-V186 SURGE VOLUME RESERVOIR LEVEL GAUGE CAC-LG-5776 ISOLATION VALVE C NA 2-C12-F101 (XX-XX) HCU INSERT HEADER VENT VALVE C SR 3.6.1.3.1 2-C12-F102 (XX-XX) HCU WITHDRAW HEADER VENT VALVE C SR 3.6.1.3.1 2-C41-F006 SLC OUTBOARD INJECTION CHECK VALVE A, B NA 2-C41-F007 SLC INBOARD INJECTION CHECK VALVE A, B NA 2-C41-F026 C41-F006 INBOARD TEST VALVE A, B NA 2-C51-TIP-CHV TIP NITROGEN PURGE LINE CHECK VALVE C NA 2-C72-IV-1378 C72-PT-N002C DRAIN VALVE C NA 2-C72-IV-1379 C72-PT-N002D INSTRUMENT DRAIN VALVE C NA 2-C72-IV-1414 C72-PT-N002B INSTRUMENT DRAIN VALVE C NA 2-C72-IV-1415 C72-PT-N002A INSTRUMENT DRAIN VALVE C NA 2-C72-PS-N004-6 C72-PS-N004 INSTRUMENT DRAIN VALVE C NA 2-C72-V5000 C72-701 FIRST SPARE INSTRUMENT ISOLATION VALVE C NA 2-C72-V5001 C72-701 SECOND SPARE INSTRUMENT ISOLATION VALVE C NA 2-C72-V5002 C72-702 FIRST SPARE INSTRUMENT ISOLATION VALVE C NA 2-C72-V5003 C72-702 SECOND SPARE INSTRUMENT ISOLATION VALVE C NA 2-E11-F025A RHR HEAT EXCHANGER 2A OUTLET PRESSURE RELIEF VALVE C NA 2-E11-F025B RHR HEAT EXCHANGER 2B OUTLET PRESSURE RELIEF VALVE C NA 2-E11-F029 SHUTDOWN COOLING SUCTION HEADER RELIEF C NA 2-E11-F036A CONTAINMENT SPRAY INBOARD AIR TEST ISOLATION VALVE A, B NA 2-E11-F055A RHR HEAT EXCHANGER 2A RE LIEF VALVE BLANK FLANGE C NA 2-E11-F055B RHR HEAT EXCHANGER 2B RE LIEF VALVE BLANK FLANGE C NA 2-E11-F058A LPCI LINE INBOARD TEST ISOLATION VALVE A, B NA 2-E11-F058B
LPCI LINE INBOARD TEST VALVE A, B NA (continued)
Brunswick Unit 2 D-8 Revision No. 23 TRM Table 3.6.1.3-1 (Page 7 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-E11-F063 E11-F008 UPSTREAM INBOARD DRAIN VALVE A, B NA 2-E11-F097 RCIC SUCTION FROM RHR SYSTEM RELIEF VALVE BLANK FLANGE C NA 2-E11-IV-1380 E11-PT-N019B INSTRUMENT DRAIN VALVE C NA 2-E11-IV-1381 E11-PT-N019D INSTRUMENT DRAIN VALVE C NA 2-E11-IV-1408 E11-PT-N019C INSTRUMENT DRAIN VALVE C NA 2-E11-IV-1409 E11-PT-N019A INSTRUMENT DRAIN VALVE C NA 2-E11-PT-N011A-6 E11-PT-N011A INSTRUMENT DRAIN VALVE C NA 2-E11-PT-N011B-6 E11-PT-N011B INSTRUMENT DRAIN VALVE C NA 2-E11-PT-N011C-6 E11-PT-N011C INSTRUMENT DRAIN VALVE C NA 2-E11-PT-N011D-6 E11-PT-N011D INSTRUMENT DRAIN VALVE C NA 2-E11-V20 RHR HEAT EXCHANGER 2A SHELL RELIEF VALVE C NA 2-E11-V21 RHR HEAT EXCHANGER 2B SHELL RELIEF VALVE C NA 2-E11-V74 VALVE E11-F020A INBOARD BODY DRAIN VALVE C NA 2-E11-V81 LPCI LINE HIGH POINT VENT VALVE A, B NA 2-E11-V82 VALVE E11-F015A INBOARD BODY DRAIN VALVE A, B NA 2-E11-V83 LPCI LINE HIGH POINT VENT VALVE A, B NA 2-E11-V84 VALVE E11-F021B INBOARD BODY DRAIN VALVE A, B NA 2-E11-V86 VALVE E11-F021B OUTBOARD BODY DRAIN VALVE A, B NA 2-E11-V87 VALVE E11-F024A BODY DRAIN VALVE A, B NA 2-E11-V91 VALVE E11-F028A BODY DRAIN VALVE A, B NA 2-E11-V92 VALVE E11-F015A OUTBOARD BODY DRAIN VALVE A, B NA 2-E11-V103 VALVE E11-F008 INBOARD BODY DRAIN VALVE A, B NA 2-E11-V121 VALVE E11-F021A OUTBOARD BODY DRAIN VALVE A, B NA (continued)
Brunswick Unit 2 D-9 Revision No. 42 TRM Table 3.6.1.3-1 (Page 8 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-E11-V122 VALVE E11-F021A INBOARD BODY DRAIN VALVE A, B NA 2-E11-V125 VALVE E11-F016B BODY DRAIN VALVE A, B NA 2-E11-V126 VALVE E11-F028B BODY DRAIN VALVE A, B NA 2-E11-V127 VALVE E11-F024B BODY DRAIN VALVE A, B NA 2-E11-V135 VALVE E11-F020B INBOARD BODY DRAIN VALVE C NA 2-E11-V169 VALVE E11-F015B INBOARD BODY DRAIN VALVE A, B NA 2-E11-V170 VALVE E11-F015B OUTBOARD BODY DRAIN VALVE A, B NA 2-E11-V189 CONTAINMENT SPRAY LINE INBOARD AIR TEST ISOLATION VALVE A, B NA 2-E11-V5003 E11-703 FIRST SPARE INSTRUMENT ISOLATION VALVE C NA 2-E11-V5004 E11-703 SECOND SPARE INSTRUMENT ISOLATION VALVE C NA 2-E11-V5005 E11-706 SPARE RACK ISOLATION VALVE C NA 2-E11-V5013 2-E11-F009 DOWNSTREAM SIDE BODY INBOARD VENT VALVE A, B NA 2-E21-F013A CS INJECTION LINE INBOARD TEST VALVE A, B NA 2-E21-F013B CS INJECTION LINE INBOARD TEST VALVE A, B NA 2-E21-F017A E21-PDS-N004A EFCV C SR 3.6.1.3.7 2-E21-F017B E21-PDS-N004B EFCV C SR 3.6.1.3.7 2-E21-V21 DIV I FULL FLOW BYPASS LINE DRAIN VALVE C NA 2-E21-V33 DIV II FULL FLOW BYPASS LINE DRAIN VALVE C NA 2-E21-V47 CS A MINIMUM FLOW BYPASS LINE TO SUPPRESSION POOL VENT VALVE C NA 2-E21-V49 CS B MINIMUM FLOW BYPASS LINE TO SUPPRESSION POOL VENT VALVE C NA 2-E21-V55 INBOARD BODY DRAIN VALVE (E21-F005A)
A, B NA 2-E21-V56 OUTBOARD BODY DRAIN VALVE (E21-F005A)
A, B NA 2-E21-V57 INBOARD BODY DRAIN VALVE (E21-F005B)
A, B NA 2-E21-V58
OUTBOARD BODY DRAIN VALVE (E21-F005B)
A, B NA (continued)
Brunswick Unit 2 D-10 Revision No. 26 TRM Table 3.6.1.3-1 (Page 9 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-E21-V77 INBOARD BODY DRAIN VALVE (E21-F001A) C NA 2-E21-V79 INBOARD BODY DRAIN VALVE (E21-F001B) C NA 2-E41-F013 HPCI TURBINE EXHAUST LINE INBOARD TEST VALVE A, B NA 2-E41-F014 HPCI STEAM SUPPLY LINE INBOARD TEST VALVE A, B NA 2-E41-F021 HPCI TURBINE EXHAUST LINE ISOLATION VALVE A, B NA 2-E41-F022 HPCI TURBINE EXHAUST DRAIN POT DRAIN VALVE TO TORUS A, B NA 2-E41-F023A E41-PDS-N004 & PS-N001A STEAM LINE PRESSURE C SR 3.6.1.3.7 2-E41-F023B HPCI STEAM LINE PRESSURE RIP VALVE C SR 3.6.1.3.7 2-E41-F023C HPCI STEAM LINE PRESSURE RIP VALVE C SR 3.6.1.3.7 2-E41-F023D HPCI STEAM LINE PRESSURE RIP VALVE C SR 3.6.1.3.7 2-E41-F040 HPCI EXHAUST DRAIN POT DRAIN TO TORUS CHECK VALVE A, B NA 2-E41-F047 EXHAUST DRAIN POT DRAIN LINE INBOARD TEST VALVE A, B NA 2-E41-F049 HPCI TURBINE EXHAUST LINE CHECK VALVE A, B NA 2-E41-F078 HPCI VACUUM BREAKER LINE DRAIN VALVE A, B NA 2-E41-F090 HPCI VACUUM BREAKER LINE DRAIN VALVE A, B NA 2-E41-F091 HPCI VACUUM BREAKER LINE DRAIN VALVE A, B NA 2-E41-IV-980 E41-LSH-N015A INSTRUMENT DRAIN VALVE C NA 2-E41-IV-981 E41-LSH-N015B INSTRUMENT DRAIN VALVE C NA 2-E41-V55 HPCI INJECTION LINE INBOARD TEST VALVE A, B NA 2-E41-V68 E41-F021 INBOARD BODY DRAIN VALVE C NA 2-E41-V70 E41-F042 INBOARD BODY DRAIN VALVE C NA 2-E41-V124 TEST CONNECTION VALVE ON LINE E41-716 C NA 2-E41-V126 TEST CONNECTION VALVE ON LINE E41-714 C NA 2-E41-V163 HPCI INJECTION LINE INBOARD DRAIN/TEST A, B NA 2-E41-V177
HPCI STEAM SUPPLY LINE OUTBOARD TEST VALVE (F003) A, B NA (continued)
Brunswick Unit 2 D-11 Revision No. 26 TRM Table 3.6.1.3-1 (Page 10 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-E41-V186 HPCI PUMP MINIMUM FLOW BYPASS LINE TEST VALVE C NA 2-E41-V188 E41-LSH-N015A TEST VENT VALVE C NA 2-E41-V189 E41-LSH-N015B TEST VENT VALVE C NA 2-E51-F001 RCIC TURBINE STEAM EXHAUST TO TORUS A, B NA 2-E51-F036 RCIC STEAM SUPPLY LINE INBOARD TEST VALVE A, B NA 2-E51-F040 RCIC TURBINE STEAM TO SUPPRESSION POOL A, B NA 2-E51-F041 RCIC TURBINE EXHAUST INBOARD TEST VALVE A, B NA 2-E51-F043A X-61F EFCV TO E51-PDT-N017 C SR 3.6.1.3.7 2-E51-F043B X-72F EFCV TO E51-PDT-N018 C SR 3.6.1.3.7 2-E51-F043C X-61E EFCV TO E51-PDT-N017 C SR 3.6.1.3.7 2-E51-F043D X-72E EFCV TO E51-PDT-N018 C SR 3.6.1.3.7 2-E51-F060 RCIC TURBINE EXHAUST VACUUM RELIEF TEST VALVE A, B NA 2-E51-F061 RCIC TURBINE EXHAUST VACUUM RELIEF TEST VALVE A, B NA 2-E51-F065 RCIC TURBINE EXHAUST VACUUM RELIEF TEST VALVE A, B NA 2-E51-V104 RCIC STEAM SUPPLY LINE OUTBOARD TEST VALVE (F008)
A, B NA 2-G16-V1110 DRYWELL FLOOR DRAIN LINE INBOARD DRAIN VALVE A, B NA 2-G16-V1112 DRYWELL EQUIPMENT DRAIN LINE INBOARD DRAIN VALVE A, B NA 2-G31-F037
RWCU RETURN TO REACTOR LINE TEST VALVE A, B NA (continued)
Brunswick Unit 2 D-12 Revision No. 26 TRM Table 3.6.1.3-1 (Page 11 of 11) Primary Containment Isolation Devices - Manual Valves, Check Valves, Excess Flow Check Valves (EFCVs), and Flanges VALVE OR FLANGE NUMBER DESCRIPTION APPLICABLE TS CONDITION(S) SURVEILLANCE REQUIREMENTS 2-RCC-IV-2374 RECIRC PUMP 2A COOLER OUTLET SAMPLE TEST C NA 2-RCC-IV-2375 RECIRC PUMP 2B COOLER OUTLET SAMPLE TEST C NA 2-RNA-V350 DIV II NON-INTERRUPTIBLE INSTRUMENT AIR SUPPLY INBOARD CHECK VALVE A, B NA 2-RNA-V351 DIV I NON-INTERRUPTIBLE INSTRUMENT AIR SUPPLY INBOARD CHECK VALVE A, B NA 2-RNA-V5000 2-RNA-SV-5261 LLRT CONNECTION A, B NA 2-RNA-V5001 2-RNA-SV-5262 LLRT CONNECTION A, B NA 2-TD-V2 TORUS DRAIN C NA TRM PCIV List Appendix D
Brunswick Unit 2 D-13 Revision No. 23 TRM Table 3.6.1.3-2 (Page 1 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S)
SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds)
