ML25356A488
| ML25356A488 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/04/2025 |
| From: | Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML25356A488 (0) | |
Text
LJC:L:.
U'"+/- 1 L.UL.:::>
MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2025-13145 USER INFORMATION:
GERLACH*ROSEY M Address: NUCSA2 Phone#:
542-3194 EMPL#:028401 CA#:
0363 TRANSMITTAL INFORMATION:
TO:
GERLACH*ROSEY M 12/04/2025 LOCATION:
USNRC FROM:
NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)
Page 1
THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU.
HARDCOPY USERS MUST ENSURE THE DOCUMENTS PROVIDED MATCH THE INFORMATION ON THIS TRANSMITTAL.
WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE THE UPDATE DOCUMENT ID IS THE SAME DOCUMENT ID YOU'RE REMOVING FROM YOUR MANUAL.
TOOLS FROM THE HUMAN PERFORMANCE TOOL BAG SHOULD BE UTILIZED TO ELIMINATE THE CHANCE OF RRORS.
ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material.
TRM2 - TECHNICAL REQUIREMENTS MANUAL UNIT 2 REMOVE MANUAL TABLE OF CONTENTS DATE: 10/30/2025 ADD MANUAL TABLE OF CONTENTS DATE: 12/03/2025 CATEGORY: DOCUMENTS TYPE: TRM2 of 5
ID:
TEXT 1.1 REMOVE:
REV:1 ADD:
REV: 2 CATEGORY: DOCUMENTS TYPE: TRM2 ID:
TEXT 3.0 REMOVE:
REV:8 ADD:
REV: 9 CATEGORY: DOCUMENTS TYPE: TRM2 ID:
TEXT 3.1.2 ADD:
REV: 1 REMOVE :
REV: 0 CATEGORY: DOCUMENTS TYPE: TRM2 ID:
TEXT 3.3.9 REMOVE:
REV:3 D:
REV: 4 CATEGORY: DOCUMENTS TYPE: TRM2 ID:
TEXT 3.4.1 ADD:
REV: 2 REMOVE:
REV:1 CATEGORY: DOCUMENTS TYPE: TRM2 ID:
TEXT 3.4.6 REMOVE:
REV:1 Llt::L:.
U'+/- 1 L.UL.:J Page 2
of 5
ADD:
REV: 2 CATEGORY: DOCUMENTS TYPE: TRM2 ID:
TEXT 3.5.3 ADD:
REV: 2 REMOVE:
REV :1 CATEGORY: DOCUMENTS TYPE : TRM2 ID:
TEXT 3.7. 11 ADD :
REV : 3 REMOVE:
REV : 2 CATEGORY: DOCUMENTS TYPE : TRM2 ID:
TEXT 3.7.9 REMOVE :
REV: 2 ADD :
REV: 3 ATEGORY: DOCUMENTS D:
TEXT 3.8. 1 ADD:
REV: 5 REMOVE:
REV:4 TYPE : TRM2 CATEGORY: DOCUMENTS TYPE: TRM2 ID:
TEXT B3.0 REMOVE :
REV: 7 ADD:
REV : 8 CATEGORY: DOCUMENTS TYPE: TRM2 Lit:!'-.,.;.
V"+/-,
L.VL.::J Page 3
of 5
ID :
TEXT B3.1.2 REMOVE :
REV: 0 ADD:
REV: 1 CATEGORY: DOCUMENTS TYPE: TRM2 ID:
TEXT B3.3.9 ADD:
REV: 5 REMOVE:
REV:4 CATEGORY: DOCUMENTS TYPE: TRM2 ID:
TEXT B3.4.1 REMOVE:
REV:0 ADD:
REV: 1 CATEGORY: DOCUMENTS TYPE: TRM2 ID:
TEXT B3.4.6 REMOVE:
REV:2 a
D:
REV: 3 CATEGORY: DOCUMENTS TYPE: TRM2 ID:
TEXT B3.5.3 REMOVE :
REV : 2 ADD:
REV: 3 CATEGORY: DOCUMENTS TYPE: TRM2 ID:
TEXT B3.7.11 ADD:
REV: 4 Page 4
of 5
LJC:L.:.
U'"+/- 1 L.UL.::>
REMOVE:
REV:3 CATEGORY: DOCUMENTS TYPE: TRM2 ID:
TEXT B3.7.9 REMOVE :
REV : 3 ADD:
REV: 4 CATEGORY: DOCUMENTS TYPE: TRM2 ID:
TEXT B3.8.1 ADD:
REV: 3 REMOVE:
REV:2 CATEGORY: DOCUMENTS TYPE: TRM2 ID:
TEXT TOC ADD:
REV: 30 REMOVE:
REV: 29 Page 5
~
y DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS @ X3171 OR X3194 FOR
.,_SSISTANCE.
UPDATES FOR HARDCOPY MANUALS WILL BE DISTRIBUTED WITHIN 3 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES.
PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON COMPLETION OF UPDATES.
FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.
of 5
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 Table Of Contents Issue Date:
12/03/2025 Procedure Name Rev Issue Date TEXT LOES 99 01/03/2019
Title:
LIST OF EFFECTIVE SECTIONS TEXT TOC
Title:
TABLE OF CONTENTS TEXT 1.1 30 2
12/03/2025 12/03/2025
Title:
USE AND APPLICATION DEFINITIONS Change ID TEXT 2.1 1
02/04/2005
'" 1 SETPOINTS PLANT PROGRAMS y
Title:
PLANT PROGRAMS AND TEXT 2.2 13 06/29/2023
Title:
PLANT PROGRAMS AND SETPOINTS I NSTRUMENT TRIP SETPOINT TABLE TEXT 3.0 9
12/03/2025 Change Number
Title:
APPLICABILITY TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT 3.1.1 2
01/15/2025
Title:
REACTIVITY CONTROL SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS - ARI) INSTRUMENTATION TEXT 3.1.2 1
12/03/2025
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT 3.1.3 5
12/18/2017
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.1.4 2
10/08/2025
Title:
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT 3.2.1 22 04/02/2025
Title:
CORE OPERATING LIMITS REPORT (COLR)
Page 1 of 15 Report Date: 12/03/25
f SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.3.1 0
11/19/2002
Title:
INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION TEXT 3.3.2 3
03/31/2011
Title:
INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3 2
11/09/20 07
Title:
INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4 11 07/21/2017
Title:
INSTRUMENTATION TRM POST-ACCIDENT MONITORING INSTRUMENTATION TEXT 3.3.5 0
11/19/2002
Title:
INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK TEXT 3.3.6 6
06/29/ 2023
Title:
INSTRUMENTATION TRM ISOLATION ACTUATION INSTRUMENTATION TEXT 3.3.7 6
04/16/2024
Title:
INSTRUMENTATION MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT 3.3.8 1
10/22/2003
Title:
INTENTIONALLY LEFT BLANK TEXT 3.3.9 4
12/03/2025
Title:
INSTRUMENTATION LPRM UPSCALE ALARM INSTRUMENTATION TEXT 3.3.10 1
12/14/2004
Title:
INSTRUMENTATION REACTOR RECIRCULATION PUMP MG SET STOPS TEXT 3.3.11 1
10/22/2003
Title:
INSTRUMENTATION MVP ISOLATION INSTRUMENTATION TEXT 3.3.12 2
04/02/2019
Title:
WATER MONITORING INSTRUMENTATION Page 2 of 15 Report Date: 12/03/25
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.4.1 2
12/03/2025
Title:
REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY TEXT 3.4.2 1
04/16/2009
Title:
INTENTIONALLY LEFT BLANK TEXT 3.4.3 1
11/09/2007
Title:
REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM (RCS)
TEXT 3.4.4 2
05/14/2009
Title:
REACTOR COOLANT SYSTEM REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT 3.4.5 1
04/26/2006
Title:
REACTOR COOLANT SYSTEM REACTOR VESSEL MATERIALS TEXT 3.4.6 2
12/03/2025
Title:
REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION TEXT 3.5.1 2
03/05/2019
Title:
ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM ADS MANUAL INHIBIT TEXT 3.5.2 2
03/05/2019
Title:
ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM ECCS RPV WATER INVENTORY CONTROL AND RCIC MONITORING INSTRUMENTATION TEXT 3.5.3 2
12/03/2025
Title:
ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM LONG TERM NITROGEN SUPPLY TO ADS TEXT 3.6.1 1
11/27/2023
Title:
CONTAINMENT VENTING OR PURGING TEXT 3.6.2 3
01/03/2019
Title:
SUPPRESSION CHAMBER TO DRYWELL VACUUM BREAKER POSITION INDICATION TEXT 3.6.3 0
11/19/2002
Title:
CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION Page 3 of 15 Report Date: 12/03/25
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.6.4 1
11/27/2023
Title:
CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT 3.7.1 0
11/19/2002
Title:
PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN TEXT 3. 7. 2 1
11/27/2023
Title:
PLANT SYSTEMS ULTIMATE HEAT SINK (UHS) AND GROUND WATER LEVEL TEXT 3.7.3.1 7
04/21/2022
Title:
PLANT SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT 3.7.3.2 3
04/16/2009
Title:
PLANT SYSTEMS SPRAY AND SPRINKLER SYSTEMS TEXT 3.7.3.3 4
05/16/2016
Title:
PLANT SYSTEMS CO2 SYSTEMS TEXT 3.7.3.4 2
04/16/2009
Title:
PLANT SYSTEMS HALON SYSTEMS TEXT 3.7.3.5 2
04/16/2009
Title:
PLANT SYSTEMS FIRE HOSE STATIONS TEXT 3.7.3.6 2
04/16/2009
Title:
PLANT SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT 3.7.3.7 1
04/26/2006
Title:
PLANT SYSTEMS FIRE RATED ASSEMBLIES TEXT 3.7.3.8 15 08/02/2021
Title:
PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION TEXT 3.7.4 2
11/27/2023
Title:
PLANT SYSTEMS SOLID RADWASTE SYSTEM Page 4 of 15 Report Date: 12/03/25
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.7.5.1 1
03/05/2 015
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT 3. 7.5.2 0
11/19/2002
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE TEXT 3.7.5.3 1
04/26/20 06
Title:
PLANT SYSTEMS LIQUID HOLDUP TANKS TEXT 3.7.6 3
06/04/2 012
Title:
PLANT SYSTEMS ESSW PUMPHOUSE VENTILATION TEXT 3.7.7 2
09/05/2 008
Title:
PLANT SYSTEMS MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMI C RADIATION MONITORING INSTRUMENTATION TEXT 3. 7.8 9
03/05/2 015
Title:
PLANT SYSTEMS SNUBBERS TEXT 3.7.9 3
12/ 03/2025
Title:
PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7.10 2
04/29/2 014
Title:
PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS )
TEXT 3.7.11 3
12/03/2025
Title:
PLANT SYSTEMS TEXT 3.8.1 5
12/03/2025
Title:
ELECTRI CAL POWER PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT 3.8.2. 1 3
09/19/2 023 Title : ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -
CONTINUOUS TEXT 3.8.2.2 3
06/23/2 021
Title:
ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -
AUTOMATIC Page 5 of 15 Report Date: 12/03/25
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.8.3 4
01/28/2020
Title:
ELECTRICAL POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT 3.8.4 2
11/27/2023
Title:
ELECTRICAL POWER 24 VDC ELECTRICAL SUBSYSTEM TEXT 3.8.5 1
11/14/2013
Title:
ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION TEXT 3.8.6 3
03/05/2019
Title:
ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING TEXT 3.8.7 3
02/25/2021
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM TEXT 3.9.1 0
11/19/2002
Title:
REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0
11/19/2002
Title:
REFUELING OPERATIONS COMMUNICATIONS TEXT 3.9.3 1
03/12/2019
Title:
REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1 2
11/27/2023
Title:
MISCELLANEOUS SEALED SOURCE CONTAMINATION TEXT 3.10.2 1
04/09/2007
Title:
MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 4
10/05/2022
Title:
MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT 3.10.4 2
04/17/2009
Title:
INTENTIONALLY LEFT BLANK Page 6 of 15 Report Date: 12/03/25
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3. 11. 1. 1 2
11/27/2023
Title:
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION TEXT 3.11.1.2 2
11/27/2023
Title:
RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE TEXT 3. 11. 1. 3 2
11/27/2023
Title:
RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT SYSTEM TEXT 3.11.1.4 3
11/27/2023
Title:
RADIOACTIVE EFFLUENTS LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.1.5 4
11/27/2023
Title:
RADIOACTIVE EFFLUENTS RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT 3. 11. 2. 1 5
11/27/2023
Title:
RADIOACTIVE EFFLUENTS DOSE RATE TEXT 3.11.2.2 2
11/27/2023
Title:
RADIOACTIVE EFFLUENTS DOSE -
NOBLE GASES TEXT 3.11.2.3 2
11/27/2023
Title:
RADIOACTIVE EFFLUENTS DOSE -
IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM TEXT 3.11.2.4 1
11/27/2023
Title:
RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM TEXT 3.11.2.5 5
11/27/2023
Title:
RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM TEXT 3.11.2.6 9
11/27/2023
Title:
RADIOACTIVE EFFLUENTS RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.3 2
11/27/2023
Title:
RADIOACTIVE EFFLUENTS TOTAL DOSE Page 7 of 15 Report Date: 12/03/25
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3. 11. 4. 1 7
06/27/2024
Title:
RADIOACTIVE EFFLUENTS MONITORING PROGRAM TEXT 3. 11. 4. 2 3
11/27/2023
Title:
RADIOACTIVE EFFLUENTS LAND USE CENSUS TEXT 3.11.4.3 2
11/27/2023
Title:
RADIOACTIVE EFFLUENTS INTERLABORATORY COMPARISON PROGRAM TEXT 3.12.1 0
11/19/2002
Title:
LOADS CONTROL PROGRAM CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT 3.12.2 4
04/17/2008
Title:
LOADS CONTROL PROGRAM HEAVY LOADS REQUIREMENTS TEXT 3.12.3 0
11/19/2002
Title:
LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENTS TEXT 4.1 0
09/27/2003
Title:
ADMINISTRATIVE CONTROLS ORGANIZATION TEXT 4.2 1
01/03/2019
Title:
ADMINISTRATIVE CONTROLS REPORTABLE EVENT ACTION TEXT 4.3 1
01/03/2019
Title:
ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION TEXT 4.4 1
12/18/2008
Title:
ADMINISTRATIVE CONTROLS PROCEDURES & PROGRAMS TEXT 4.5 2
11/27/2023
Title:
ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS TEXT 4.6 0
09/27/2003
Title:
ADMINISTRATIVE CONTROLS RADIATION PROTECTION PROGRAM Page 8 of 15 Report Date: 12/03/25
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 4.7 1
12/13/2022
Title:
ADMINISTRATIVE CONTROLS TRAINING TEXT B3.0 8
12/03/2025
Title:
APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT B3.1.1 2
04/29/2014
Title:
REACTIVITY CONTROL SYSTEM BASES ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT B3.1.2 1
12/03/2025
Title:
REACTIVITY CONTROL SYSTEM BASES CONTROL ROD DRI VE (CRD) HOUSING SUPPORT TEXT B3.1.3 4
12/18/2017
Title:
REACTIVITY CONTROL SYSTEM BASES CONTROL ROD BLOCK INSTRUMENTATION TEXT B3.1.4 2
10/08/2025
Title:
REACTIVITY CONTROL SYSTEM BASES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT B3.2.1 0
11/19/2002
Title:
CORE OPERATING LIMITS BASES CORE OPERATING LIMITS REPORT (COLR)
TEXT B3.3.1 1
01/31/2014
Title:
INSTRUMENTATION BASES RADIATION MONI TORING INSTRUMENTATION TEXT B3.3.2 2
03/31/2011
Title:
INSTRUMENTATION BASES SEISMIC MONITORING INSTRUMENTATION TEXT B3.3.3 2
11/09/2007
Title:
INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION TEXT B3.3.4 8
11/27/2023
Title:
INSTRUMENTATION BASES TRM POST ACCIDENT MONITORING (PAM)
INSTRUMENTATION TEXT B3.3.5 2
11/09/2007
Title:
INSTRUMENTATION BASES THIS PAGE INTENTIONALLY LEFT BLANK Page 9 of 15 Report Date: 12/03/25