AUTOMATIC ISOLATION GROUP 2-B21-F016 MAIN STEAM LINE DRAIN INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 1 2-B21-F019 MAIN STEAM LINE DRAIN OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 1 2-B21-F022A INBOARD MSIV A A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F022B INBOARD MSIV B A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F022C INBOARD MSIV C A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F022D INBOARD MSIV D A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F028A OUTBOARD MSIV A A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F028B OUTBOARD MSIV B A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F028C OUTBOARD MSIV C A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F028D OUTBOARD MSIV D A, B, D SR 3.6.1.3.5 SR 3.6.1.3.6 SR 3.6.1.3.9 3 and 5 1 2-B21-F032A FEEDWATER SUPPLY LINE A ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-B21-F032B FEEDWATER SUPPLY LINE B ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-B32-F019 SAMPLE LINE INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 5 1 2-B32-F020 SAMPLE LINE OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 5 1 2-B32-V22 RECIRC PUMP 2A SEAL INJECTION A, B SR 3.6.1.3.4 (a) NA 2-B32-V30 RECIRC PUMP 2B SEAL INJECTION A, B SR 3.6.1.3.4 (a) NA 2-CAC-SV-1200B CAC-AT-1261 INBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (continued)
(a) Allowable Isolation Time specified in the Inservice Testing Program.
Brunswick Unit 2 D-14 Revision No. 49 TRM Table 3.6.1.3-2 (Page 2 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S)
SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds)
AUTOMATIC ISOLATION GROUP 2-CAC-SV-1205E CAC-AT-4409 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1209A CAC-AT-4409 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1209B CAC-AT-4409 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1211E CAC-AT-1262 INBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1211F CAC-AT-1262 INBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1213A CAC-AT-4409 TORUS INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1215E CAC-AT-4409 INBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1218A CAC-AT-4410 TORUS INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1225B COMMON INBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1227A CAC-AT-4410 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1227B CAC-AT-4410 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1227C CAC-AT-1260 INBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1227E CAC-AT-4410 PRIMARY CONTAINMENT INBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6
15 6 (b) (continued)
(a) Allowable Isolation Time specified in the Inservice Testing Program.
(b) The PCIV receives a Group 6 isolation signal for instrument protection. The PCIV is considered OPERABLE if it is capable of closing from the control room within the specified Allowable Isolation Time.
Brunswick Unit 2 D-15 Revision No. 49 TRM Table 3.6.1.3-2 (Page 3 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S)
SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds)
AUTOMATIC ISOLATION GROUP 2-CAC-SV-1231B CAC-AT-4410 INBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-1260 CAC-AT-1260 OUTBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1261 CAC-AT-1261 OUTBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-1262 CAC-AT-1262 OUTBOARD SAMPLE INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-3439 CAC-AT-1262 OUTBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-3440 COMMON OUTBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-SV-4409-1 CAC-AT-4409 TORUS OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4409-2 CAC-AT-4409 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4409-3 CAC-AT-4409 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4409-4 CAC-AT-4409 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4410-1 CAC-AT-4410 TORUS OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4410-2 CAC-AT-4410 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4410-3 CAC-AT-4410 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4410-4 CAC-AT-4410 PRIMARY CONTAINMENT OUTBOARD SAMPLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4540 CAC-AT-4409 OUTBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) 2-CAC-SV-4541 CAC-AT-4410 OUTBOARD SAMPLE RETURN A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (b) (continued)
(a) Allowable Isolation Time specified in the Inservice Testing Program.
(b) The PCIV receives a Group 6 isolation signal for instrument protection. The PCIV is considered OPERABLE if it is capable of closing from the control room within the specified Allowable Isolation Time.
Brunswick Unit 2 D-16 Revision No. 23 TRM Table 3.6.1.3-2 (Page 4 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S)
SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds)
AUTOMATIC ISOLATION GROUP 2-CAC-V4 INBOARD PRIMARY CONTAINMENT N2 INERTING INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V5 SUPPRESSION POOL N2 INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V6 DRYWELL N2 INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V7 INBOARD SUPPRESSION POOL PURGE EXHAUST A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V8 OUTBOARD SUPPRESSION POOL PURGE EXHAUST A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V9 INBOARD DRYWELL PURGE EXHAUST A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V10 OUTBOARD DRYWELL PURGE EXHAUST A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V15 PRIMARY CONTAINMENT PURGE AIR INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V22 SUPPRESSION POOL 2" EXHAUST A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V23 DRYWELL 2" EXHAUST A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V49 DRYWELL HEAD INBOARD PURGE EXHAUST A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V50 DRYWELL HEAD OUTBOARD PURGE EXHAUST A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V55 DRYWELL CAD N2 INJECTION SOLENOID A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V56 DRYWELL CAD N2 INJECTION SOLENOID A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V160 SUPPRESSION POOL CAD N2 INJECTION INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V161 DRYWELL CAD N2 INJECTION INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V162 SUPPRESSION POOL CAD N2 INJECTION INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V163 DRYWELL CAD N2 INJECTION INLET A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V172 SUPPRESSION POOL PURGE EXHAUST SOLENOID A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-CAC-V216 HARDENED WETWELL VENT OUTBOARD ISOLATION
A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (continued)
Brunswick Unit 2 D-17 Revision No. 59 TRM Table 3.6.1.3-2 (Page 5 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S)
SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds)
AUTOMATIC ISOLATION GROUP 2-C51-J004A A TIP BALL VALVE AND SHEAR VALVE ASSEMBLY A, B SR 3.6.1.3.3 SR 3.6.1.3.4 SR 3.6.1.3.6 SR 3.6.1.3.8 (a) 2 2-C51-J004B B TIP BALL VALVE AND SHEAR VALVE ASSEMBLY A, B SR 3.6.1.3.3 SR 3.6.1.3.4 SR 3.6.1.3.6 SR 3.6.1.3.8 (a) 2 2-C51-J004C C TIP BALL VALVE AND SHEAR VALVE ASSEMBLY A, B SR 3.6.1.3.3 SR 3.6.1.3.4 SR 3.6.1.3.6 SR 3.6.1.3.8 (a) 2 2-C51-J004D D TIP BALL VALVE AND SHEAR VALVE ASSEMBLY A, B SR 3.6.1.3.3 SR 3.6.1.3.4 SR 3.6.1.3.6 SR 3.6.1.3.8 (a) 2 2-E11-F007A MINIMUM FLOW BYPASS VALVE A TO SUPPRESSION POOL C SR 3.6.1.3.4 (a) NA 2-E11-F007B MINIMUM FLOW BYPASS VALVE B TO SUPPRESSION POOL C SR 3.6.1.3.4 (a) NA 2-E11-F008 SHUTDOWN COOLING OUTBOARD SUCTION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 43 8(c) 2-E11-F009 SHUTDOWN COOLING INBOARD SUCTION THROTTLE A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 8(c) 2-E11-F011A RHR HEAT EXCHANGER 2A DRAIN TO SUPPRESSION POOL C SR 3.6.1.3.4 (a) NA 2-E11-F011B RHR HEAT EXCHANGER 2B DRAIN TO SUPPRESSION POOL C SR 3.6.1.3.4 (a) NA 2-E11-F015A LPCI A INBOARD INJECTION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 8(c) 2-E11-F015B LPCI B INBOARD INJECTION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 8(c) 2-E11-F016A DRYWELL SPRAY A OUTBOARD ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F016B DRYWELL SPRAY B OUTBOARD ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F017A LPCI A OUTBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E11-F017B LPCI B OUTBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E11-F020A RHR PUMP 2A AND 2C TORUS SUCTION C SR 3.6.1.3.4 (a) NA (continued)
(a) Allowable Isolation Time specified in the Inservice Testing Program.