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.3.6 7
06/29/2023
Title:
INSTRUMENTATION BASES TRM ISOLATION ACTUATION INSTRUMENTATION TEXT B3.3.7 6
04/16/2024
Title:
INSTRUMENTATION BASES MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT B3.3.8 1
10/22/2003
Title:
INTENTIONALLY BLANK TEXT B3.3.9 5
12/03/2025
Title:
INSTRUMENTATION BASES LPRM UPSCALE ALARM INSTRUMENTATION TEXT B3.3.10 3
02/22/2012
Title:
INSTRUMENTATION BASES REACTOR RECIRCULATION PUMP MG SET STOPS TEXT B3.3.11 1
10/22/2003
Title:
INSTRUMENTATION BASES MVP ISOLATION INSTRUMENTATION TEXT B3.3.12 1
04/02/2019
Title:
WATER MONITORING INSTRUMENTATION TEXT B3.4.1 1
12/03/2025
Title:
REACTOR COOLANT SYSTEM BASES REACTOR COOLANT SYSTEM CHEMISTRY TEXT B3.4.2 1
04/16/2009
Title:
REACTOR COOLANT SYSTEM BASES STRUCTURAL INTEGRITY TEXT B3.4.3 1
11/09/2007
Title:
REACTOR COOLANT SYSTEM BASES HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITOR TEXT B3.4.4 1
01/03/2019
Title:
REACTOR COOLANT SYSTEM BASES REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT B3. 4.5 0
11/19/2002
Title:
REACTOR COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS Page 10 of 15 Report Date: 12/03/25
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.4.6 3
12/03/2025
Title:
REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION TEXT B3.5.1 2
03/17/2020
Title:
ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM ADS MANUAL INHIBIT TEXT B3.5.2 2
03/05/2019
Title:
ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM ECCS RPV WATER INVENTORY CONTROL AND RCIC MONITORING INSTRUMENTATION TEXT B3.5.3 3
12/03/2025
Title:
ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM LONG TERM NITROGEN SUPPLY TO ADS TEXT B3.6.1 1
11/27/2023
Title:
CONTAINMENT BASES VENTING OR PURGING TEXT B3.6.2 0
11/19/2002
Title:
CONTAINMENT BASES SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT B3.6.3 1
04/19/2007
Title:
CONTAINMENT BASES SUPPRESSION POOL ALARM INSTRUMENTATION TEXT B3.6.4 2
11/27/2023
Title:
CONTAINMENT BASES PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT B3.7.1 0
11/19/2002
Title:
PLANT SYSTEMS BASES EMERGENCY SERVICE WATER SYSTEM (SHUTDOWN)
TEXT B3.7.2 1
11/27/2023
Title:
PLANT SYSTEMS BASES ULTIMATE HEAT SINK (UHS) GROUND WATER LEVEL TEXT B3.7.3.1 4
02/16/2017
Title:
PLANT SYSTEMS BASES FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT B3.7.3.2 2
04/26/2006
Title:
PLANT SYSTEMS BASES SPRAY AND SPRINKLER SYSTEMS Page 11 of 15 Report Date: 12/03/25
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.7.3.3 0
11/19/2002
Title:
PLANT SYSTEMS BASES CO2 SYSTEMS TEXT B3.7.3.4 3
06/19/2019
Title:
PLANT SYSTEMS BASES HALON SYSTEMS TEXT B3.7.3.5 1
04/26/2006
Title:
PLANT SYSTEMS BASES FIRE HOSE STATIONS TEXT B3.7.3.6 1
04/26/2006
Title:
PLANT SYSTEMS BASES YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT B3.7.3.7 0
11/19/2002
Title:
PLANT SYSTEMS BASES FIRE RATED ASSEMBLIES TEXT B3.7.3.8 3
09/27/2012
Title:
PLANT SYSTEMS BASES FIRE DETECTION INSTRUMENTATION TEXT B3.7.4 1
11/27/2023
Title:
PLANT SYSTEMS BASES SOLID RADWASTE SYSTEM TEXT B3.7.5.1 0
11/19/2002
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT B3.7.5.2 0
11/19/2002
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE TEXT B3.7.5.3 0
11/19/2002
Title:
PLANT SYSTEMS BASES LIQUID HOLDUP TANKS TEXT B3.7.6 4
06/04/2013
Title:
PLANT SYSTEMS BASES ESSW PUMPHOUSE VENTILATION TEXT B3.7.7 2
01/31/2008
Title:
PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION Page 12 of 15 Report Date: 12/03/25
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.7.8 4
01/31/2014
Title:
PLANT SYSTEMS BASES SNUBBERS TEXT B3.7.9 4
12/03/2025
Title:
PLANT SYSTEMS BASES CONTROL STRUCTURE HVAC TEXT B3.7.10 1
12/14/2004
Title:
PLANT SYSTEMS BASES SPENT FUEL STORAGE POOLS TEXT B3.7.11 4
12/03/2025
Title:
STRUCTURAL INTEGRITY TEXT B3.8.1 3
12/03/2025
Title:
ELECTRICAL POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES TEXT B3.8.2.1 1
09/19/2023
Title:
ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV)
THERMAL OVERLOAD PROTECTION -
CONTINUOUS TEXT B3.8.2.2 2
06/23/2021
Title:
ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV)
THERMAL OVERLOAD PROTECTION -
AUTOMATIC TEXT B3.8.3 0
11/19/2002
Title:
ELECTRICAL POWER BASES DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT B3.8.4 1
11/27/2023
Title:
ELECTRICAL POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT B3.8.5 1
11/14/2013
Title:
ELECTRICAL POWER BASES DEGRADED VOLTAGE PROTECTION TEXT B3.8.6 4
03/05/2019
Title:
ELECTRICAL POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING TEXT B3.8.7 3
02/25/2021
Title:
BATTERY MAINTENANCE AND MONITORING PROGRAM Page 13 of 15 Report Date: 12/03/25
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3. 9.1 0
11/19/2002
Title:
REFUELING OPERATIONS BASES DECAY TIME TEXT B3.9.2 0
11/19/2002
Title:
REFUELING OPERATIONS BASES COMMUNICATIONS TEXT B3.9.3 1
03/12/2019
Title:
REFUELING OPERATIONS BASES REFUELING PLATFORM TEXT B3.10.1 1
11/27/2023
Title:
MISCELLANEOUS BASES SEALED SOURCE CONTAMINATION TEXT B3.10.2 1
04/10/2007
Title:
MISCELLANEOUS BASES SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT B3.10.3 4
04/02/2025
Title:
MISCELLANEOUS BASES INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TEXT B3. 11.1.1 2
11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS CONCENTRATION TEXT B3.11.1.2 1
11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS DOSE TEXT B3.11.1. 3 1
11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM TEXT B3.11.1.4 1
11/27/2 023
Title:
RADIOACTIVE EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT B3. 11.1.5 1
11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT B3.ll.2.1 3
10/15/2024
Title:
RADIOACTIVE EFFLUENTS BASES DOSE RATE Page 14 of 15 Report Date: 12/03/25
SSES MANUAL Manual Name:
TRM2 Manual
Title:
TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.ll.2.2 1
11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES DOSE -
NOBLE GASES TEXT B3.ll.2.3 1
11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES DOSE -
IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATES FORM TEXT B3.ll.2.4 1
11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM TEXT B3.11. 2. 5 6
11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES VENTILATION EXHAUST TREATMENT SYSTEM TEXT B3.ll.2.6 3
11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT B3. 11. 3 1
11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES TOTAL DOSE TEXT B3. 11. 4. 1 8
06/27/2024
Title:
RADIOACTIVE EFFLUENTS BASES MONITORING PROGRAM TEXT B3. 11. 4. 2 1
11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES LAND USE CENSUS TEXT B3.ll.4.3 1
11/27/2023
Title:
RADIOACTIVE EFFLUENTS BASES INTERLABORATORY COMPARISON PROGRAM TEXT B3.12.l 1
10/04/2007
Title:
LOADS CONTROL PROGRAM BASES CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT B3.12.2 1
12/03/2010
Title:
LOADS CONTROL PROGRAM BASES HEAVY LOADS REQUIREMENTS TEXT B3.12.3 0
11/19/2002
Title:
LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS Page 15 of 15 Report Date: 12/03/25
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 30 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION TITLE PAGE 1.0 USE AND APPLICATION............................................................................ 1.0-1 1.1 Definitions.............................................................................................. 1.0-1 2.0 PLANT PROGRAMS AND SETPOINTS...................................................... 2.0-1 2.1 Plant Programs...................................................................................... 2.0-1 2.2 Instrument Trip Setpoint Table............................................................... 2.0-5 3.0 APPLICABILITY........................................................................................... 3.0-1 3.0 Technical Requirement for Operation (TRO) Applicability...................... 3.0-1 3.0 Technical Requirement Surveillance (TRS) Applicability........................ 3.0-3 3.1 REACTIVITY CONTROL SYSTEMS............................................................ 3.1-1 3.1.1 Anticipated Transient Without Scram Alternate Rod Injection (ATWS-ARI) lnstrumentation.................................................................. 3.1-1 3.1.2 Control Rod Drive (CRD) Housing Support............................................ 3.1-4 3.1.3 Control Rod Block Instrumentation......................................................... 3.1-5 3.1.4 Control Rod Scram Accumulators Instrumentation and 3.2 3.2.1 3.3 3.3.1 3.3.2 3.3.3 3.3.4 3.3.5 3.3.6 3.3.7 3.3.8 3.3.9 3.3.10 3.3.11 3.3.12 Check Valve........................................................................................... 3.1-9 CORE OPERATING LIMITS REPORT........................................................ 3.2-1 Core Operating Limits Report................................................................. 3.2-1 INSTRUMENTATION.................................................................................. 3.3-1 Radiation Monitoring Instrumentation..................................................... 3.3-1 Seismic Monitoring Instrumentation........................................................ 3.3-4 Meteorological Monitoring Instrumentation............................................. 3.3-7 TRM Post-Accident Monitoring Instrumentation..................................... 3.3-9 Section Not Used................................................................................... 3.3-12 TRM Isolation Actuation Instrumentation................................................ 3.3-13 Main Turbine Overspeed Protection System.......................................... 3.3-1 7 Section Not Used................................................................................... 3.3-19 OPRM Instrumentation Configuration..................................................... 3.3-21 Reactor Recirculation Pump MG Set Stops............................................ 3.3-22 MVP Isolation lnstrumentation................................................................ 3.3-24 Water Monitoring Instrumentation.......................................................... 3.3-26 3.4 REACTOR COOLANT SYSTEM.................................................................. 3.4-1 3.4.1 Reactor Coolant System Chemistry........................................................ 3.4-1 3.4.2 Section Not Used................................................................................... 3.4-6 3.4.3 High/Low Pressure Interface Leakage Monitors..................................... 3.4-9 3.4.4 Reactor Recirculation Flow and Rod Line Limit...................................... 3.4-12 3.4.5 Reactor Vessel Materials...................................................................... 3.4-13 3.4.6 Section Not Used................................................................................... 3.4-14 SUSQUEHANNA - UNIT 2 TOC-1
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 30 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION TITLE PAGE 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM............... 3.5-1 3.5.1 ADS Manual Inhibit................................................................................ 3.5-1 3.5.2 ECCS, RPV Water Inventory Control, and RCIC System Monitoring Instrumentation..................................................................... 3.5-3 3.5.3 Long Term Nitrogen Supply to ADS....................................................... 3.5-6 3.6 CONTAINMENT........................................................................................... 3.6-1 3.6.1 Venting or Purging................................................................................. 3.6-1 3.6.2 Suppression Chamber-to-Drywell Vacuum Breaker Position lndication................................................................................................ 3.6-3 3.6.3 Suppression Pool Alarm Instrumentation............................................... 3.6-4 3.6.4 Primary Containment Closed System Boundaries.................................. 3.6-7 3.7 3.7.1 3.7.2 3.7.3 3.7.3.1 3.7.3.2 3.7.3.3 3.7.3.4 3.7.3.5 3.7.3.6 3.7.3.7 3.7.3.8 3.7.4 3.7.5 3.7.5.1 3.7.5.2 3.7.5.3 3.7.6 3.7.7 3.7.8 3.7.9 3.7.10 3.7.11 PLANT SYSTEMS....................................................................................... 3.7-1 Emergency Service Water System (ESW) Shutdown............................. 3.7-1 Ultimate Heat Sink (UHS) and Ground Water Level............................... 3.7-3 Fire Protection........................................................................................ 3.7-4 Fire Suppression Water Supply System................................................. 3.7-4 Spray and Sprinkler Systems................................................................. 3.7-8 CO2 systems......................................................................................... 3.7-12 Halon Systems....................................................................................... 3.7-16 Fire Hose Stations.................................................................................. 3.7-18 Yard Fire Hydrants and Hydrant Hose Houses....................................... 3.7-22 Fire Rated Assemblies........................................................................... 3.7-24 Fire Detection Instrumentation............................................................... 3.7-26 Solid Radwaste System......................................................................... 3.7-34 Explosive Gas and Storage Tank Radioactivity Monitoring Program................................................................................ 3. 7-37 Main Condenser Offgas Hydrogen Monitor............................................ 3.7-37 Main Condenser Offgas Explosive Gas Mixture..................................... 3.7-38 Liquid Holdup Tanks.............................................................................. 3.7-39 ESSW Pumphouse Ventilation............................................................... 3.7-40 Main Condenser Offgas Pretreatment Logarithmic Radiation Monitoring Instrumentation..................................................................... 3. 7-41 Snubbers................................................................................................ 3.7-43 Control Structure HVAC......................................................................... 3.7-49 Spent Fuel Storage Pools (SFSPs)........................................................ 3.7-51 Structural Integrity.................................................................................. 3.7-54 SUSQUEHANNA - UNIT 2 TOC-2
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 30 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION TITLE PAGE 3.8 ELECTRICAL POWER................................................................................ 3.8-1 3.8.1 Primary Containment Penetration Conductor Overcurrent Protective Devices................................................................................. 3.8-1 3.8.2 Motor Operated Valves Thermal Overload Protection............................ 3.8.5 3.8.2.1 Motor Operated Valves (MOV) Thermal Overload Protection -
Continuous............................................................................................. 3.8-5 3.8.2.2 Motor Operated Valves (MOV) Thermal Overload Protection -
Automatic............................................................................................... 3.8-11 3.8.3 Diesel Generator (DG) Maintenance Activities....................................... 3.8-13 3.8.4 24 VDC Electrical Power Subsystem...................................................... 3.8-15 3.8.5 Degraded Voltage Protection................................................................. 3.8-21 3.8.6 Emergency Switchgear Room Cooling................................................... 3.8-24 3.8.7 Battery Monitoring and Maintenance Program....................................... 3.8-26 3.9 REFUELING OPERATIONS........................................................................ 3.9-1 3.9.1 Decay Time............................................................................................ 3.9-1 3.9.2 Communications.................................................................................... 3.9-2 3.9.3 Refueling Platform.................................................................................. 3.9-3 3.10 MISCELLANEOUS...................................................................................... 3.10-1 3.10.1 Sealed Source Contamination................................................................ 3.10-1 3.10.2 3.10.3 Shutdown Margin Test RPS Instrumentation.......................................... 3.10-4 Independent Spent Fuel Storage Installation (ISFSI).............................. 3.10-7 3.10.4 Section Not Used................................................................................... 3.10-8 3.11 RADIOACTIVE EFFLUENTS....................................................................... 3.11-1 3.11.1 Liquid Effluents...................................................................................... 3.11-1 3.11.1.1 Liquid Effluents Concentration................................................................ 3.11-1 3.11.1.2 Liquid Effluents Dose............................................................................. 3.11-4 3.11.1.3 Liquid Radwaste Treatment System....................................................... 3.11-6 3.11.1.4 Liquid Radwaste Effluent Monitoring Instrumentation............................. 3.11-8 3.11.1.5 Radioactive Liquid Process Monitoring Instrumentation......................... 3.11-13 3.11.2 Gaseous Effluents.................................................................................. 3.11-17 3.11.2.1 Dose Rate.............................................................................................. 3.11-17 3.11.2.2 Dose - Noble Gases............................................................................... 3.11-20 3.11.2.3 Dose - Iodine, Tritium, and Radionuclides in Particulate Form............... 3.11-21 3.11.2.4 Gaseous Radwaste Treatment System.................................................. 3.11-22 3.11.2.5 Ventilation Exhaust Treatment System................................................... 3.11-23 3.11.2.6 Radioactive Gaseous Effluent Monitoring Instrumentation..................... 3.11-25 3.11.3 Total Dose.............................................................................................. 3.11-33 3.11.4 Radiological Environmental Monitoring.................................................. 3.11-35 3.11.4.1 Monitoring Program................................................................................ 3.11-35 3.11.4.2 Land Use Census................................................................................... 3.11 -45 3.11.4.3 lnterlaboratory Comparison Program..................................................... 3.11-47 SUSQUEHANNA - UNIT 2 TOC-3
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 30 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION 3.12 3.12.1 3.12.2 3.12.3 4.0 4.1 4.2 4.3 4.4 4.5 4.5.1 4.5.2 4.5.3 4.6 4.7 TITLE PAGE LOADS CONTROL PROGRAM................................................................... 3.12-1 Crane Travel - Spent Fuel Storage Pool................................................. 3.12-1 Heavy Loads Requirements................................................................... 3.1 2.3 Light Loads Requirements..................................................................... 3.1 2-5 ADMINISTRATIVE CONTROLS..................................................................4.0-1 Organization........................................................................................... 4.0-1 Reportable Event Action.........................................................................4.0-2 Safety Limit Violation..............................................................................4.0-3 Procedures and Programs.....................................................................4.0-4 Reporting Requirements........................................................................4.0-5 Startup Reports...................................................................................... 4.0-5 Annual Reports...................................................................................... 4.0-6 Section Not Used...................................................................................4.0-6 Radiation Protection Program................................................................4.0-7 Section Not Used...................................................................................4.0-8 SUSQUEHANNA - UNIT 2 TOC-4
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 30 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION TITLE B 3.0 Technical Requirement for Operation (TRO) Applicability...................... B 3.0-1 B 3.0 Technical Requirement Surveillance (TRS) Applicability........................ B 3.0-9 B 3.1.1 Anticipated Transient Without Scram Alternate Rod Injection (ATWS-ARI) lnstrumentation.................................................................. B 3.1-1 B 3.1.2 Control Rod Drive (CRD) Housing Support............................................ B 3.1-4 B 3.1.3 Control Rod Block Instrumentation......................................................... 8 3.1-5 B 3.1.4 Control Rod Scram Accumulators Instrumentation and Check Valve........................................................................................... 8 3.1-8 B 3.2.1 Core Operating Limits Report (COLR).................................................... 8 3.2-1 B 3.3.1 Radiation Monitoring Instrumentation..................................................... 8 3.3-1 B 3.3.2 Seismic Monitoring lnstrumentation........................................................ 8 3.3-2 B 3.3.3 Meteorological Monitoring Instrumentation............................................. 8 3.3-3 B 3.3.4 TRM Post-Accident Monitoring Instrumentation..................................... 8 3.3-4 B 3.3.5 Section Not Used................................................................................... 8 3.3-9 B 3.3.6 TRM Isolation Actuation Instrumentation................................................ 8 3.3-10 B 3.3.7 Turbine Overspeed Protection System................................................... B 3.3-14 B 3.3.8 Section Not Used................................................................................... 8 3.3-15 B 3.3.9 OPRM lnstrumentation........................................................................... 8 3.3-18 B 3.3.10 B 3.3.11 Reactor Recirculation Pump MG Set Stops............................................ 8 3.3-20 MVP Isolation lnstrumentation................................................................ 8 3.3-22 B 3.3.12 Water Monitoring Instrumentation.......................................................... 8 3.3-24 B 3.4.1 Reactor Coolant System Chemistry........................................................ 8 3.4-1 B 3.4.2 Section Not Used................................................................................... 8 3.4-2 B 3.4.3 High/Low Pressure Interface Leakage Monitor....................................... 8 3.4-4 B 3.4.4 Reactor Recirculation Flow and Rod Line Limit...................................... 8 3.4-5 B 3.4.5 Reactor Vessel Materials....................................................................... 8 3.4-6 B 3.4.6 Section Not Used................................................................................... 8 3.4-7 B 3.5.1 ADS Manual Inhibit................................................................................ 8 3.5-1 B 3.5.2 ECCS, RPV Water Inventory Control, and RCIC System Monitoring Instrumentation..................................................................... 8 3.5-3 B 3.5.3 Long Term Nitrogen Supply to ADS....................................................... 8 3.5-4 B 3.6.1 Venting or Purging................................................................................. 8 3.6-1 B 3.6.2 Suppression Chamber-to-Drywell Vacuum Breaker Position lndication................................................................................................ 8 3.6-3 B 3.6.3 Suppression Pool Alarm Instrumentation............................................... 8 3.6-4 B 3.6.4 Primary Containment Closed System Boundaries.................................. 8 3.6-6 SUSQUEHANNA - UNIT 2 TOC-5