(c) Except as noted in TS Table 3.3.6.1-1 (Note (d)), these PCIVs are also required to be OPERABLE in MODES 4 and 5 to support the OPERABILITY of Function 6.b of TS Table 3.3.6.1-1.
Brunswick Unit 2 D-18 Revision No. 23 TRM Table 3.6.1.3-2 (Page 6 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S)
SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds)
AUTOMATIC ISOLATION GROUP 2-E11-F020B RHR PUMP 2B AND 2D TORUS SUCTION C SR 3.6.1.3.4 (a) NA 2-E11-F021A DRYWELL SPRAY A INBOARD ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F021B DRYWELL SPRAY B INBOARD ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F024A SUPPRESSION POOL COOLING A ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F024B SUPPRESSION POOL COOLING B ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F027A SUPPRESSION POOL SPRAY A ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F027B SUPPRESSION POOL SPRAY B ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F028A SUPPRESSION POOL SPRAY A ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F028B SUPPRESSION POOL SPRAY B ISOLATION A, B SR 3.6.1.3.4 (a) NA 2-E11-F103A RHR HEAT EXCHANGER 2A OUTBOARD VENT C SR 3.6.1.3.4 (a) NA 2-E11-F103B RHR HEAT EXCHANGER 2B OUTBOARD VENT C SR 3.6.1.3.4 (a) NA (continued)
(a) Allowable Isolation Time specified in the Inservice Testing Program.
Brunswick Unit 2 D-19 Revision No. 23 TRM Table 3.6.1.3-2 (Page 7 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S)
SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds)
AUTOMATIC ISOLATION GROUP 2-E21-F001A SUPPRESSION POOL A SUCTION C SR 3.6.1.3.4 (a) NA 2-E21-F001B SUPPRESSION POOL B SUCTION C SR 3.6.1.3.4 (a) NA 2-E21-F004A CORE SPRAY PUMP 2A OUTBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E21-F004B CORE SPRAY PUMP 2B OUTBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E21-F005A CORE SPRAY PUMP 2A INBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E21-F005B CORE SPRAY PUMP 2B INBOARD INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E21-F015A CORE SPRAY FULL FLOW TEST BYPASS C SR 3.6.1.3.4 (a) NA 2-E21-F015B CORE SPRAY FULL FLOW TEST BYPASS C SR 3.6.1.3.4 (a) NA 2-E21-F031A CORE SPRAY MINIMUM FLOW BYPASS C SR 3.6.1.3.4 (a) NA 2-E21-F031B CORE SPRAY MINIMUM FLOW BYPASS C SR 3.6.1.3.4 (a) NA 2-E41-F002 HPCI STEAM SUPPLY INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 50 4 2-E41-F003 HPCI STEAM SUPPLY OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 50 4 2-E41-F006 HPCI INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E41-F012 HPCI MINIMUM FLOW BYPASS TO SUPPRESSION POOL C SR 3.6.1.3.4 20 NA 2-E41-F042 HPCI SUPPRESSION POOL SUCTION C SR 3.6.1.3.4 SR 3.6.1.3.6
80 4 (continued)
(a) Allowable Isolation Time specified in the Inservice Testing Program.
Brunswick Unit 2 D-20 Revision No. 23 TRM Table 3.6.1.3-2 (Page 8 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S)
SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds)
AUTOMATIC ISOLATION GROUP 2-E41-F075 HPCI TURBINE EXHAUST VACUUM BREAKER A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 7 2-E41-F079 HPCI TURBINE EXHAUST VACUUM BREAKER A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 7 2-E51-F007 RCIC STEAM SUPPLY INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 5 2-E51-F008 RCIC STEAM SUPPLY OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 5 2-E51-F013 RCIC INJECTION A, B SR 3.6.1.3.4 (a) NA 2-E51-F019 RCIC MINIMUM FLOW BYPASS TO SUPPRESSION POOL C SR 3.6.1.3.4 (a) NA 2-E51-F031 RCIC SUPPRESSION POOL SUCTION C SR 3.6.1.3.4 SR 3.6.1.3.6 80 5 2-E51-F062 RCIC TURBINE EXHAUST VACUUM BREAKER A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 9 2-E51-F066 RCIC TURBINE EXHAUST VACUUM BREAKER A, B SR 3.6.1.3.4 SR 3.6.1.3.6 30 9 2-G16-F003 DRYWELL FLOOR DRAIN INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 20 2 2-G16-F004 DRYWELL FLOOR DRAIN OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 20 2 2-G16-F019 DRYWELL EQUIPMENT DRAIN INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 20 2 2-G16-F020 DRYWELL EQUIPMENT DRAIN OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 20 2 2-G31-F001 RWCU INLET INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 35 3 (e) 2-G31-F004 RWCU INLET OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 35 3 2-G31-F042 RWCU RETURN TO REACTOR A, B SR 3.6.1.3.4 (a) NA 2-RCC-SV-1222B RECIRC PUMP 2A COOLER OUTLET SAMPLE C SR 3.6.1.3.4 (a) NA (continued)
(a) Allowable Isolation Time specified in the Inservice Testing Program.
(e) Valve does not automatically close on an isolation signal associated with Function 5.f of TS Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation."
Brunswick Unit 2 D-21 Revision No. 24 TRM Table 3.6.1.3-2 (Page 9 of 9) Power Operated and Automatic PCIVs VALVE NUMBER VALVE DESCRIPTION APPLICABLE TS CONDITION(S)
SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds)
AUTOMATIC ISOLATION GROUP 2-RCC-SV-1222C RECIRC PUMP 2B COOLER OUTLET SAMPLE C SR 3.6.1.3.4 (a) NA 2-RCC-V28 RBCCW DRYWELL DISCHARGE HEADER ISOLATION C SR 3.6.1.3.4 (a) NA 2-RCC-V52 RBCCW DRYWELL SUPPLY HEADER ISOLATION C SR 3.6.1.3.4 (a) NA 2-RNA-SV-5251 BACKUP NITROGEN SUPPLY TO DRYWELL ISOLATION VALVE - DIVISION II C SR 3.6.1.3.4 (a) NA 2-RNA-SV-5253 BACKUP NITROGEN SUPPLY TO DRYWELL ISOLATION VALVE - DIVISION I C SR 3.6.1.3.4 (a) NA 2-RNA-SV-5261 NON-INTERRUPTIBLE REACTOR INSTRUMENT AIR SOLENOID A, B SR 3.6.1.3.4 SR 3.6.1.3.6 (a) 10 2-RNA-SV-5262 NON-INTERRUPTIBLE REACTOR INSTRUMENT AIR SOLENOID A, B SR 3.6.1.3.4 SR 3.6.1.3.6 (a) 10 2-RXS-SV-4186 LIQUID SAMPLE RETURN INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-RXS-SV-4187 LIQUID SAMPLE RETURN OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-RXS-SV-4188 GAS SAMPLE RETURN INBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 2-RXS-SV-4189 GAS SAMPLE RETURN OUTBOARD ISOLATION A, B SR 3.6.1.3.4 SR 3.6.1.3.6 15 6 (a) Allowable Isolation Time specified in the Inservice Testing Program.
Brunswick Unit 2 Revision No. 23 APPENDIX E SECONDARY CONTAINMENT ISOLATION DAMPER (SCID) LIST
TRM SCID List Appendix E
Brunswick Unit 2 E-1 Revision No. 23 APPENDIX E SECONDARY CONTAINMENT ISOLATION DAMPER (SCID) LIST
PURPOSE This appendix provides a table to aid in complying with the requirements of Technical
Specification (TS) 3.6.4.2, "Secondary Containment Isolation Dampers (SCIDs)."
TRM Table 3.6.4.2-1, "Secondary Containment Automatic Isolation Dampers," provides a list of
the SCIDs that are required to automatically close on a secondary containment isolation signal.
TRM Table 3.6.4.2-1 includes a reference to the applicable TS Surveillance Requirements and
the required Allowable Isolation Times.
TRM SCID List Appendix E
Brunswick Unit 2 E-2 Revision No. 23 TRM Table 3.6.4.2-1 (Page 1 of 1) Secondary Containment Automatic Isolation Dampers DAMPER NUMBER DAMPER DESCRIPTION SURVEILLANCE REQUIREMENTS ALLOWABLE ISOLATION TIME (in seconds) 2-VA-2A-BFIV-RB Reactor Building Ventilation Supply Inboard Isolation SR 3.6.4.2.1 SR 3.6.4.2.2 4 2-VA-2B-BFIV-RB Reactor Building Ventilation Supply Outboard Isolation SR 3.6.4.2.1 SR 3.6.4.2.2 4 2-VA-2C-BFIV-RB Reactor Building Ventilation Exhaust Inboard Isolation SR 3.6.4.2.1 SR 3.6.4.2.2 4 2-VA-2D-BFIV-RB Reactor Building Ventilation Exhaust Outboard Isolation SR 3.6.4.2.1 SR 3.6.4.2.2 4 2-VA-2A-BFV-RB Purge System Exhaust Outlet Valve SR 3.6.4.2.1 SR 3.6.4.2.2 (a) 2-VA-2I-BFV-RB Purge System Inlet Valve SR 3.6.4.2.1 SR 3.6.4.2.2 (a)
(a) Allowable Isolation Time specified in the Inservice Testing Program.