SUSQUEHANNA STEAM ELECTRIC STATION Rev.30 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION PAGE B 3.7.1 Emergency Service Water System (Shutdown)...................................... 8 3.7-1 B 3.7.2 Ultimate Heat Sink (UHS) Ground Water Level...................................... 8 3.7-2 B 3.7.3.1 Fire Suppression Water Supply System................................................. 8 3.7-3 B 3.7.3.2 Spray and Sprinkler Systems................................................................. 8 3.7-5 B 3.7.3.3 CO2 Systems......................................................................................... B 3.7-7 B 3.7.3.4 Halon Systems....................................................................................... 8 3.7-8 B 3.7.3.5 Fire Hose Stations.................................................................................. B 3.7-10 B 3.7.3.6 Yard Fire Hydrants and Hydrant Hose Houses....................................... 8 3.7-11 B 3.7.3.7 Fire Rated Assemblies........................................................................... 8 3.7-12 B 3.7.3.8 Fire Detection Instrumentation............................................................... 8 3.7-14 B 3.7.4 Solid Radwaste System......................................................................... 8 3.7-1 5 B 3.7.5.1 Main Condenser Offgas Hydrogen Monitor............................................ 8 3.7-17 B 3.7.5.2 Main Condenser Offgas Explosive Gas Mixture..................................... 8 3.7-19 B 3.7.5.3 Liquid Holdup Tanks.............................................................................. 8 3.7-20 B 3.7.6 ESSW Pumphouse Ventilation............................................................... 8 3.7-21 B 3.7.7 Main Condenser Offgas Pretreatment Logarithmic Radiation Monitoring Instrumentation..................................................................... 8 3.7-22 B 3.7.8 Snubbers................................................................................................ 8 3.7-24 B 3.7.9 Control Structure HVAC......................................................................... 8 3.7-31 B3.7.10 Spent Fuel Storage Pools...................................................................... 8 3.7-33 B 3.7.11 B 3.8.1 Structural Integrity.................................................................................. 8 3.7-36 Primary Containment Penetration Conductor Overcurrent Protective Devices................................................................................. 8 3.8-1 B 3.8.2.1 Motor Operated Valves (MOV) Thermal Overload Protection -
Continuous............................................................................................. B 3.8-3 B 3.8.2.2 Motor Operated Valves (MOV) Thermal Overload Protection -
Automatic............................................................................................... B 3.8-4 8 3.8.3 Diesel Generator (DG) Maintenance Activities....................................... 8 3.8-5 B 3.8.4 24 VDC Electrical Power Subsystem...................................................... B 3.8-6 B 3.8.5 Degraded Voltage Protection................................................................. 8 3.8-16 8 3.8.6 Emergency Switchgear Room Cooling................................................... 8 3.8-17 B 3.8.7 Battery Monitoring and Maintenance Program....................................... 8 3.8-18 8.3.9.1 Decay Time............................................................................................ B 3.9-1 8 3.9.2 Communications.................................................................................... 8 3.9-2 B 3.9.3 Refueling Platform.................................................................................. B 3.9-3 8 3.10.1 Sealed Source Contamination................................................................ 8 3.10-1 B 3.10.2 Shutdown Margin Test RPS Instrumentation.......................................... B 3.1 0-2 83.10.3 Independent Spent Fuel Storage Installation (ISFSl).............................. 8 3.10-4 SUSQUEHANNA-UNIT 2 TOC-6
SUSQUEHANNA STEAM ELECTRIC STATION Rev. 30 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)
SECTION 8 3.11.1.1 8 3.11.1.2 8 3.11.1.3 8 3.11.1.4 8 3.11.1.5 8 3.11.2.1 8 3.11.2.2 83.11.2.3 8 3.11.2.4 8 3.11.2.5 8 3.11.2.6 8 3.11.3 8 3.11.4.1 8 3.11.4.2 8 3.11.4.3 8.3.12.1 8.3.12.2 8.3.12.3 TITLE PAGE Liquid Effluents Concentration................................................................ 8 3.11-1 Liquid Effluents Dose............................................................................. 8 3.11-4 Liquid Radwaste Treatment System....................................................... 8 3.11-6 Liquid Radwaste Effluent Monitoring Instrumentation............................. 8 3.11-7 Radioactive Liquid Process Monitoring Instrumentation......................... 8 3.11-1 O Dose Rate.............................................................................................. 8 3.11-12 Dose - Noble Gases............................................................................... 8 3.11-16 Dose - Iodine, Tritium, and Radionuclides in Particulates Form................................................................................... 8 3.11-18 Gaseous Radwaste Treatment System.................................................. 8 3.11 -20 Ventilation Exhaust Treatment System................................................... 8 3.11-21 Radioactive Gaseous Effluent Monitoring Instrumentation..................... 8 3.11-24 Total Dose.............................................................................................. 8 3.11-26 Monitoring Program................................................................................ 8 3.11-28 Land Use Census................................................................................... 8 3.11 -34 lnterlaboratory Comparison Program..................................................... 8 3.11 -36 Crane Travel - Spent Fuel Storage Pool................................................ 8 3.12-1 Heavy Loads Requirements................................................................... 8 3.12-2 Light Loads Requirements..................................................................... 8 3.12-3 SUSQUEHANNA - UNIT 2 TOC-7
Rev. 2 1.0 USE AND APPLICATION 1.1 Definitions Definitions 1.1
NOTE ----------------------------------------------------------
The defined terms of this section appear in capitalized type and are applicable throughout these Technical Requirements and Bases.
Term ACTIONS CHANNEL CALIBRATION CHANNEL CHECK CHANNEL FUNCTIONAL TEST SUSQUEHANNA - UNIT 2 Definition ACTIONS shall be that part of a Technical Requirement that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.
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 in place 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.
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.
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 FUNCTIONALITY, 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.
TRM / 1.0-1
Rev. 2 1.1 Definitions (continued)
CORE ALTERATION FUNCTIONAL -
FUNCTIONALITY GASEOUS RADWASTE TREATMENT SYSTEM MEMBER(S) OF THE PUBLIC MODE SUSQUEHANNA - UNIT 2 Definitions 1.1 CORE AL TERA Tl ON 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 to be 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 AL TERA TIONS shall not preclude completion of movement of a component to a safe position.
A system, structure, or component (SSC) is FUNCTIONAL or has FUNCTIONALITY when it is capable of performing its function(s) as described in the design and licensing basis.
FUNCTIONALITY includes the ability of required support systems to perform their related support function(s) for equipment required to be OPERABLE by the Technical Specifications.
A GASEOUS RADWASTE TREATMENT SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.
MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.
A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 of the Technical Specifications with fuel in the reactor vessel.
TRM / 1.0-2
Rev.2 1.1 Definitions (continued)
PROCESS CONTROL PROGRAM PURGE - PURGING OPERABLE - OPERABILITY SITE BOUNDARY SOLIDIFICATION SOURCE CHECK THERMAL POWER UNRESTRICTED AREA SUSQUEHANNA - UNIT 2 Definitions 1.1 The PROCESS CONTROL PROGRAM (PCP) shall contain the sampling, analysis, and formulation determination by which SOLIDIFICATION of radioactive wastes from liquid systems is assured.
PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.
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).
The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee. See FSAR Section 2.1.1.2.
SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).
A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.
THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the site boundary used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes. See FSAR Section 2.1.1.3.
TRM / 1.0-3
Rev.2 1.1 Definitions (continued)
VENTILATION EXHAUST TREATMENT SYSTEM VENTING SUSQUEHANNA-UNIT 2 Definitions 1.1 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.
VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during venting. Vent, used in system names, does not imply a VENTING process.
TRM / 1.0-4
Rev. 9 TRO Applicability 3.0 3.0 TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TRO 3.0.1 TRO 3.0.2 TRO 3.0.3 TRO 3.0.4 TRO 3.0.5 TRO 3.0.6 TROs shall be met during the MODES or other specified conditions in the Applicability, except as provided in TRO 3.0.2.
Upon discovery of a failure to meet a TRO, the ACTIONS shall be met within the Completion Times, with the exceptions specified below:
- a. If the TRO is met or is no longer applicable prior to expiration of the specified Completion Time(s), completion of the ACTION(S) is not required, unless otherwise stated.
- b. Administrative controls may be employed in lieu of the specified ACTIONS if necessary to perform testing to verify the FUNCTIONALITY of equipment.
When a TRO is not met and the associated ACTIONS are not met, an associated ACTION is not provided, or if directed by the associated ACTIONS, initiate a Condition Report in accordance with the Corrective Action Program.
Not Used. Refer to TRO 3.0.2.
Not Used. Refer to TRO 3.0.2.
Not Used. Refer to TRO 3.0.2.
SUSQUEHANNA - UNIT 2 TRM / 3.0-1
Rev. 9 TRO Applicability 3.0 3.0 TECHNICAL REQUIREMENT SURVEILLANCE (TRS) APPLICABILITY TRS 3.0.1 TRS 3.0.2 TRS 3.0.3 TRS 3.0.4 TRS shall be met during the MODES or other specified conditions in the Applicability for individual TROs, unless otherwise stated. Failure to meet a TRS, whether such failure is experienced during the performance of the TRS or between performances of the TRS, shall be failure to meet the TRO. TRSs do not have to be performed on nonfunctional equipment or variables outside specified limits.
The specified Frequency for each TRS is met if the TRS 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.
Should a TRS not be performed within the specified Frequency, a Condition Report shall be initiated to determine if the associated TRO is met. The TRS shall be performed at the next reasonable opportunity.
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 Requirement are stated in the individual Requirements.
Not Used. Refer to TRS 3.0.2.
Not Used. Refer to TRS 3.0.2.
SUSQUEHANNA - UNIT 2 TRM / 3.0-2
Rev. 1 3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 Control Rod Drive (CRD) Housing Support TRO 3.1.2 The CRD housing support shall be in place.
APPLICABILITY:
MODES 1, 2 and 3.
ACTIONS CONDITION A.
CRD housing support not in place.
REQUIRED ACTION A. 1 Enter TRO 3.0.3.
TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE TRS 3.1.2.1 Verify the CRD housing support to be in place.
SUSQUEHANNA - UNIT 2 TRM / 3.1-4 CRD Housing Support 3.1.2 COMPLETION TIME Immediately FREQUENCY Prior to entering MODES 2 or3 from MODES 4 or 5 any time it has been disassembled or when maintenance has been performed in the CRD housing support area
Rev. 4 3.3 INSTRUMENTATION 3.3.9 OPRM Instrumentation Configuration OPRM Instrumentation 3.3.9 TRO 3.3.9 Oscillation Power Range Monitor (OPRM) supporting setpoints and settings shall be within the specified limits.
APPLICABILITY:
Thermal POWER ?:23% RTP.
ACTIONS
NO TE ----------------------------------------------------------
Se pa rate Condition entry is allowed for each channel.
CONDITION REQUIRED ACTION COMPLETION TIME A.
OPRM Setpoints and A.1 Enter the condition Immediately Settings not in referenced in accordance with Table 3.3.9-1 for the Table 3.3.9-1.
parameter.
- 8. As required by Required 8.1 Declare affected OPRM Immediately Action A.1 and channel inoperable.
referenced in Table 3.3.9.1.
C. As required by Required C.1 Restore the OPRM 120 days Action A.1 and Setpoints and Settings to referenced in within the specified limits.
Table 3.3.9-1.
OR C.2 Declare affected OPRM Immediately channel inoperable.
SUSQUEHANNA - UNIT 2 TRM / 3.3-21
Rev.4 ACTIONS (continued)
CONDITION D.
Alternate method to detect and suppress thermal hydraulic instability oscillations required by LCO 3.3.1.1 Required Action 1.1.
E.
NOTE -----------
Only applicable as required by Required Action D.1.
Total core flow as a function of THERMAL POWER within Region I of the Power Flow map as specified in the COLR.
OR Total core flow as a function of THERMAL POWER within Region II of the Power Flow map as specified in the COLR and less than 50% of required LPRM upscale alarms FUNCTIONAL.
SUSQUEHANNA - UNIT 2 REQUIRED ACTION D.1 Initiate monitoring to detect entry into Conditions E, F, and/or G.
E.1 Place reactor mode switch in the shutdown position.
TRM / 3.3-21a OPRM Instrumentation 3.3.9 COMPLETION TIME Immediately Immediately
Rev. 4 ACTIONS (continued)
CONDITION F.
NOTE -----------
Only applicable as required by Required Action D.1 and when in Region II of the Power Flow map as specified in the COLR.
Two or more APRM readings oscillating with one or more oscillating
~10% of RTP peak-to-peak.
OR Two or more LPRM upscale alarms activating and deactivating with a period ~1 second and
- 5 seconds.
OR Sustained LPRM oscillations > 1 O W/cm2 peak-to-peak with a period ~1 second and
- 5 seconds.
G. ----------- NOTE -----------
Only applicable as required by Required Action D.1.
Total core flow as a function of THERMAL POWER is within Region 11 of the Power Flow map as specified in the COLR.
SUSQUEHANNA - UNIT 2 REQUIRED ACTION F.1 Place the reactor mode switch in the shutdown position.
G.1 Initiate action to restore total core flow as a function of THERMAL POWER outside of Region II.
TRM / 3.3-21b OPRM Instrumentation 3.3.9 COMPLETION TIME Immediately Immediately
Rev. 4 ACTIONS (continued)
CONDITION REQUIRED ACTION OPRM Instrumentation 3.3.9 COMPLETION TIME H.
Less than 50% of the H.1 Post sign on the reactor 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> required LPRM Upscale Alarms are control panel that less than 50% of the LPRM Upscale FUNCTIONAL.
Alarms are FUNCTIONAL.
TECHNICAL REQUIREMENT SURVEILLANCE TRS 3.3.9.1 TRS 3.3.9.2 TRS 3.3.9.3 SURVEILLANCE
NOTE ------------------------------
0 n ly required to be met when an alternate method to detect and suppress thermal hydraulic instability oscillations is required by LCO 3.3.1.1 Required Action 1.1.
Verify total core flow as a function of THERMAL POWER is outside of Region I and II of the Power Flow map as specified in the COLR.
Perform CHANNEL CALIBRATION on the LPRM Upscale alarm.
Verify OPRM parameter setpoints and settings are within limits.
SUSQUEHANNA - UNIT 2 TRM / 3.3-21 c FREQUENCY 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 24 months 24 months
Rev. 4 TABLE 3.3.9-1 OPRM Instrumentation 3.3.9 OPRM SETPOINTS AND SETTINGS CONDITIONS REFERENCED FROM OPRM REQUIRED PARAMETER DESCRIPTION ACTION A.1 VALUE
- 1. TOL(E)
Period Tolerance B
- 0.10 and
- 0.30 sec
- 2. fc Conditioning Filter Cutoff Frequency B
1.5 Hz
- 3. Tmin Oscillation Period Lower Time Limit B
- 1.0 and
- 1.2 sec
- 4. Tmax Oscillation Period Upper Time Limit B
3.5 sec
- 5. LPRMmin Minimum LRPMs/Cell Required for Cell B
- 2 Operability
- 6. S1 Peak Threshold Setpoint/ABA & GRBA C
- 1.10 and
- 1.20
- 7. S2 Valley Threshold Setpoint/ABA & GRBA C
- 0.85 and
- 0.95
- 8. Smax Amplitude Trip Setpoint/ABA C
- 1.30 and
- 1.50
- 9. DR3 Growth Rate Factor Setpoint/GRBA C
- 1.30 and
- 1.60 SUSQUEHANNA - UNIT 2 TRM / 3.3-21 d
Rev. 2 REACTOR COOLANT SYSTEM Reactor Coolant System Chemistry 3.4.1 3.4 3.4.1 Reactor Coolant System Chemistry TRO 3.4.1 The chemistry of the reactor coolant system shall be maintained within the limits specified in Table 3.4.1-1 and the conductivity recorder shall be FUNCTIONAL.
APPLICABILITY:
At all times.
ACTIONS
NO TE ----------------------------------------------------
The provisions of TRO 3.0.4 are not applicable.
CONDITION REQUIRED ACTION COMPLETION TIME A.
Conductivity not within A.1 Perform TRS 3.4.1.1 and Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> the limits specified in TRS 3.4.1.3.
Table 3.4.1-1.
AND A.2 Perform TRS 3.4.1.4.
Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> B.
In MODE 1, Conductivity B.1 Restore parameter(s) 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or Chlorides not within within limits.
limits specified in AND Table 3.4.1-1 but within Transient Limits.
~ 336 hour0.00389 days <br />0.0933 hours <br />5.555556e-4 weeks <br />1.27848e-4 months <br />s/year cumulative time exceeding the limit SUSQUEHANNA UNIT 2 TRM / 3.4-1
Rev. 2 ACTIONS (continued)
CONDITION C.
In MODE 1, pH not within limits of Table 3.4.1-1 but within Transient Limits.
OR In MODES other than 1, 2 or 3, one or more chemistry parameter in excess of Table 3.4.1-1 but within Transient Limits.
D.
In MODE 2 or 3, one or more chemistry parameter in excess of Table 3.4.1-1 but within Transient Limits.
E.
Required Action and associated Completion Time not met.
OR One or more chemistry parameter in excess of Transient Limit.
NOTE--------------
Applicable only in MODE 4 or MODE 5.
F.
Chloride concentration greater than 0.5 ppm for >24 hours.
SUSQUEHANNA UNIT 2 C.1 D.1 E.1 F.1 Reactor Coolant System Chemistry 3.4.1 REQUIRED ACTION COMPLETION TIME Restore parameter within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> limits.
Restore parameter within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> limits.
Enter TRO 3.0.3.
Immediately Perform Engineering Prior to proceeding to Evaluation of structural MODE 2 or MODE 3 integrity.
TRM / 3.4-2
Rev. 2 ACTIONS (continued)
CONDITION G. Conductivity recorder nonfunctional.
SUSQUEHANNA UNIT 2 G.1 Reactor Coolant System Chemistry 3.4.1 REQUIRED ACTION Obtain in-line conductivity measurement or grab sample.
TRM / 3.4-3 COMPLETION TIME
NOTE ----------
Applicable in MODES 1, 2, or 3 Once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> AND
NOTE ----------
Applicable in other than MODES 1, 2, or 3 Once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
Rev. 2 Reactor Coolant System Chemistry 3.4.1 TECHNICAL REQUIREMENT SURVEILLANCE TRS 3.4.1.1 TRS 3.4.1.2 TRS 3.4.1.3 TRS 3.4.1.4 SURVEILLANCE Analyze a sample of reactor coolant for chlorides.
Analyze a sample of reactor coolant for conductivity.
Analyze a sample of reactor coolant for pH.
Perform CHANNEL CHECK of the continuous conductivity monitor.
SUSQUEHANNA UNIT 2 TRM / 3.4-4 FREQUENCY 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 72 hours
NOTE -------
Only required to be performed if reactor conductivity is greater than 1.0
µmho/cm at 25°C 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 7 days
Rev. 2 TABLE 3.4.1-1 Reactor Coolant System Chemistry 3.4.1 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS Conductivity Chloride Concentration MODE
µmho/cm @ 25°C ppm pH 1
~ 1.0
~ 0.2 5.6 ~ pH ~ 8.6 2 and 3
~ 2.0
~ 0.1 5.6 ~ pH ~ 8.6 At all times other
~ 10.0
~ 0.5 5.3 ~ pH ~ 8.6 than MODE 1, 2, or 3 Transient Limit 1, 2, and 3
~ 10.0
~ 0.5 5.3 ~ pH ~ 8.6 SUSQUEHANNA UNIT 2 TRM / 3.4-5
Rev. 2 THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA UNIT 2 TRM / 3.4-14 Not Used 3.4.6
Rev. 2 Long Term Nitrogen Supply to ADS 3.5.3 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL, AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.3 Long Term Nitrogen Supply to Automatic Depressurization System (ADS)
TRO 3.5.3 The Long Term Nitrogen Supply to ADS System shall be FUNCTIONAL.
APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One bank of the backup A. 1 Restore the bottle bank 14 days nitrogen bottle supply is and associated header to isolated or the long term FUNCTIONAL status.
nitrogen supply is otherwise nonfunctional.
B.
Both banks of backup 8.1 Restore at least one 3 days nitrogen bottle supply bottle bank or associated are isolated or both header to FUNCTIONAL headers otherwise status.
nonfunctional.
C. Required Action and C.1 Enter TRO 3.0.3.
Immediately associated Completion Time of Conditions A or B not met.
SUSQUEHANNA - UNIT 2 TRM / 3.5-6
Rev.2 Long Term Nitrogen Supply to ADS 3.5.3 TECHNICAL REQUIREMENT SURVEILLANCE TRS 3.5.3. 1 TRS 3.5.3.2 TRS 3.5.3.3 TRS 3.5.3.4 SURVEILLANCE FREQUENCY Verify Long Term Nitrogen Supply System header 31 days pressure is ~ 135 psig.
Verify each Long Term Nitrogen Supply System 31 days manual and power operated valve in the flow path, that is not locked, sealed, or otherwise secured in position, are in the correct position.
Perform a functional test of the swap over to the Long 24 months Term Nitrogen Supply System.
Demonstrate Long Term Nitrogen Supply ability to 24 months maintain at least 135 psig for a minimum of 3 days.
SUSQUEHANNA - UNIT 2 TRM / 3.5-7
Rev.3 3.7 PLANT SYSTEMS 3.7.9 Control Structure HVAC Control Structure HVAC 3.7.9 TRO 3.7.9 The following Control Structure HVAC Subsystems shall be FUNCTIONAL:
- a. Battery Room Exhaust System,
- b. Standby Gas Treatment (SGT) Equipment Room Ventilation System (Heating),
- c. SGT Equipment Room Ventilation System (Cooling).
APPLICABILITY:
MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, and During CORE ALTERATIONS.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
A single division of A.1 Restore all affected 30 days subsystems a-b subsystems to nonfunctional for its FUNCTIONAL status.
cooling or heating mode.
B.
A single division of B.1 Restore the affected 30 days subsystem c cooling unit to nonfunctional.
FUNCTIONAL status.
C.
Both divisions of any C.1 Evaluate OPERABILITY/
Immediately subsystem nonfunctional FUNCTIONALITY of for the cooling or heating supported systems.
mode.
AND C.2 Declare supported Immediately systems inoperable/
nonfunctional, if applicable.
SUSQUEHANNA - UNIT 2 TRM / 3.7-49
Rev.3 ACTIONS (continued)
CONDITION REQUIRED ACTION D.
Required Action and D.1 Enter TRO 3.0.3.
associated Completion Time of Condition A, or B not met.
TECHNICAL REQUIREMENT SURVEILLANCE TRS 3.7.9.1 SURVEILLANCE Administratively verify that the Control Structure HVAC Subsystems are available.
SUSQUEHANNA - UNIT 2 TRM / 3.7-50 Control Structure HVAC 3.7.9 COMPLETION TIME Immediately FREQUENCY 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
Rev. 3
- 3. 7 PLANT SYSTEMS 3.7.11 Structural Integrity Structural Integrity 3.7.11 TRO 3.7.11 ASME Code Class 1, 2, and 3 pressure retaining components and structural support components shall maintain structural integrity.
APPLICABILITY:
MODES 1, 2, 3, 4, and 5.
ACTIONS
NOTE -------------------------------------------------------
Separate condition entry is allowed for each pressure retaining component and structural support component.
CONDITION REQUIRED ACTION COMPLETION TIME A.
NOTE-------------
A.1 Evaluate the impact of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Required Action A.1 the indication or failed shall be completed if this inspection on Condition is entered.
OPERABILITY/
FUNCTIONALITY and Unevaluated indication structural integrity of or failed inspection is associated systems, found in ASME Code structures, or components.
Class 1, 2, or 3 pressure retaining component(s) or structural support component(s) required to be OPERABLE /
FUNCTIONAL.
B.
Required Action and B.1 Declare the associated Immediately associated Completion systems, structures or Time of Condition A not components inoperable /
met.
nonfunctional.
SUSQUEHANNA UNIT 2 3.7-54
Rev. 3 ACTIONS (continued)
CONDITION C. Structural integrity not C.1 maintained (including through-wall flaws) for any ASME Code Class 1 AND pressure retaining component(s) required C.2 to be OPERABLE /
FUNCTIONAL.
D. Structural integrity not D.1 maintained (including through-wall flaws) for any ASME Code Class 2 or Class 3 pressure retaining component(s)
AND required to be OPERABLE/
D.2 FUNCTIONAL.
AND D.3 SUSQUEHANNA UNIT 2 REQUIRED ACTION Initiate actions to isolate the affected component(s).
Declare the affected component(s) and associated systems, structures or components inoperable / nonfunctional.
Perform an immediate determination of OPERABILITY/
FUNCTIONALITY.
If Required Action D.1 determined the deficient condition could have a functional impact, perform a prompt operability determination.
If determined to be inoperable / nonfunctional by Required Action D.2, declare the affected component(s) and associated systems, structures or components inoperable/ nonfunctional.