Brunswick Unit 2 Revision No. 23 APPENDIX F SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)
TRM SFDP Appendix F SFDP Definitions Brunswick Unit 2 SFDP-1 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)
1.0 SFDP DEFINITIONS
Loss of Safety Inability to accomplish a Safety Function as defined Function(LOSF) in this program. See the definition of Safety Function below.
For the performance of a Safety Function Determination (SFD), identifies specific conditions which constitute a
LOSF. This attachment includes any Technical Specification (TS)
Condition which requires entry into LCO 3.0.3 or a unit shutdown. Safety Function A TS function that must be performed to mitigate the consequences of an accident, transient, or special event as
defined in the current BNP licensing basis, including TS functions
that have been deemed important contributors to risk reduction.
Support Feature A TS system/subsystem/component which supports a required TS system(s) in order for the TS syst em to perform its required Safety Function.
Supported Feature A TS system/subsystem/component that performs a specific Safety Function.
TRM SFDP Appendix F Cascading Requirements Brunswick Unit 2 SFDP-2 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)
2.0 CASCADING
REQUIREMENTS
2.1 Technical
Specification (TS) LCO 3.0.2 requires that the TS ACTIONS (Conditions and Required Actions) be entered and performed when an
applicable LCO is not met, except as provided in LCO 3.0.5 and LCO 3.0.6. 2.2 TS LCO 3.0.6 is applicable in instances when a Supported Feature LCO is not met solely due to a Support Feature LCO not being met.
of this program provides a limited cross reference of
Support Feature TS and associated Supported Feature TS. In the event
LCO 3.0.6 is applicable, the following should be considered:
2.2.1 The applicable Conditions for the inoperable Support Feature shall be entered and the associated Required Actions
performed. Document the Required Actions in accordance
with Procedure No. OOI-01.08, "Control of Equipment and
System Status." 2.2.2 --------------------------------------NOTE-------------------------------------
For the purposes of this program, the single failure criterion is
not required when determining OPERABILITY of the
Supported Feature(s).
The inoperable Support Feature may impact multiple Supported Features and the inoperable Support Feature may
be several support levels up from the Supported Feature. As
such, OPERABILITY Determinations may be required to
determine if an inoperable Support Feature does result in one
or more Supported Features becoming inoperable. If an
OPERABILITY Determination is required, an Engineering
Service Request should be generated in accordance with
Procedure No. EGR-NGGC-0005, "Engineering Service
Requests." Attachments 2 and 3 of this program and
Procedure No. OI-18, "Definition of Instrument Channels and
Trip Systems for Selected Instruments," may be used as an
aid in the OPERABILITY Determinations.
(continued)
TRM SFDP Appendix F Cascading Requirements Brunswick Unit 2 SFDP-3 Revision No. 23
2.0 CASCADING
REQUIREMENTS (continued)
2.2.3 If the inoperable Support Feature results in a Supported Feature(s) becoming inoperable, then the Supported
Feature(s) shall be considered inoperable. 2.2.4 The applicable TS Conditions for the inoperable Supported Feature(s) shall be entered and the associated Required
Actions performed (i.e., "cascade" to the Supported Feature
TS ACTIONS) when: 2.2.4.1 The inoperability is not associated with a Support Feature TS but does impact OPERABILITY of a
Supported Feature(s); 2.2.4.2 The TS Required Actions for the inoperable Support Feature direct that the inoperable Supported
Feature(s) be declared inoperable; or 2.2.4.3 Any Note to the TS Required Actions for the inoperable Support Feature that direct the Conditions
and Required Actions for the inoperable Supported
Feature(s) be entered. Document the Required Actions per Procedure No. 0OI-01.08.
2.3 -------------------------------------------NOTE----------------------------------------------
If only one Support Feature is inoperable and no other TS
system/subsystem/component is inoperable, the Safety Function
Determination (SFD) may be delayed until a subsequent inoperability
occurs.
Unless cascading to the Supported Feature TS ACTIONS is required (as described in Section 2.2.4 of this program), it is not required to enter the
TS ACTIONS for the inoperable Supported Feature(s). If the TS
ACTIONS for the inoperable Supported Feature(s) are not entered, then a
SFD shall be performed. 2.4 A SFD includes performing cross division checks in order to determine if redundant features are capable of performing their required Safety
Function. Figure 2-1 of this program provides guidance on the process of
performing a SFD. Refer to the SFDP Bases for SFD evaluation
examples.
(continued)
TRM SFDP Appendix F Cascading Requirements Brunswick Unit 2 SFDP-4 Revision No. 23
2.0 CASCADING
REQUIREMENTS (continued)
2.5 If the SFD indicates that a LOSF exists, then the appropriate Conditions in the TS where the LOSF has occurred shall be entered and the
associated Required Actions performed. Attachment 4 of this program
should be used to determine if a LOSF exists.
TRM SFDP Appendix F Cascading Requirements Brunswick Unit 2 SFDP-5 Revision No. 23
Figure 2-1 (page 1 of 1)
Safety Function Determination Program Flowchart
TRM SFDP Appendix F Maximum Completion Time Brunswick Unit 2 SFDP-6 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)
3.0 MAXIMUM
COMPLETION TIME
3.1 A Supported Feature(s) made inoperable by Support Feature inoperabilities shall be restored to OPERABLE status within the Maximum
Completion Time. The Maximum Completion Time, for the purposes of
this program, is the Completion Time specified in the Technical
Specifications (TS) for restoring the first inoperable Support Feature to OPERABLE status plus the Completion Time specified in the TS for restoring the Supported Feature to OPERABLE status. 3.2 If the Supported Feature is not restored to OPERABLE status (by restoring the Supported Feature and all associated Support Features to
OPERABLE status) within the Maximum Completion Time, the associated
Condition for the inoperable Supported Feature's Completion Time not
being met shall be entered and the Required Actions shall be performed.
TRM SFDP Appendix F SFD Review Brunswick Unit 2 SFDP-7 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)
4.0 SAFETY
FUNCTION DETERMINATION (SFD) REVIEW
4.1 A review of the SFD shall be performed after every subsequent inoperability. If a review of the SFD indicates a LOSF has occurred, then
the appropriate Conditions in the TS where the LOSF has occurred shall
be entered and the associated Required Actions performed.
TRM SFDP Appendix F Attachment 1 Brunswick Unit 2 SFDP-8 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)
Support Feature/Supported Feature TS Cross Reference - Attachment 1
Support System TS
Number Support System Supported System TS
Number Supported System 3.3.5.1 ECCS Instrumentation 3.5.1 3.5.2 3.6.2.3 3.8.1 3.8.2 ECCS - Operating
ECCS - Shutdown
RHR Suppression Pool Cooling
AC Sources - Operating
AC Sources - Shutdown 3.3.5.2 RCIC Instrumentation 3.5.3 RCIC System 3.3.6.1 Primary Containment Isolation Instrumentation 3.1.7 3.6.1.3 3.6.1.5 SLC System
PCIVs Reactor Building-to-Suppression
Chamber Vacuum Breakers 3.3.6.2 Secondary Containment Isolation Instrumentation 3.6.4.2 3.6.4.3 SCIDs SGT System 3.3.7.1 CREV System Instrumentation 3.7.3 CREV System 3.3.8.1 LOP Instrumentation 3.3.5.1 3.7.2 3.8.1 3.8.2 ECCS Instrumentation
AC Sources - Operating
AC Sources - Shutdown 3.6.1.5 Reactor Building-to-Suppression Chamber
Vacuum Breakers 3.6.1.1 Primary Containment 3.6.1.6 Suppression Chamber-to-Drywell Vacuum Breakers 3.6.1.1 Primary Containment (continued)
TRM SFDP Appendix F Attachment 1 Brunswick Unit 2 SFDP-9 Revision No. 23 (continued)
Support System TS
Number Support System Supported System TS
Number Supported System 3.6.4.2 SCIDs 3.6.4.1 Secondary Containment 3.6.4.3 SGT System 3.6.4.1 Secondary Containment 3.7.1 RHRSW System 3.4.7 3.6.2.3 RHR SDC System - Hot Shutdown
RHR Suppression Pool Cooling 3.7.2 SW System and UHS 3.5.1 3.4.7 3.6.2.3 ECCS - Operating
RHR Suppression Pool Cooling 3.8.1 AC Sources - Operating 3.8.7 Distribution Systems - Operating (AC portion only) 3.8.2 AC Sources - Shutdown 3.8.8 Distribution Systems - Shutdown (AC portion only) 3.8.4 DC Sources - Operating 3.8.7 Distribution Systems - Operating (DC portion only) 3.8.5 DC Sources - Shutdown 3.8.8 Distribution Systems - Shutdown (DC portion only)
(continued)
TRM SFDP Appendix F Attachment 1 Brunswick Unit 2 SFDP-10 Revision No. 23 (continued)
Support System TS
Number Support System Supported System TS
Number Supported System 3.8.7 (AC only)
Distribution Systems -
Operating (AC portion
only) provides a
listing of equipment
supported by AC
distribution.
provides a
listing of electrical power
supplies supporting
PCIVs. 3.1.7 3.3.3.1 3.3.3.2
3.3.6.1
3.4.5
3.4.7 3.5.1 3.5.3 3.6.1.3 3.6.2.3 3.6.4.2 3.6.4.3 3.7.1 3.7.2 3.7.3 3.7.4 3.8.1 3.8.3 3.8.4 SLC System
PAM Instrumentation
Remote Shutdown Monitoring
Instrumentation
Primary Containment Isolation
Instrumentation
RCS Leakage Detection
Instrumentation
ECCS - Operating
RCIC System
PCIVs RHR Suppression Pool Cooling
SCIDs SGT System
RHRSW System
CREV System
Control Building AC System
AC Sources - Operating
Diesel Fuel Oil
DC Sources - Operating (continued)
TRM SFDP Appendix F Attachment 1 Brunswick Unit 2 SFDP-11 Revision No. 23 (continued)
Support System TS
Number Support System Supported System TS
Number Supported System 3.8.7 (DC only)
Distribution Systems - Operating (DC portion only) provides a listing of
electrical power supplies
supporting PCIVs.
3.3.3.1 3.3.3.2 3.3.5.1 3.3.5.2
3.3.6.1
3.3.8.1 3.4.7
3.5.1 3.5.3 3.6.1.3 3.6.2.3
3.7.1 3.7.2 3.8.1 PAM Instrumentation
Remote Shutdown System
ECCS Instrumentation
RCIC System
Instrumentation
Isolation Instrumentation
LOP Instrumentation
Shutdown ECCS - Operating
RCIC System
Cooling RHRSW System
AC Sources - Operating
(continued)
TRM SFDP Appendix F Attachment 1 Brunswick Unit 2 SFDP-12 Revision No. 23 (continued)
Support System TS
Number Support System Supported System TS
Number Supported System 3.8.8 (AC only)
Distribution Systems - Shutdown (AC portion only) provides a listing of
equipment supported by AC
distribution.
provides a listing of
electrical power supplies
supporting PCIVs.
3.3.6.1
3.4.8
3.5.2 3.6.1.3 3.6.4.2 3.6.4.3 3.7.3 3.7.4
3.8.2 3.8.3 3.8.5 3.9.7
3.9.8 Primary
Containment
Isolation Instrumentation
Shutdown ECCS - Shutdown
CREV System
Control Building AC
System AC Sources - Shutdown
Diesel Fuel Oil
DC Sources - Shutdown
RHR - High Water Level
RHR - Low Water Level
(continued)
TRM SFDP Appendix F Attachment 1 Brunswick Unit 2 SFDP-13 Revision No. 23 (continued)
Support System TS
Number Support System Supported System TS
Number Supported System 3.8.8 (DC only)
Distribution Systems - Shutdown (DC portion only) provides a listing of
electrical power supplies
supporting PCIVs.
3.3.5.1 3.3.6.1
3.3.8.1 3.4.8
3.5.2 3.6.1.3 3.8.2 3.9.7 3.9.8 ECCS Instrumentation
Isolation Instrumentation
LOP Instrumentation
Shutdown ECCS - Shutdown
RHR - High Water Level
RHR - Low Water Level
TRM SFDP Appendix F Attachment 2 Brunswick Unit 2 SFDP-14 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)
Unit 2 AC Electrical Supported Equipment - Attachment 2
SUPPORT SYSTEM AC ELECTRICAL LOAD GROUPS LCO 3.8.7, 3.8.8 LCO SUPPORTED SUBSYSTEM E1 E2 E3 E4 3.1.7 2A SLC X 2B SLC X 3.3.3.1 2A PAM INST. (FUNC. 1)
X 1 X 1 2B PAM INST. (FUNC. 1)
X 1 X 1 2A PAM INST. (FUNC. 2)
X 2B PAM INST. (FUNC. 2)
X 1 2A PAM INST. (FUNC. 3-7,9,10)
X 2B PAM INST. (FUNC. 3-7,9,10)
X PAM PCIV POSITION (FUNC. 8) 3 X X X X 3.3.3.2 REMOTE SHUTDOWN MON. INST.
X 3.3.6.1 2A HPCI/RCIC INST.
X 2B HPCI/RCIC INST.
X 3.4.5 U2 RCS LEAKAGE DETECTION X X 3.4.7, 3.4.8 2A RHR SDC X 2 X 3.9.7, 3.9.8 2B RHR SDC X 2 X 2C RHR SDC X X 2 2D RHR SDC X 1 X 3.5.1, 3.5.3 U2 HPCI X 1 X 1 U2 RCIC X 1 2A RECIRC. DISC. VALVE X 2B RECIRC. DISC. VALVE X 3.5.1, 3.5.2 2A LPCI SUBSYSTEM X X 2 2A LPCI PUMP X 2C LPCI PUMP X 2B LPCI SUBSYSTEM X X 2 2B LPCI PUMP X 2D LPCI PUMP X 2A CORE SPRAY SUBSYSTEM X 2B CORE SPRAY SUBSYSTEM X 3.6.1.3 U2 PCIVs (MOVs) 3 X X X X 1 Provides one of two power supplies. If the affected subsystem(s)/component(s) is not capable of performing its required function, the subsystem or instrument channel is inoperable. An OPERABILITY determination may be required.
2 Provides power to an MOV. If the affected supported subsystem(s)/component(s) is not capable of performing its required function, the subsystem is inoperable. An OPERABILITY determination may be required.
3 See Attachment 3 for specific valves and indication affected.
(continued)
TRM SFDP Appendix F Attachment 2 Brunswick Unit 2 SFDP-15 Revision No. 23 (continued)
SUPPORT SYSTEM AC ELECTRICAL LOAD GROUPS LCO 3.8.7, 3.8.8 LCO SUPPORTED SUBSYSTEM E1 E2 E3 E4 3.6.2.3 2A SP COOL (A or C) X X 2B SP COOL (B or D)
X X 3.6.4.2 U2 SCIDs X X 3.6.4.3 2A SGT TRAIN X 2B SGT TRAIN X 3.7.1 2A RHRSW LOOP (A or C)
X X 3.7.2 U2 NSW X X U2 CSW X X X U1 NSW X X 3.7.3 A CREV FAN X B CREV FAN X 3.7.4 1D CONTROL ROOM AC X 2D CONTROL ROOM AC X 2E CONTROL ROOM AC X 3.8.1, 3.8.2
3.8.3 DG 1 X DG 2 X DG 3 X DG 4 X 3.8.4, 3.8.5 U-2 DIV I DC X U-2 DIV II DC X U-1 DIV I DC X U-1 DIV II DC X
TRM SFDP Appendix F Attachment 3 Brunswick Unit 2 SFDP-16 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)
Unit 2 TS LCO 3.6.1.3 "PCIVs" Electrical Power Supporting PCIVs - Attachment 3
SUPPORT SYSTEM ELECTRICAL POWER DISTRIBUTION SYSTEM LCO 3.8.7, 3.8.8 AC 480 VAC EMERGENCY BUSES 250 VDC SYSTEM PCIV - MOTOR OPERATED E-5 E-6 E-7 E-8 DIV I DIV II FW 2-B21-F032A X 2-B21-F032B X MAIN STEAM 2-B21-F016 X 2-B21-F019 X RESIDUAL HEAT REMOVAL 2-E11-F007A X 2-E11-F007B X 2-E11-F008 X 2-E11-F009 X 2-E11-F011A X 2-E11-F011B X 2-E11-F015A X 2-E11-F015B X 2-E11-F016A X 2-E11-F016B X 2-E11-F017A X 2-E11-F017B X 2-E11-F020A X 2-E11-F020B X 2-E11-F021A X 2-E11-F021B X 2-E11-F024A X 2-E11-F024B X 2-E11-F027A X 2-E11-F027B X 2-E11-F028A X 2-E11-F028B X (continued)
TRM SFDP Appendix F Attachment 3 Brunswick Unit 2 SFDP-17 Revision No. 23 (continued)
SUPPORT SYSTEM ELECTRICAL POWER DISTRIBUTION SYSTEM LCO 3.8.7, 3.8.8 AC 480 VAC EMERGENCY BUSES 250 VDC SYSTEM PCIV - MOTOR OPERATED E-5 E-6 E-7 E-8 DIV I DIV II RESIDUAL HEAT REMOVAL 2-E11-F103A X 2-E11-F103B X RWCU 2-G31-F001 X 2-G31-F004 X 2-G31-F042 X REACTOR RECIRC. 2-B32-V22 X 2-B32-V30 X RCIC 2-E51-F007 X 2-E51-F008 X 2-E51-F013 X 2-E51-F019 X 2-E51-F031 X 2-E51-F062 X 2-E51-F066 X CORE SPRAY 2-E21-F001A X 2-E21-F001B X 2-E21-F004A X 2-E21-F004B X 2-E21-F005A X 2-E21-F005B X 2-E21-F015A X 2-E21-F015B X 2-E21-F031A X 2-E21-F031B X (continued)
TRM SFDP Appendix F Attachment 3 Brunswick Unit 2 SFDP-18 Revision No. 23 (continued)
SUPPORT SYSTEM ELECTRICAL POWER DISTRIBUTION SYSTEM LCO 3.8.7, 3.8.8 AC 480 VAC EMERGENCY BUSES 250 VDC SYSTEM PCIV - MOTOR OPERATED E-5 E-6 E-7 E-8 DIV I DIV II HPCI 2-E41-F002 X 2-E41-F003 X 2-E41-F006 X 2-E41-F012 X 2-E41-F042 X 2-E41-F075 X 2-E41-F079 X CAC 2-CAC-V22 X 2-CAC-V23 X RBCCW 2-RCC-V28 X 2-RCC-V52 X
TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-19 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP)
LOSF Table - Attachment 4
NOTE -----------------------------------------------------------
In addition to the TS system being a Supported Feature, the TS systems denoted with an asterisk are also Support Features. ------------------------------------------------------------------------------------------------------------------------------- LCO No. TECHNICAL SPECIFICATION SECTION
3.1.7 Standby
Liquid Control (SLC) System Two SLC subsystems inoperable. 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation For each Function, a loss of all required channels. 3.3.3.2 Remote Shutdown System For each Function (listed in Tech. Spec. Bases B 3.3.3.2), a loss of the
required channel. 3.3.4.1 ATWS-RPT Instrumentation For each Function, a loss of both channels in a trip system OR the
inability of a Recirc. pump to trip on reactor LL2 or reactor high pressure. *3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation For each Function, a loss of initiation capability as a result of a loss of one
or more required channels. *3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation 1. For Function 1, a loss of initiation capability as a result of a loss of two or more required channels. 2. For Function 2, a loss of one required channel. 3. For Function 3, a loss of both required channels. *3.3.6.1 Primary Containment Isolation Instrumentation For each Function, loss of all required channels in a trip system such that the associated Function cannot be accomplished.
(continued)
TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-20 Revision No. 23 (continued)
- 3.3.8.1 Loss of Power (LOP) Instrumentation For each Function, the loss of one or more channels on a 4.16 kV
emergency bus. *3.4.5 RCS Leakage Detection Instrumentation Loss of the Floor Monitoring Systems and the Primary Containment
Atmospheric Gaseous Monitoring System. 3.4.7 RHR Shutdown Cooling System-Hot Shutdown Both required SDC subsystems inoperable, Recirc. pumps not in operation, and no alternate method of decay heat removal. 3.4.8 RHR Shutdown Cooling System-Cold Shutdown Both required SDC subsystems inoperable, Recirc. pumps not in operation, and no alternate method of decay heat removal.