3.7-55 Structural Integrity 3.7.11 COMPLETION TIME Immediately Immediately Immediately 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Immediately
Rev.3 ACTIONS (continued)
CONDITION E. Structural integrity not maintained for any ASME Code Class 1, 2, or 3 structural support component(s) required to be OPERABLE /
FUNCTIONAL.
SUSQUEHANNA UNIT 2 E.1 AND E.2 AND E.3 REQUIRED ACTION Perform an immediate determination of OPERABILITY/
FUNCTIONALITY.
If Required Action E.1 determined the deficient condition could have a functional impact, perform a prompt operability determination.
If determined to be inoperable / nonfunctional by Required Action E.2, declare the affected component(s) and associated systems, structures or components inoperable / nonfunctional, if applicable.
3.7-56 Structural Integrity 3.7.11 COMPLETION TIME Immediately 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Immediately
Rev. 3 ACTIONS (continued)
CONDITION F.
NOTE-------------
F.1 Applicable only if, at the time of discovery, the component(s) is not AND required to be OPERABLE/
F.2.1 FUNCTIONAL.
Unevaluated indication or failed inspection is found in ASME Code F.2.2 Class 1, 2, or 3 pressure retaining component(s) or structural support component(s).
Structural integrity not maintained for any ASME Code Class 1, 2, or 3 pressure retaining component(s) or structural support component(s).
REQUIRED ACTION Generate a Condition Report.
Complete repair/
replacement activity.
OR Perform a prompt operability determination.
TECHNICAL REQUIREMENT SURVEILLANCE TRS 3.7.11.1 SURVEILLANCE Perform inservice inspection of ASME Section XI Code Class 1, 2, and 3 Components.
SUSQUEHANNA UNIT 2 3.7-57 Structural Integrity 3.7.11 COMPLETION TIME Immediately Prior to entering the mode of applicability Prior to entering the mode of applicability FREQUENCY In accordance with lnservice Inspection Program
Rev. 5 Primary Containment Penetration Conductor Overcurrent Protective Devices 3.8.1 3.8 ELECTRICAL POWER 3.8.1 Primary Containment Penetration Conductor Overcurrent Protective Devices TRO 3.8.1 The primary containment penetration conductor overcurrent protective devices in Table 3.8.1-1 shall be FUNCTIONAL.
Applicability:
MODES 1, 2 and 3.
ACTIONS
NO TE ----------------------------------------------------------
Separate condition entry is allowed for each device.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more A.1 Deenergize the circuit(s) 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> containment penetration and declare the affected conductor overcurrent system or component protective devices inoperable or nonfunctional.
nonfunctional, as applicable.
AND A.2 Verify affected circuit Once per 7 days deenergized.
B.
Required Action and B.1 Enter TRO 3.0.3.
Immediately associated Completion Time for Condition A not met.
SUSQUEHANNA - UNIT 2 TRM / 3.8-1
Rev. 5 Primary Containment Penetration Conductor Overcurrent Protective Devices 3.8.1 TECHNICAL REQUIREMENT SURVEILLANCE TRS 3.8.1.1 TRS 3.8.1.2 TRS 3.8.1.3 SURVEILLANCE
NOTE -------------------------------
For each circuit breaker found nonfunctional, an additional representative sample of :::::10% of all the circuit breakers of the same type shall be functionally tested until no more failures are found or all circuit breakers of that type have been functionally tested.
Perform a functional test on a representative sample of ::::: 10% of each type of lower voltage circuit breaker.
Perform a functional test on each overcurrent relay.
NOTE -------------------------------
The provisions of TRS 3.0.2 are not applicable.
Subject each circuit breaker to inspection and preventive maintenance.
SUSQUEHANNA - UNIT 2 TRM / 3.8-2 FREQUENCY 24 months 24 months 120 months
Primary Containment Penetration Conductor Overcurrent Protective Devices Rev. 5 3.8.1 TABLE 3.8.1-1 (Page 1 of 2)
PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES Circuit Breaker Designation System/Equipment Powered A.
Type 150A Frame - Thermal Magnetic
- 1.
2B237043 2B237043A Rx Recirc/HV-B31-2F023A
- 2.
2B219022 2B219022A Rx Recirc/HV-B31-2F031A
- 3.
2B219023 2B219023A Rx Recirc/HV-B31-2F032A
- 4.
2B246011 2B246011A Rx Recirc/HV-B31-2F023B
- 5.
2B229022 2B229022A Rx Recirc/HV-B31-2F031 B
- 6.
2B229023 2B229023A Rx Recirc/HV-B31-2F032B
- 7.
2B236042 2B236042A Drywell Air Flow/2V411 A
- 8.
2B236032 2B236032A Drywell Air Flow/2V412A
- 9.
2B236011 2B236011A Drywell Air Flow/2V413A
- 10.
2B236033 2B236033A Drywell Air Flow/2V414A 11.
2B236053 2B236053A RWCU/HV-G33-2F001
- 12.
2B236082 2B236082A Drywell Air Flow/2V415A
- 13.
2B236043 2B236043A Drywell Air Flow/2V416A
- 14.
2B236021 2B236021A Drywell Air Flow/2V417 A
- 15.
2B246091 2B246091A Drywell Air Flow/2V411 B
- 16.
2B246103 2B246103A Drywell Air Flow/2V412B
- 17.
2B246102 2B246102A Drywell Air Flow/2V413B
- 18.
2B246061 2B246061A Drywell Air Flow/2V414B
- 19.
2B246072 2B246072A Drywell Air Flow/2V415B
- 20.
2B246081 2B246081A Drywell Air Flow/2V416B 21.
2B246051 2B246051A Drywell Air Flow/2V417B
- 22.
2B236123 2B236123A Drywell Air Flow/2V418A
- 23.
2B246121 2B246121A Drywell Air Flow/2V418B
- 24.
2B236052 2B236052A RHR/HV-E11 -2F009
- 25.
2B237073 2B237073A RHR/HV-E11 -2F022
- 26.
2B237082 2B237082A HPCI/HV-E41-2F002
- 27.
2B253021 2B253021A NSSS/HV-B21 -2F011A
- 28.
2B263023 2B263023A NSSS/HV-B21 -2F011 B
- 29.
2B253041 2B253041A MSIV Hoist/TBB25
- 30.
2B263021 2B263021A MSIV Hoist/TBB26 SUSQUEHANNA - UNIT 2 TRM / 3.8-3
Primary Containment Penetration Conductor Overcurrent Protective Devices Rev. 5 3.8.1 TABLE 3.8.1-1 (Page 2 of 2)
PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES Circuit Breaker Designation System/Equipment Powered B.
Type 150A Frame - Magnetic
- 1.
2B236023 2B236023A Cont. Inst. Gas/HV-22603
- 2.
2B246022 2B246022A RCIC/HV-E51-2F007
- 3.
2B237072 2B237072A NSSS/HV-B21-2F016
- 4.
2B236102 2B236102A NSSS/HV-B21-2F001
- 5.
2B246112 2B246112A NSSS/HV-B21 -2 F002
- 6.
2B246113 2B246113A NSSS/HV-B21-2F005
- 7.
2B253052 2B253052A RWCU/HV-G33-2F102
- 8.
2B263043 28253043A RWCU/HV-G33-2F100
- 9.
2B263052 2B263052A RWCU/HV-G33-2F106
- 10.
2B246062 2B246062A RBCCW/HV-21346 11.
2B246012 2B246012A RBCCW/HV-21345
- 12.
2B253063 28253063A Drywell Sump/2P402A
- 13.
2B263071 28263071A Drywell Sump/2P402B
- 14.
2B253043 2B253043A Drywell Sump/2P403A
- 15.
2B263072 2B263072A Drywell Sump/2P403B C.
Circuit Breakers Tripped by Overcurrent Relays
- 1.
2A20501 2A20502 Rx Recirc/2P401A
- 2.
2A20601 2A20602 Rx Recirc/2P401 B SUSQUEHANNA - UNIT 2 TRM / 3.8-4
Rev. 8 TRO Applicability B 3.0 B 3.0 TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY BASES TRO 3.0.1 TRO 3.0.2 TRO 3.0.3 TRO 3.0.1 establishes the Applicability statement within each individual requirement for when the TRO is required to be met (i.e., when the unit is in the MODES or other specified conditions of the Applicability statement of each requirement).
TRO 3.0.2 establishes that upon discovery of a failure to meet a TRO, the associated ACTIONS shall be met. The Completion Time of each Required Action for an ACTIONS Condition is applicable from the point in time that an ACTIONS Condition is entered, unless otherwise specified.
The Required Actions establish those remedial measures that must be taken within specified Completion Times when the requirements of a TRO are not met. Completing the Required Actions is not required when a TRO is met or is no longer applicable, unless otherwise stated in the individual requirement.
TRO 3.0.2 provides an allowance for following administrative controls instead of the ACTIONS when necessary to allow the performance of required testing to demonstrate either the FUNCTIONALITY of the equipment that is nonfunctional in accordance with the associated TRO or the FUNCTIONALITY of other equipment.
TRO 3.0.3 establishes the actions that must be implemented when a TRO is not met and either:
- a.
An associated Required Action and Completion Time is not met and no other Condition applies; or
- b.
The condition of the unit is not specifically addressed by the associated ACTIONS.
A TRO may also direct entry into TRO 3.0.3.
Under these conditions, as a minimum, a Condition Report must be initiated in accordance with the Corrective Action Program. Initiation of a Condition Report assures that the plant condition will be corrected as required by 10 CFR 50, Appendix B, Criterion XVI, "Corrective Action."
SUSQUEHANNA - UNIT 2 TRM / B 3.0-1
TRO Applicability Rev. 8 B 3.0 BASES TRO 3.0.4 Not Used. Refer to TRO 3.0.2.
TRO 3.0.5 Not Used. Refer to TRO 3.0.2.
TRO 3.0.6 Not Used. Refer to TRO 3.0.2.
SUSQUEHANNA - UNIT 2 TRM / B 3.0-2
Rev. 8 TRO Applicability B 3.0 B 3.0 TECHNICAL REQUIREMENT SURVEILLANCE (TRS) APPLICABILITY BASES TRS 3.0.1 TRS 3.0.2 TRS 3.0.3 TRS 3.0.4 TRS 3.0.1 establishes the requirement that TRSs must be met during the MODES or other specified conditions in the Applicability for which the requirements of the TRO apply, unless otherwise specified in the individual TRSs. This TRS is to ensure that tests are performed to verify the FUNCTIONALITY of systems and components, and that variables are within specified limits. TRSs may be performed by means of any series of sequential, overlapping, or total steps provided the entire TRS is performed within the specified Frequency.
TRSs do not have to be performed when the unit is in a MODE or other specified condition for which the requirements of the associated TRO are not applicable, unless otherwise specified.
TRSs, including TRSs invoked by Required Actions, do not have to be performed on nonfunctional equipment or variable outside their limits because the ACTIONS define the remedial measures that apply. TRSs have to be met and performed in accordance with TRS 3.0.2 prior to returning equipment to FUNCTIONAL status.
TRS 3.0.2 establishes the requirements for meeting the specified Frequency for TRS and any Required Action with a Completion Time that requires the periodic performance of the Required Action on a "once per... " interval.
TRS 3.0.2 permits a 25% extension of the interval specified in the Frequency. This extension facilitates Surveillance scheduling and considers plant operating conditions that may not be suitable for conducting the TRS (e.g., transient conditions or other ongoing Surveillance or maintenance activities).
If a TRS is not performed within the specified Frequency, or it is determined that a TRS was not performed within the specified Frequency, a Condition Report shall be initiated to determine if the associated TRO is met. The TRS shall be performed at the next reasonable opportunity.
Not Used. Refer to TRS 3.0.2.
Not Used. Refer to TRS 3.0.2.
SUSQUEHANNA-UNIT 2 TRM / B 3.0-3
Rev. 1 CRD Housing Support B 3.1.2 B 3.1.2 Control Rod Drive (CRD) Housing Support BASES TRO ACTIONS TRS REFERENCES The CRD Housing Support System is designed to ensure that following a postulated CRD housing failure, control rod downward motion shall be limited so that any resulting nuclear transient could not be sufficient to cause fuel damage. The clearance between the CRD housings and the supports shall be sufficient to prevent vertical contact stresses caused by thermal expansion during plant operation. (Reference 1)
The CRD housing suppo_rts are horizontal beams installed immediately below the bottom head of the reactor vessel, between the rows of CRD housings. The beams are supported by brackets welded to the steel form liner of the drive room in the reactor support pedestal.
The CRD Housing Support restricts the outward movement of a control rod to less than 3 inches in the event of a housing failure. The amount of rod reactivity which could be added by this small amount of rod withdrawal is less than a normal withdrawal increment and will not contribute to any damage to the primary coolant system. The support is not required when there is no reactor pressure to act as a driving force to rapidly eject a drive housing.
Actions are defined to ensure proper corrective measures are taken in response to the inoperable components.
Verification is to be performed by visual inspection. The TRS is defined to be performed at the specified Frequency to ensure that the CRD Housing Support Function is maintained FUNCTIONAL.
- 1.
FSAR SECTION 5.3.3.1.4.2.
SUSQUEHANNA - UNIT 2 TRM / B 3.1-4
Rev. 5 OPRM Instrumentation B 3.3.9 B 3.3.9 OPRM Instrumentation BASES TRO The OPRM system configuration governs its operation in accordance with the licensing analysis. Several configuration parameters are intrinsic to the trip function safety setpoint bases or provide settings for defense-in-depth algorithm features that are not assumed in the basis for the protection system safety analysis (Reference 2, Reference 3).
Each of the setting values may be used as the process setpoint or device setting without further adjustment for uncertainties.
Setpoints and Settings Bases TOU£)
Period Tolerance The specified range of values for the period tolerance has been demonstrated to provide continuous confirmations upon transition from stable reactor operation to a growing reactor instability. A range of values is provided to allow system tuning to avoid spurious alarms on period confirmations. Limiting the setpoint adjustment range provides assurance that the Period Based Detection Algorithm will provide sufficient confirmations for a growing instability.
~
Conditioning Filter Cutoff Frequency The specified value for the Conditioning Filter Cutoff Frequency has been demonstrated to provide continuous confirmations upon transition from stable reactor operation to a growing reactor instability. Setting minimizes impact on signal amplitude and provides assurance that the Period Based Detection Algorithm will provide sufficient confirmations for a growing instability.
Tmin Tmax Oscillation Period Lower Time Limit Oscillation Period Upper Time Limit The Oscillation Period Time Limit parameters establish the range of detectable oscillation periods of OPRM cell signals for signal oscillations associated with reactor core thermal-hydraulic instability.
SUSQUEHANNA-UNIT 2 TRM / B 3.3-18
Rev. 5 BASES TRO
( continued)
ACTIONS LPRMmin OPRM Instrumentation B 3.3.9 This value determines the availability and resulting sensitivity of cells in the reactor core in the event of LPRM channel failures. The minimum LPRM per cell parameter is an assumption of the OPRM trip setpoint (Sp) basis calculation.
Amplitude and Growth Rate Based Algorithm Parameters S1 S2 Peak Threshold Setpoint/ABA & GRBA Valley Threshold Setpoint/ABA & GRBA Amplitude Trip Setpoint/ABA Growth Rate Factor Setpoint/GRBA These parameters calibrate the Amplitude and Growth Rate Based Algorithm, described in References 2 and 3, which provides an OPRM trip output to the Reactor Protection System. The OPRM design and licensing basis takes no credit for the Amplitude and Growth Rate Based Algorithm. The algorithm is provided as a defense-in-depth feature in the event of unanticipated power oscillations. These Amplitude and Growth Rate Based Algorithm Parameters are considered sufficient to provide backup protection and to avoid spurious trips by maximizing margin to expected operating conditions and transients.
The required actions assure that the system settings that support the Period Based Algorithm setpoint analysis, and those parameters that define the Amplitude and Growth Rate Based Algorithm are returned in a timely manner to the values assumed in the analysis (Reference 2, Reference 3) or that the affected channel is declared inoperable and the applicable Required Action of LCO 3.3.1.1 is then entered, or an alternate method to detect and suppress thermal hydraulic instability oscillations is employed.
SUSQUEHANNA-UNIT 2 TRM / B 3.3-19
Rev.5 BASES ACTIONS
( continued)
OPRM Instrumentation B 3.3.9 Note 1 has been provided to modify the ACTIONS related to affected OPRM channels. Technical Specification 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. Technical Specification Section 1.3 also specifies that Required Actions of the Condition continue to apply for each additional failure, with Completion Times based on initial entry into the Condition. However, the Required Actions for affected OPRM channels provide appropriate compensatory measures. As such, a Note has been provided that allows separate Condition entry for each affected OPRM channel.
B.1 Several parameter settings are essential for the proper operation of the OPRM period-based trip algorithm. The permissible values of Period Confirmation Tolerance, Averaging Filter time constant, Conditioning Filter Cutoff Frequency, and minimum operable LPRM per cell parameters are limited by the setpoint basis calculations and system transient response analysis. The Minimum and Maximum Oscillation Period settings limit the algorithm window to the cell signal resonances that can be associated with unstable thermal-hydraulic conditions.
Because the ability of the OPRM channel to perform its safety function is affected by these parameter settings, the affected OPRM channel must be considered inoperable when these conditions are not met.
Operability is evaluated for each inoperable channel and Required Actions taken in accordance with LCO 3.3.1.1.
C.1 The design objective for the Amplitude and Growth Rate Based Algorithms is to provide automatic action to limit the size of these unanticipated oscillations, thereby preventing fuel cladding damage.
Several parameter settings define the function of the Amplitude and Growth Rate Based Algorithm. The OPRM design and licensing basis takes no credit for the Amplitude and Growth Rate Based Algorithm, which is provided as a defense-in-depth feature in the event of unanticipated oscillations.
SUSQUEHANNA - UNIT 2 TRM / B 3.3-19a
Rev.5 BASES ACTIONS (continued)
C.1 (continued)
OPRM Instrumentation B 3.3.9 Because the ability of the OPRM channel to perform its safety function is not affected by these parameter settings, the affected OPRM channel need not be immediately considered inoperable when these conditions are not met. These parameters are to be maintained for conformance with the licensing requirement of a defense-in-depth feature in addition to the licensed OPRM trip function. This is corrected by returning the parameters to conformance within 120 days of identification.
Since the Amplitude and Growth Rate Based parameters affect only the defense-in-depth response within each channel, failure to maintain the proper parameters in the channel affects only the operability of that channel.
0.1 This Action is to be taken if the Period Based Detection Algorithm trip function is not available in accordance with LCO 3.3.1.1, and initiation of an alternate method to Detect and Suppress thermal hydraulic instability oscillations is required by the referenced LCO Required Actions. The applicable Conditions are entered as required.
E.1 As directed from Required Action 0.1, this Action provides preemptive protection through Power/Flow Map operating restrictions.
When operating in Region I of the Power/ Flow map specified in the COLR, or when operating in Region 11 of the Power/ Flow map specified in the COLR with less than 50% of the required LPRM upscale alarms FUNCTIONAL, the potential for thermal-hydraulic oscillations is greatly increased and sufficient margin may not be available for operator response to suppress potential thermal-hydraulic oscillations. Therefore, the reactor mode switch must be immediately placed in the shutdown position. Action is taken immediately to place the plant in a condition where any potential for thermal-hydraulic instabilities will be terminated.
Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/ alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors.
SUSQUEHANNA - UNIT 2 TRM / B 3.3-19b
Rev. 5 BASES ACTIONS
( continued)
F.1 OPRM Instrumentation B 3.3.9 As directed from Required Action D.1, this Action provides guidance for Operator action in response to thermal-hydraulic instability oscillations.
When operating in Region II of the Power/Flow map specified in the COLR immediate response is necessary when there are indications that thermal hydraulic oscillations are occurring as defined in Condition F.
LPRM upscale alarms are required to detect reactor core thermal-hydraulic instability events. The criteria for determining which LPRM upscale alarms are required is based on assignment of these alarms to designated core zones. These core zones consist of the level A, B, and C alarms in 4 or 5 adjacent LPRM strings. The number and location of LPRM strings in each zone assure that with 50% or more of the associated LPRM upscale alarms FUNCTIONAL sufficient monitoring capability is available to detect core wide and regional oscillations.
Operating plant instability data is used to determine the specific LPRM strings assigned to each zone.
Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/ alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors.
G.1 As directed from Required Action D.1, this Action provides guidance for Operator action in response to operation in conditions that may lead to thermal-hydraulic instability oscillations.
When operating in Region II of the Power/Flow map specified in the COLR, the potential for thermal-hydraulic oscillations is increased and sufficient margin may not be available for operator response to suppress potential thermal-hydraulic oscillations. Therefore, action must be initiated immediately to restore operation outside of Regions 11 of the Power/Flow map specified in the COLR. This can be accomplished by either decreasing THERMAL POWER with control rod insertion or increasing core flow by increasing recirculation pump speed. The starting of a recirculation pump will not be used as a means to exit the excluded Regions because the starting of a recirculation pump with the plant operating above the 70% rod line is prohibited due to potential instability problems.
SUSQUEHANNA - UNIT 2 TRM / B 3.3-19c
Rev. 5 BASES ACTIONS
( continued)
TRS H.1 OPRM Instrumentation B 3.3.9 The LPRMs provide a capability to monitor power in selected locations of the reactor core. The LPRM Upscale Alarm Instrumentation provides information concerning local power oscillations. Condition F requires a reactor scram when operating in Region II of the Power/Flow map specified in the COLR with indications that thermal hydraulic oscillations are occurring. The number and location of LPRM strings in each zone assures that with 50% or more of the associated LPRM upscale alarms FUNCTIONAL any power oscillations which could occur would be detected and proper actions can be taken.
Identification of which LPRMs are Upscale can be determined by a number of methods in the control room. The most commonly used method is visual and audible observance of the LPRM Upscale Annunciator and Alarm followed with identification of the individual LPRMs feeding the annunciation/ alarm. Identification of individual LPRM Upscale is possible by observance of the various Operator display assemblies and control panel monitors.
A sign is posted in the Control Room to ensure that plant operators are aware of the system condition if a plant transient results in the plant entering into the instability region.
TRS 3.3.9.1 Required only when the OPRM trip function is not available, this TRS ensures the combination of core flow and THERMAL POWER are within required limits to prevent uncontrolled thermal hydraulic oscillations by ensuring the recirculation loops are within the limits established by the Power / Flow map specified in the COLR. At low recirculation flows and high reactor power, the reactor exhibits increased susceptibility to thermal-hydraulic instability. The Power/ Flow map specified in the COLR is based on guidance provided in References 7, 8, and 9 which also provided the guidance on how to respond to operation in these conditions. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency is based on operating experience and the operator's inherent knowledge of the current reactor status, including significant changes in THERMAL POWER and core flow to ensure the requirements are constantly met.
TRS 3.3.9.2 This TRS is to be performed at the specified Frequency to ensure that the LPRM Upscale Alarm Instrumentation are maintained FUNCTIONAL.
SUSQUEHANNA - UNIT 2 TRM / B 3.3-19d
Rev. 5 BASES TRS (continued)
REFERENCES OPRM Instrumentation B 3.3.9 TRS 3.3.9.3 The parameter setpoint verification surveillance compares the desired settings and setpoints to the values contained in the processor memory.
This surveillance is required to assure that the settings are maintained in accordance with the setpoint analysis. The frequency is based on the OPRM CHANNEL CALIBRATION frequency per SR 3.3.1.1.18.
- 1.
NEDO-31960-A, BWROG Long Term Solution Licensing Methodology.
- 2.
NEDO-31960-A, Supp. 1, BWROG Long Term Solution Licensing Methodology.
- 3.
NEDO-32465-A, BWROG Reactor Stability Detect and Suppress Solutions Licensing Basis Methodology and Reload Applications.
- 4.
Deleted.
- 5.
- 6.
- 7.
- 8.
- 9.
Generic Letter 94-02, Long-Term Solutions and Upgrade Of Interim Operating Recommendations for Thermal-Hydraulic Instabilities in Boiling Water Reactors.
LCO 3.3.1.1, Reactor Protection System (RPS) Instrumentation.
GE Service Information Letter No. 380, "BWR Core Thermal Hydraulic Stability," Revision 1, February 10, 1984.
Letter, L.A. England to M. J. Virgilio, "BWR Owner's Group Guidelines for Stability Interim Corrective Action," June 6, 1994.
EMF-CC-074(P)(A), Volume 4, Revision 0, "BWR Stability Analysis:
Assessment of STAIF with Input from MICROBURN-B2,"
November 1999.
- 10. NEDC-32410P-A, "Nuclear Measurement Analysis and Control Power Range Neutron Monitor (NUMAC PRNM) Retrofit Plus Option Ill Stability Trip Function".
SUSQUEHANNA - UNIT 2 TRM / B 3.3-19e
Rev. 1 Reactor Coolant System Chemistry B 3.4.1 B 3.4.1 Reactor Coolant System Chemistry BASES TRO ACTIONS TRS REFERENCES The water chemistry limits of the reactor coolant system 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 0.2 ppm limit on chlorides is permitted during power operation. During shutdown and refueling operations, the temperature necessary for stress corrosion to occur is not present so a 0.5 ppm concentration of chlorides is not considered harmful during these periods.