3.5.1 ECCS-Operating 1. Two or more required ADS valves inoperable. OR
- 2. HPCI and RCIC inoperable.
- 3. HPCI and two or more required ADS valves inoperable. OR
- 4. Three or more low pressure ECCS pumps (LPCI and/or Core Spray (CS)) inoperable. OR
- 5. The following combinations of two or more low pressure ECCS injection/spray subsystems inoperable:
- a. One CS subsystem and one LPCI subsystem (except one inoperable LPCI pump in the LPCI subsystem). b. Two CS subsystems.
- c. Two LPCI subsystems (except one inoperable LPCI pump in each subsystem).
(continued)
TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-21 Revision No. 23 (continued)
3.5.2 ECCS-Shutdown Both required low pressure ECCS injection/spray subsystems inoperable. 3.5.3 RCIC System RCIC and HPCI inoperable. 3.6.1.1 Primary Containment 1. Determination that a breach in Primary Containment exists such that leakage exceeds the limit specified in the Primary
Containment Leakage Rate Testing Program. OR
- 2. Drywell to suppression chamber differential pressure decreases
> 0.25 inch of water gauge per minute. *3.6.1.3 Primary Containment Isolation Valves (PCIVs) 1. For penetrations with two PCIVs, two valves inoperable on a single penetration and the penetration is not isolated. OR
- 2. For penetrations with one PCIV, one valve inoperable on a single penetration and the penetration is not isolated. 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling (SPC)
Two RHR SPC subsystems inoperable. 3.6.4.1 Secondary Containment 1. An equipment hatch or combination of hatches that results in a breach of Secondary Containment. OR
- 2. Both SGT subsystems inoperable such that neither subsystem can draw and maintain 0.25" vacuum on Secondary Containment in accordance with SR 3.6.4.1.3.
(continued)
TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-22 Revision No. 23 (continued)
- 3.6.4.2 Secondary Containment Isolation Dampers (SCIDs)
Two dampers inoperable on a single penetration and the penetration is
not isolated. 3.6.4.3 Standby Gas Treatment (SGT) System Both SGT subsystems inoperable. *3.7.1 Residual Heat Removal Service Water (RHRSW) System 1. One RHRSW pump inoperable in each RHRSW loop.
- 2. Both RHRSW subsystems inoperable.
- 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
- 3. SW System inoperable such that SW cannot be provided to the vital header, RHR SW header, or the DGs. OR
- 4. SW System inoperable such that SW cannot be provided to the A vital header and the B RHRSW header. OR
- 5. SW System inoperable such that SW cannot be provided to the B vital header and the A RHRSW header. OR
- 6. UHS > 92
°F or level less than -6 ft. mean sea level.
(continued)
TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-23 Revision No. 23 (continued)
3.7.3 Control
Room Emergency Ventilation (CREV) System 1. Two CREV subsystems inoperable for reasons other than CREV System instrumentation. OR
- 2. Two CREV subsystems inoperable due to CREV System instrumentation and no CREV subsystems operating in the
radiation protection mode. *3.7.4 Control Room Air Conditioning (AC) System Three Control Room AC subsystems inoperable. *3.8.1 AC Sources-Operating 1. Two or more DGs inoperable.
- 2. Two offsite circuits inoperable to two or more 4.16 kV emergency buses. OR
- 3. One DG inoperable and two or more 4.16 kV offsite circuits inoperable. OR
- 4. Two or more DGs inoperable and one or more 4.16 kV offsite circuits inoperable. *3.8.2 AC Sources-Shutdown All offsite circuits and the DG associated with a 4.16 kV emergency bus
required by LCO 3.8.8 are inoperable.
(continued)
TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-24 Revision No. 23 (continued)
- 3.8.3 Diesel Fuel Oil 1. One or more DGs with day fuel oil tank level < 22,650 gal. and main fuel oil storage tank level < 20,850 gal. per DG. OR
- 2. One or more DGs with day fuel oil tank level < 17,000 gal.
- 3. One or more DGs with main fuel oil storage tank level < 13,900 gal. per DG. *3.8.4 DC Sources-Operating Two or more DC divisions (Unit 1 and 2) inoperable. *3.8.5 DC Sources-Shutdown A DC subsystem (Unit 1 or 2) required to support the shutdown unit is inoperable.
(continued)
TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-25 Revision No. 23 (continued)
- 3.8.7 Distribution Systems-Operating 1. Two or more 4.16 kV emergency buses are inoperable.
- 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.
- 5. Any emergency bus (4.16 kV or 480 VAC) is inoperable concurrent with any other emergency bus (4.16 kV or 480 VAC)
inoperability such that one of the following occurs on the subject
unit:
- a. Loss of SDC capability when no recirc pumps are running.
- b. Two or more ECCS subsystems are inoperable.
- c. Two or more RHR SPC subsystems are inoperable.
- d. Both SGT subsystems are inoperable.
- e. Both RHRSW subsystems are inoperable.
- f. Two or more DGs are inoperable.
- g. SW System is inoperable due to a loss of two or more required NSW pumps. h. Two CREV subsystems are inoperable.
- i. Three Control Room AC subsystems inoperable.
(continued)
TRM SFDP Appendix F Attachment 4 Brunswick Unit 2 SFDP-26 Revision No. 23 (continued)
- 3.8.8 Distribution Systems-Shutdown 1. Any 4.16 kV emergency bus that is required to support the shutdown unit is inoperable. OR
- 2. Any 480 VAC emergency bus that is required to support the shutdown unit is inoperable. OR
- 3. A DC subsystem (Unit 1 or 2) that is required to support the shutdown unit is inoperable. 3.9.7 Residual Heat Removal (RHR)-High Water Level One required SDC subsystem inoperable and no alternate method of decay heat removal. 3.9.8 Residual Heat Removal (RHR)-Low Water Level Two required SDC subsystems inoperable and no alternate method of decay heat removal.
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-1 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP) BASES
Program Use and Application
PURPOSE AND The purpose of a Safety Function Determination (SFD) evaluation is to SCOPE detect a loss of a required Safety Function associated with systems in the Technical Specifications (TS) which could exist when an inoperable
Support Feature(s) results in a Supported Feature(s) becoming
TS 5.5.11, "Safety Function Determination Program (SFDP)," requires
implementation of a SFDP and specifies the provisions which must be
included in the SFDP.
The purpose of the SFDP is to ensure that SFD evaluations:
- 1. are performed when required;
- 2. include the required provisions in order to detect a LOSF;
- 3. ensure that the unit is placed in a safe condition if a LOSF exists; and 4. limit the time that inoperable Support Features result in Supported Features being inoperable.
One example of the Support/Supported Feature relationship is the HPCI
System initiation instrumentation/logic. This instrumentation logic is a
Support Feature for the HPCI System. The HPCI System is the
Supported Feature. Another example of the Support/Supported Feature
relationship is the DC Electrical Distribution System. This Support
Feature is several support "levels" from the Supported Feature that
performs the primary Safety Function. The DC Electrical Distribution
System is a Support Feature for the Loss of Power (LOP) Instrumentation
since DC electrical distribution subs ystems provide DC control power to the LOP instrumentation functions. The LOP Instrumentation is, in turn, the Support Feature for the AC Electrical Distribution System since the
LOP instruments support the 4.16 kV emergency buses. Finally, the AC
Electrical Distribution System supports the Emergency Core Cooling
Systems (ECCS) since the AC emergency buses supply power to the low
pressure ECCS subsystems. Note that each support level has a
corresponding Safety Function. For example, the Safety (continued)
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-2 Revision No. 23 Program Use and Application
PURPOSE AND Function of the LOP Instrumentation is to monitor and actuate, if required, SCOPE to ensure the AC Electrical Distribution System is powered (from offsite (continued) or onsite AC power sources) during assumed accidents or transients.
The Support/Supported Feature relationship is generally identified in the
associated TS Bases. Attachment 1 also provides a limited listing of
Support/Supported Feature relationships.
TS LCO 3.0.6 establishes an exception to TS LCO 3.0.2 for Support
Features that have an LCO specified in the TS. This exception is
provided because TS LCO 3.0.2 would require that the Conditions and
Required Actions of the associated inoperable Supported Feature TS be
entered solely due to the inoperability of Support Features. This
exception is justified because the remedial actions that are required to
ensure the plant is maintained in a safe condition are specified in the
Support Feature's TS ACTIONS. The TS Required Actions may include
entering the Supported Feature's Conditions and Required Actions. TS
LCO 3.0.6 specifies when a SFD must be performed.
Upon entry into TS LCO 3.0.6, the SFDP shall be used to determine if
LOSF exists. Additionally, other limitations, remedial actions, or compensatory actions may be identified as a result of the Support
Feature inoperability.
When a Support Feature is inoperable and there is an LCO specified for
the feature in TS, the Supported Feature(s) LCO may be not met as a
result of the Support Feature inoperability. However, it is not necessary
to enter the Supported Features' TS ACTIONS unless directed to do so
by the Support Feature's TS ACTIONS provided the associated Safety
Function is retained.
Definitions in the SFDP are initially capitalized throughout the SFDP and
Bases. (continued)
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-3 Revision No. 23 Program Use and Application (continued)
CASCADING A SFD is only required during specific instances when TS LCO 3.0.6 REQUIREMENTS is entered and two or more Support or Supported Features are inoperable. Therefore, it is important to know when TS LCO 3.0.6 is
applicable. TS LCO 3.0.6 is applicable in instances when a Supported
Feature LCO is not met solely due to a Support Feature LCO not being
met (i.e., a Supported Feature is inoperable due to a Support Feature
being inoperable).
Per TS LCO 3.0.2, the applicable Conditions for the inoperable Support
Feature shall be entered and the associated Required Actions performed.
The TS ACTIONS are documented in accordance with Procedure No.
0OI-01.08, "Control of Equipment and System Status."
It may not be obvious that an associated Supported Feature is inoperable
when a Support Feature is inoperable. Therefore, an OPERABILITY
Determination should be performed to determine if the inoperable Support
Feature does result in a Supported Feature becoming inoperable. If the
inoperable Support Feature does not result in any Supported Features
becoming inoperable, then TS LCO 3.0.6 is not applicable and a SFD is
not required. However, if the inoperable Support Feature does result in a
Supported Feature(s) becoming inoperable, then the Supported
Feature(s) shall be considered inoperable and LCO 3.0.6 applies.
Typically, TS LCO 3.0.6 does not require "cascading" to the associated
Supported Feature TS since the Support Feature TS ACTIONS are
considered sufficient (e.g., the Support Feature allowable out of service
time is the same or more restrictive than the allowable out of service time
of the Supported Features). In some cases, the TS ACTIONS of the
Support Feature require cascading to the Supported Feature TS
ACTIONS. Cascading to the Supported Feature TS ACTIONS is required
if the feature is not controlled by a TS (e.g., ECCS room coolers) since
the TS definition of OPERABILITY applies and the requirements of
LCO 3.0.6 are not applicable to non-TS support features. Cascading to
the Supported Feature TS ACTIONS is also required if the Support
Feature TS ACTIONS require cascading. If cascading is required, a SFD
is not required.
(continued)
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-4 Revision No. 23 Program Use and Application
CASCADING Unless cascading is required, TS LCO 3.0.6 does not require entry into REQUIREMENTS the TS ACTIONS for the inoperable Supported Feature(s) unless a LOSF (continued) exists. Therefore, a SFD must be performed to ensure Safety Function is maintained. The TS ACTIONS of the inoperable Supported Feature may
be entered even if the Safety Function is retained. However, this is a
conservative decision. If a decision is made to cascade to the Supported
Feature(s) TS, a SFD evaluation is not required.
The SFDP requires cross division checks to identify a LOSF for those
Support Features that support safety systems. The SFD evaluation
should include an administrative cross divisional check to verify that the
Supported Features of the redundant OPERABLE Support Features are
OPERABLE, thereby ensuring Safety Function is retained. The
evaluation should also include a conclusion as to the status of the Safety
Function (i.e., Safety Function maintained or lost). The SFD should be
performed by a licensed Senior Reactor Operator or another qualified
member of the technical staff. If this SFD evaluation determines that a
LOSF exists, the appropriate Conditions and Required Actions of the TS
in which the LOSF exists are required to be entered. Attachment 4 of the
SFDP provides all known combinations of Supported Feature
inoperabilities where a LOSF exists.
In addition, since the TS ACTIONS associated with the Support Feature
restricts plant operation, the single failure criterion does not have to be
considered when determining OPERABILITY of the Supported
Feature(s).
MAXIMUM A Supported Feature(s) made inoperable by Support Feature COMPLETION inoperabilities may only remain inoperable for a limited period of time TIME (without entering the Supported Feature TS ACTIONS). This time limit is defined as the Maximum Completion Time. The Maximum Completion
Time for restoring the Supported Feature(s) to OPERABLE status is the
Completion Time specified in TS for restoring the first inoperable Support Feature to OPERABLE status plus the Completion Time specified in TS for restoring the inoperable Supported Feature to OPERABLE status.
This Maximum Completion Time requirement includes restoring all Support Features to OPERABLE status.
(continued)
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-5 Revision No. 23 Program Use and Application
MAXIMUM The Maximum Completion Time establishes a limit on the maximum COMPLETION time allowed for any combination of Support Features and Supported TIME Features being inoperable during a single contiguous occurrence of (continued) failing to meet the Suppor ted Feature's TS LCO. This "Maximum Completion Time" philosophy is similar to that of TS Section 1.3, Completion Times.
(continued)
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-6 Revision No. 23 Program Use and Application
MAXIMUM COMPLETION EXAMPLE 3.1-1 TIME (continued)
Assume that Systems A and B are TS systems and they Support System C. The Completion Times for restoring the systems to OPERABLE status
are; 3 days for System A, 7 days for System B, and 7 days for System C.
If System A becomes inoperable and makes System C inoperable, then
the maximum Completion Time for restoring System C to OPERABLE
status is 10 days (3 days plus 7 days).
(continued)
Maximum Com p letion Time 3 da y s 7 da y s 3 da y s + 7 da y s = 10 da y sSystem A Da y 1 Da y 3 S y stem C Da y 10 Da y 3 S y stem B Da y 3 Da y 10 TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-7 Revision No. 23 Program Use and Application
MAXIMUM Example 3.1-1 (continued)
COMPLETION TIME If System C should then become inoperable for reasons other than the support system being inoperable on Day 3 (time from System A
inoperability; System A is restored to OPERABLE status later on Day 3),
then System C must be restored to OPERABLE status by Day 10 (within
7 days). Subsequently, if System B should become inoperable on Day 8 (time from System A inoperability), t hen System B must also be restored
to OPERABLE status by Day 10 (within 2 days instead of 7 days) in order
to restore System C to OPERABLE status within its 10-day Maximum
Completion Time.
The Maximum Completion Time is considered an acceptable limitation on
the potential to fail to meet the Supported Feature's TS LCO indefinitely.
If System C is not restored to OPERABLE status within 10 days (by
restoring Systems A and B to OPERABLE status), then the Condition in
TS for System C which states, "Required Action and associated
Completion Time not met," shall be entered and the associated Required
Actions shall be performed.
SFD For every subsequent inoperability, a review of the SFD is required to REVIEW ensure that the SFD remains valid and a LOSF has not occurred. This includes inoperabilities as a result of surveillance testing or maintenance.
This also includes inoperabilities as a result of declaring a Supported Feature inoperable per TS ACTIONS.
A complete re-evaluation of all redundant supported subsystems and
associated support subsystems should be performed to ensure the Safety
Function is maintained with the additional inoperabilities.
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-8 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP) BASES
Safety Function Determination (SFD) Evaluation Examples
SFD The plant is operating in MODE 3 with reactor pressure at < 75 psig. The EVALUATION "A" RHR-SDC subsystem is in operation and the "C" and "D" RHR-SDC EXAMPLE 1 subsystems are OPERABLE. The "B" RHR pump has been removed from service for maintenance on the motor. Condition A of both
TS 3.6.2.3, "RHR Suppression Pool Cooling," and TS 3.5.1, "ECCS-
Operating," were entered at 1500 on 1/1/98.
At 2100 on 1/2/98, the breaker for the "C" RHRSW pump tripped on
overload. TS 3.7.1, "RHRSW System," Condition A was entered. TS 3.6.2.3 ACTIONS do not yet have to be entered per LCO 3.0.6.
The following is the SFD for the Supported Features:
- Although the "C" RHR-SDC subsystem became inoperable at 2100 on 1/2/98, the "D" RHR-SDC subsystem is OPERABLE.
Therefore, LCO 3.4.7, "RHR Shutdown Cooling System - Hot
Shutdown," is met and LCO 3.0.6 is not applicable to TS 3.4.7.
- The safety analysis for RHR-SPC requires 8000 gpm service water flow to ensure an RHR-SPC subsystem can perform its
Safety Function. As a result, LCO 3.6.2.3 is not met due to the "A" RHR-SPC subsystem inoperable (one RHRSW pump inoperable).
However, TS 3.6.2.3 ACTIONS do not yet have to be entered per
- Per LCO 3.0.6 and TS 5.5.11, a SFD must be performed and would reveal that the "B" RHR-SPC subsystem has been
inoperable since 1500 on 1/1/98. Since the "A" RHR-SPC
subsystem is inoperable concurrent with the "B" RHR-SPC
subsystem, a LOSF exists for TS 3.6.2.3.
==
Conclusion:==
TS 3.6.2.3 Condition A should be continued for the "A" RHR-SPC subsystem inoperable and TS 3.6.2.3 Condition B should be
entered immediately upon discovery of the LOSF.
(continued)
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-9 Revision No. 23 SFD Evaluation Examples
SFD Assuming the "B" RHR pump is restored to OPERABLE status by 1500 EVALUATION on 1/8/98 and the "C" RHRSW pump is restored to OPERABLE status by EXAMPLE 1 2100 on 1/16/98, the Maximum Completion Time for restoring the "A" (continued) RHR-SPC subsystem to OPERABLE status following subsequent contiguous inoperabilities (including all Support Features) is 2100 on
1/23/98; 14 days (TS 3.7.1 Required Action A.1) plus 7 days (TS 3.6.2.3
Required Action A.1).
SFD Unit 2 is operating at 100% power. A portion of SR 3.3.5.2.5 is being EVALUATION performed to verify Relay K-52 is OPERABLE. TS 3.3.5.2, "RCIC System EXAMPLE 2 Instrumentation," Condition C was entered at 0300 on 4/2/98 due to the testing. Six hours has elapsed as allowed by Note 2 to the Surveillance
Requirements. At 2000 on 4/2/98, the 2A DC Switchboard de-energizes
due to an internal electrical short. TS 3.8.7, "Distribution Systems-
Operating," Condition C is entered.
The following is the SFD for the Supported Features:
- The HPCI System is inoperable due to the loss of power to much of the system. However, TS 3.5.1, "ECCS-Operating," ACTIONS
do not have to be entered per LCO 3.0.6.
- The Bases for TS 3.5.3, "RCIC System," states that the function of the RCIC System is to provide core cooling during a loss of
feedwater event. Since the RCIC System can still perform its
required function in the above condition (RCIC high water level trip
inoperable), it can be considered OPERABLE and a LOSF has not
occurred.
==
Conclusion:==
Since a LOSF has not occurred, entry into TS 3.5.1 or TS 3.5.3 ACTIONS is not required at this time. However, if SR 3.3.5.2.5 is
not satisfactorily completed by 0300 on 4/3/98, TS 3.3.5.2
Required Action E.1 requires declaring the RCIC System
inoperable and TS 3.5.3 Condition A must be entered.
(continued)
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-10 Revision No. 23 SFD Evaluation Examples
SFD A review of the SFD (refer to Attachment 4 of the SFDP) will show that EVALUATION the HPCI and RCIC Systems are both inoperable. Therefore, TS 3.5.1 EXAMPLE 2 Condition I must be entered and TS 3.5.3 Condition B must be entered (continued) upon discovery that both systems are inoperable.
Assuming that Relay K-52 is demonstrated OPERABLE by 0300 on
4/3/98 and the 2A DC Switchboard is restored to OPERABLE status by
2000 on 4/9/98, the Maximum Completion Time for restoring the HPCI
System to OPERABLE status following subsequent contiguous
inoperabilities (including all Support Features) is 2000 on 4/23/98; 7 days (TS 3.8.7 Required Action C.1) plus 14 days (TS 3.5.1 Required Action
D.2). SFD Unit 1 is in MODE 5 and Unit 2 is operating at 100% power. At 0900 on EVALUATION 10/2/98, Diesel Generator (DG)
- 1 was removed from service to perform EXAMPLE 3 preventative maintenance and Unit 2 TS 3.8.1, "AC Sources-Operating," Condition C is entered. Unit 1 LCO 3.8.2, "AC Sources-Shutdown," is
met. During the performance of SR 3.3.5.1.2 on Unit 2, it was discovered
that improper grounding resulted in a failure of Relays K-11B and K-10B
on Unit 2 core spray logic. I&C reports that the "B" core spray logic is
inoperable and the "A" core spray logic is still OPERABLE. The "B" core
spray logic (TS 3.3.5.1, "ECCS Instrumentation," Functions 1.a, 1.b, and
1.c) is declared inoperable at 1500 on 10/4/98.
Unit 2 TS 3.3.5.1 Conditions B and C are entered at this time. Required
Actions B.1 and C.1 are not applicable at this time since "A" core spray
initiation capability is still available. Required Actions B.3 and C.2 allow
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to fix the relays before declaring the Supported Features
inoperable. TS 3.5.1, "ECCS-Operating," ACTIONS do not yet have to be
entered per LCO 3.0.6.
The following is the SFD for the Supported Features:
- Although core spray Relay K-11B is not available to start the emergency diesel generators, Relay K-11A is still OPERABLE.
Therefore, DGs 2,3, and 4 will start if required and are still
considered OPERABLE and a LOSF has not occurred.
(continued)
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-11 Revision No. 23 SFD Evaluation Examples
SFD * ----------------------------------------NOTE---------------------------------------- EVALUATION The DGs cannot withstand a single failure (i.e., failure of core EXAMPLE 3 spray Relay K-11A), however, plant operation is limited by (continued) TS 3.3.5.1 ACTIONS.
The 2A LPCI subsystem is still OPERABLE since offsite power is available to the E1 4.16 kV bus. However, the Completion Time
for TS 3.8.1 Required Action C.2 begins at 1500 on 10/4/98 since
E1 supplies power to the 2A LPCI subsystem (2C LPCI pump and
LPCI injection valves) and 2A LPCI is redundant to the 2B core
spray subsystem. Since only one low pressure ECCS subsystem is inoperable a LOSF has not occurred.
==
Conclusion:==
Since all ECCS will initiate except 2B core spray, the Safety Function is maintained and TS 3.5.1 ACTIONS do not have to be
entered at this time. However, at 1900 on 10/4/98, TS 3.8.1
Required Action C.2 requires declaring the 2A LPCI subsystem
inoperable and TS 3.5.1 Condition A must be entered. A review of
the SFD at this time (refer to Attachment 4 of the SFDP) will show
that the 2A LPCI subsystem and 2B core spray subsystem are
both inoperable. Therefore, TS 3.5.1 Condition J must be entered
upon discovery that both low pressure ECCS subsystems are
inoperable. In addition, TS 3.5.1 Condition A should be continued
and TS 3.5.1 Condition B should be entered for the 2B core spray
subsystem inoperable. Assuming DG#1 is restored to OPERABLE status prior to completion of the shutdown required by LCO 3.0.3 and the 2B
core spray logic is restored to OPERABLE status by 1500 10/5/98, the Maximum Completion Time for restoring the 2B core spray
subsystem to OPERABLE status following subsequent contiguous
inoperabilities (including all Support Features) is 1500 on 10/12/98; 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (TS 3.3.5.1 Required Action C.2) plus 7 days (TS 3.5.1 Required Action A.1).
(continued)
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-12 Revision No. 23 SFD Evaluation Examples (continued)
SFD A 480 VAC emergency bus (E8) indicates a ground fault at 1300 on EVALUATION 7/2/98. Further investigation reveals that, although all E8 loads seem to EXAMPLE 4 be operating normally, a high impedance ground fault has developed on the E8 emergency bus (cause unknown). Engineering has been
contacted to provide technical support and perform an OPERABILITY
Determination.
Unit 2 is operating at 100% power. At 2300 on 7/5/98, the control power
transformer fuse fails in the 2A SGT fan motor control circuit.
Maintenance reports that the failing of the fuse damaged the fuse holder
and it may take 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to correct the problem. All secondary
containment isolation instrumentation functions are declared inoperable
for the 2A SGT subsystem and TS 3.3.6.2, "Secondary Containment
Isolation Instrumentation," Condition A is entered. TS 3.6.4.3, "SGT
System," ACTIONS do not yet have to be entered per LCO 3.0.6.
Engineering reports at 0900 on 7/6/98 that the margin in the AC
Distribution Voltage Study shows that the high impedance fault results in
E8 being inoperable. TS 3.8.7, "Distribution Systems - Operating,"
Condition A is entered at this time. TS 3.6.4.3 ACTIONS do not yet have
to be entered per LCO 3.0.6.
The following is the SFD for the Supported Features:
- LCO 3.6.4.2, "SCIDs," is still met since the failure of the secondary containment isolation instrumentation functions only
affects the 2A SGT subsystem and is independent of the
secondary containment isolation dampers.
- Improper voltage (as a result of the ground) on the E8 results in the 2B SGT subsystem becoming inoperable. Per LCO 3.0.6 and
TS 5.5.11, a SFD must be performed and would reveal that the 2A
SGT subsystem has been inoperable since 2300 on 7/5/98. Since
the 2A SGT subsystem is inoperable concurrent with the 2B SGT
subsystem, a loss of LOSF exists for TS 3.6.4.3.
==
Conclusion:==
TS 3.6.4.3 Conditions A and B should be entered immediately upon discovery of the LOSF.
(continued)
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-13 Revision No. 23 SFD Evaluation Examples
SFD Assuming either E8 is restored to OPERABLE status or the 2A SGT fan EVALUATION is restored to OPERABLE status prior to the completion of the plant EXAMPLE 4 shutdown required by TS3.6.4.3 Condition B and both E8 and 2A SGT (continued) instrumentation are restored to OPERABLE status within their associated Completion Times, the Maximum Completion Time for restoring the 2A
SGT subsystem to OPERABLE status following subsequent contiguous
inoperabilities (including all Support Features) is 1100 on 7/13/98; 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> (TS 3.8.7 Required Action A.1) plus 7 days (TS 3.6.4.3
Required Action A.1).
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-14 Revision No. 23 SAFETY FUNCTION DETERMINATION PROGRAM (SFDP) BASES Attachments
ATTACHMENT 1 This attachment is an aid which identifies the Supported Features associated with each Support Feature Technical Specification (TS). The
Table includes the TS number and title of the support system and
supported systems so the appropriate TS and Bases may be reviewed.
The Table of Support vs. Supported Features does not infer that a
Support Feature inoperability results in all Supported Features becoming
inoperable. The Table only provides Supported Feature TS that may be
affected. To ensure the list is user friendly, the list is minimized to the
extent practical. Therefore, features that are not in TS are not included in since TS LCO 3.0.6 does not apply to these features (e.g.,
ECCS room cooler subsystems). Additionally, Support Features that
exclusively support only one Supported Feature and contain TS
ACTIONS that require cascading to the Supported Feature TS ACTIONS
are generally not included in Attachment 1 (e.g., Control Rod
Accumulators). Support Features that are "failsafe" upon loss of power (i.e., loss of power results in the feature automatically performing its
required Safety Function), are also not listed since the Safety Function is
performed upon loss of power (e.g., loss of DC power to RPS electric
power monitoring assemblies).
ATTACHMENT 2 This attachment provides a list of all TS equipment affected by a loss of a single emergency load group (i.e., a loss of a single 4.16 kV emergency
bus) except equipment that is "failsafe." If a supported subsystem is "failsafe" upon loss of AC power, the supported subsystem is not listed in
. Additionally, this Attachment is limited to redundant
supported subsystems and does not provide detail as to which component has lost power. Unless otherwise noted, an "X" in the support
subsystem column indicates the supported subsystem is inoperable.
ATTACHMENT 3 This attachment provides a list of all the motor-operated primary containment isolation valves (PCIVs) and their associated power
supplies. If a motor-operated valve is open and loses power, it cannot
provide the required isolation function.
(continued)
TRM SFDP Appendix F Bases Brunswick Unit 2 B SFDP-15 Revision No. 23 Attachments
ATTACHMENT 3 This attachment is an aid which identifies all of the affected PCIVs.
(continued) If the PCIV is closed and loses power, inherently the Safety Function is maintained. Some of the PCIVs have a normal and alternate power
supply. As noted, PCIVs are considered OPERABLE provided power is
available to the motor-operator.
ATTACHMENT 4 This attachment provides all known combinations of inoperabilities where LOSF exists. The attachment includes combinations of inoperabilities
that require a plant shutdown or entry into TS LCO 3.0.3 per the
Supported Feature TS.
Additionally, this attachment only includes loss of function for systems
used to perform Safety Function Determinations. If a TS system is
supported by a system that is not a TS system, the non-TS support feature is not included in the attachment because TS LCO 3.0.6 is not
applicable for this case. If a TS system is supported by another TS
system but the TS ACTIONS for the inoperable TS Support Feature
require "cascading" into the TS ACTIONS for the Supported Feature TS, then a LOSF for this Supported Feature is not included in the attachment
because TS LCO 3.0.6 is not applicable for this case.
Several TS LCOs do not require all installed features (e.g., only six of
seven ADS valves are required to be OPERABLE to meet LCO 3.5.1). As
such, the word required is underlined in Attachment 4 to indicate only
those features required to meet the LCO. Since the NRC has previously
approved the TS, continued operation with plant degradations within the
bounds of the Supported Feature TS is allowed. Continued operation
with plant degradations outside the bounds of the Supported Feature TS
is not allowed. Therefore, if the combination of inoperabilities results in a
LOSF as defined in Attachment 4 (i.e., continued plant operation is not
allowed by the Supported Feature TS), the appropriate Conditions of the
Supported Feature TS must be entered and the Required Actions
performed.