Conductivity measurements are required on a continuous basis since changes in this parameter are an indication of abnormal conditions.
When the conductivity is within limits, the pH must also be within its acceptable limit. With the conductivity monitor nonfunctional, additional samples must be analyzed to ensure that the conductivity is not exceeding its limit.
The Actions are defined to ensure proper corrective measures are taken when limits are exceeded.
Condition F requires an engineering evaluation. This evaluation should determine the effects of the out-of-limit condition on the structural integrity of the reactor coolant system. Determine that the structural integrity of the reactor coolant system remains acceptable for continued operation prior to proceeding to MODE 2 or MODE 3. Condition F is modified by a note which limits the applicability of the condition to MODE 4 and MODE 5.
The TRSs are defined to be performed at the specified Frequency to ensure that the Reactor Coolant Chemistry is maintained within limits.
None.
SUSQUEHANNA - UNIT 2 TRM / B 3.4-1
Rev. 3 THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 2 B 3.4-7 Not Used B 3.4.6
Rev. 3 B 3.5 B 3.5.3 BASES TRO Long Term Nitrogen Supply ADS B 3.5.3 Emergency Core Cooling Systems (ECCS), Reactor Pressure Vessel (RPV) Water Inventory Control, and Reactor Core Isolation Cooling (RCIC) System Long Term Nitrogen Supply to Automatic Depressurization System (ADS)
The safety related nitrogen storage system contains adequate gas in storage for long term operation of the ADS after a postulated Design Basis Accident. The ADS system performs two functions related to safety. The first is the short term blowdown function, LCO 3.5.1, ECCS Operating, and the second is the longer term core cooling function. The design basis identifies the normal RHR shutdown cooling suction path as a viable means of post accident heat removal. Recognizing that the solitary suction flowpath between the vessel and all four RHR pumps for shutdown cooling is not single failure proof, GE Design Specifications identify an alternate mode of shutdown cooling using ADS valves to provide a return flowpath to the suppression pool. There are three flowpaths available for post accident long term core cooling. First, there is RHR shutdown cooling, addressed in Technical Specifications. The second and third paths are through either of the two sets of ADS valves supplied by the two, independent nitrogen bottle trains.
Two redundant sets of high pressure nitrogen storage bottles are designed as an ESF auxiliary supporting system to provide the necessary compressed gas for the operation of the main steam relief valves for long term depressurization and decay heat removal.
ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the nonfunctional components.
TRS The TRSs are defined to be performed at the specified Frequency to ensure that the Long Term Nitrogen Supply to ADS is maintained FUNCTIONAL.
TRS 3.5.3.1 requires verification that the Long Term Nitrogen Supply System header pressure is ;:;:: 135 psig. Verification provides assurance that the integrity of the header pressure boundary has been maintained and that the distribution piping is capable of delivering the gas necessary for long term operation of the ADS following a postulated design basis accident.
SUSQUEHANNA - UNIT 2 TRM / B 3.5-4
Rev. 3 BASES TRS
( continued)
REFERENCES Long Term Nitrogen Supply ADS B 3.5.3 TRS 3.5.3.2 requires verification that each manual and power operated valve in the Long Term Nitrogen Supply System flow path is correctly aligned. Verification provides assurance that the proper flow path will exist for Long Term Nitrogen Supply System operation. This TRS does not apply to valves that are locked, sealed, or otherwise secured in position since these were verified to be in the correct position prior to locking, sealing, or securing. This TRS does not require any testing or valve manipulation; rather, it involves verification that those valves capable of potentially being mispositioned are in the correct position.
This TRS does not apply to valves that cannot be inadvertently misaligned, such as check valves.
TRS 3.5.3.3 requires the performance of a functional test of the capability to swap to the long term nitrogen supply.
TRS 3.5.3.4 requires demonstration that the long term nitrogen supply is sufficient to maintain system pressure above 135 psig for 3 days (i.e.,
system leakage is bounded by the system design leakage rate).
- 1.
FSAR Section 9.3.1.5.
SUSQUEHANNA - UNIT 2 TRM / B 3.5-5
Rev. 4 Control Structure HVAC B 3.7.9 B 3.7 Plant Systems B 3.7.9 Control Structure HVAC BASES TRO Control structure HVAC systems have safety related functions to maintain the required air pressure control in the building and maintain the heating and cooling of support equipment required to mitigate a Loss of Coolant Accident. The Control Structure and Computer Room ventilation fans are required to maintain the habitability envelope at a positive pressure (i.e.,> O" we) and also to perform a heating and/or cooling function. The operation and surveillance requirements of the ventilation fans to maintain the habitability envelope at a positive pressure during CREOAS operation are discussed in TS 3.7.3.
Technical Specification LCOs 3.7.3 and 3.7.4 address operating and surveillance requirements for the Control Room Emergency Outside Air Supply System and the Control Room Floor Cooling System; these specifications govern OPERABILITY of the Control Structure Heating and Ventilating System, Computer Room Floor Cooling System, and Control Structure Chilled Water. The Unit 2 Technical Requirement Manual TRO 3.8.6 addresses operating requirements for the Unit 1 Emergency Switchgear Room Cooling System.
The SGTS Room Cooling and Heating systems are essential to maintain the normal and post accident environment of the Control Structure Elevation 806 within acceptable design temperature limits. CREOASS, SGTS, and Control Structure Chilled Water equipment is located on Control Structure Elevation 806.
The Battery Room Exhaust System functions to maintain the battery room design temperature, design pressure, and hydrogen concentration within limits. The Battery Room Exhaust System consists of two independent, redundant subsystems consisting of fans, ductwork, dampers and instrumentation and controls.
SUSQUEHANNA - UNIT 2 TRM / B 3.7-31
Rev. 4 BASES ACTIONS TRS REFERENCES Control Structure HVAC B 3.7.9 The Actions are defined to ensure proper corrective measures are taken in response to the nonfunctional components. With one of the HVAC subsystems nonfunctional, the nonfunctional HVAC subsystem must be restored to FUNCTIONAL status within 30 days. With the unit in this condition, the remaining FUNCTIONAL HVAC subsystem is adequate to perform the cooling and/or heating function. However, the overall reliability is reduced because a single failure in the FUNCTIONAL subsystem results in the loss of the HVAC function. The 30 day Completion Time is based on the consideration that the remaining subsystem can provide the required protection, and the availability of alternate nonsafety cooling methods.
The TRS assures sufficient system functionality to ensure operation when called upon to perform its design function.
- 1.
FSAR Section 9.4.1.
- 2.
FSAR Section 9.2.12.1.
SUSQUEHANNA - UNIT 2 TRM / B 3.7-32
Rev. 4 Structural Integrity B 3.7.11 B 3.7.11 Structural Integrity BASES TRO ACTIONS The inspection programs for American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 components ensure that the structural integrity of these components will be maintained at an acceptable level throughout the life of the plant. This requirement identifies appropriate actions to be taken upon discovery of indications or flaws in components that affect the structural integrity in piping and components.
This requirement applies to all ASME Code Class 1, 2, and 3 piping and components.
In addition to these piping and components, structural support components such as pipe hangers, vendor catalog items, supplementary steel, base plates, welds, bolts, etc are considered part of the scope of this TRO.
Snubbers are not considered part of the scope of this TRO. They are part of the scope of TRO 3.7.8.
The lnservice Inspection (ISi) Program for ASME Code Class 1, 2 and 3 components will be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable addenda as required by 1 0CFR Part 50.55a(g) except where specific written relief has been granted by the NRC pursuant to 1 0 CFR Part 50.55a(g)(6)(i).
(Reference 1)
The Actions are defined to ensure proper corrective measures are taken in response to the inoperable / nonfunctional components.
A.1 Upon finding an "indication," ISi personnel will conduct further investigation. During the time frame of these investigations, no Condition Reports (CR) are generated and no Technical Requirement is considered not met.
SUSQUEHANNA - UNIT 2 TRM / B 3.7-36
Rev.4 BASES ACTIONS (continued)
A.1 (continued)
Structural Integrity B 3.7.11 At such time as the above examinations indicate that an "unevaluated indication" exists (i.e., an indication which fails to meet the acceptance criteria of the ASME or applicable code, the requirements of an endorsed ASME Code Case, or an NRC approved alternative), a CR will be written and forwarded for review. In addition this TRO will be declared "not met" and Condition A will be entered. As stated in a Note for Condition A, an evaluation of all "unevaluated indications" must be completed. If the "indication" is found to impact the structural integrity or OPERABILITY/
FUNCTIONALITY of the component, system, or structure, the appropriate TRO Condition shall be entered. If the evaluation determines that the flaw does not impact the component, systems, or structure OPERABILITY
/ FUNCTIONALITY or structural integrity, the "indication" becomes an "evaluated indication" and the TRO is considered met and the Actions Table is exited. The 72-hour Completion Time provides a reasonable amount of time to perform the necessary evaluations.
If the OPERABILITY/ FUNCTIONALITY evaluation cannot be completed within the required Completion Time, the component shall be declared inoperable / nonfunctional and the appropriate LCOs and TROs entered.
C.1 When ASME Class 1 pressure retaining 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 or FUNCTIONALITY assessment cannot conclude a reasonable expectation of OPERABILITY
/ FUNCTIONALITY exists and the components are inoperable /
nonfunctional. Satisfaction of Code acceptance standards is the minimum necessary for OPERABILITY/ FUNCTIONALITY of Class 1 pressure boundary components because of the importance of the safety function being performed.
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 declared inoperable/ nonfunctional.
SUSQUEHANNA - UNIT 2 TRM / B 3.7-37
Rev. 4 BASES ACTIONS
( continued)
D. 1, D.2, and D.3 Structural Integrity B 3.7.11 When ASME Class 2 or Class 3 pressure retaining 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 of whether the deficient condition results in a TSffRM-required SSC or a TS/TRM-required support sec being inoperable/ nonfunctional must be made. In order to determine the component is OPERABLE/ FUNCTIONAL under an immediate OPERABILITY determination or FUNCTIONALITY assessment, the degradation mechanism must be readily apparent. To be readily apparent, the degradation mechanism must be discernable from visual 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 or FUNCTIONALITY assessment. If detailed non-destructive examination is necessary and the examination 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
/ nonfunctional and the appropriate TSffRM action statement entered.
There is no indeterminate state of OPERABILITY.
The time frame for flaw characterization and engineering analysis should be no longer than a reasonable time frame for completing the actions.
If at any point during the performance of the prompt operability (functionality) determination assessment a component is determined to be nonfunctional or inoperable, declare the affected component(s) and associated systems, structures or components inoperable / nonfunctional in accordance with Required Action D.3.
E.1, E.2, and E.3 Structural support components are required to be OPERABLE /
FUNCTIONAL by the TS or TRM, since they are related support functions for secs in the TS or TRM. Examples of structural degradation are concrete cracking and spalling, excessive deflection or deformation, water leakage, rebar corrosion, missing or bent anchor bolts, and degradation of door and penetration sealing. If the support structure is deficient, the support 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.
SUSQUEHANNA - UNIT 2 TRM / B 3.7-38
Rev. 4 BASES ACTIONS
( continued)
TRS E.1, E.2, and E.3 (continued)
Structural Integrity B 3.7.11 The time frame for an engineering analysis should be no longer than a reasonable time frame for completing the actions.
If at any point during the performance of the prompt operability (functionality) determination assessment a component is determined to be nonfunctional or inoperable, declare the affected component(s) and associated systems, structures or components inoperable / nonfunctional in accordance with Required Action E.3. "If applicable" is used in E.3 to mean if a component does not need to maintain structural integrity for a system to perform its specified safety function, and the condition does not impact the ability of other TS or TRM SSCs to perform their specified design or safety functions, then the condition can be addressed through other processes (e.g., corrective action program).
F.1 and F.2 The preceding actions addressed conditions associated with components required to be OPERABLE/ FUNCTIONAL at the time of discovery.
Condition F Required Actions prescribe commensurate actions for conditions associated with components not required to be OPERABLE /
FUNCTIONAL at the time of discovery. Specifically, a deficient condition must be restored or repaired to be code-compliant prior to entering the mode of applicability or a prompt operability determination shall be completed prior to entering the mode of applicability to determine if the condition is acceptable as-is (OPERABLE or OPERABLE-deficient). If the condition renders the component nonfunctional or inoperable, the affected component(s) and associated systems, structures or components must be declared inoperable / nonfunctional and appropriate actions taken to restore the OPERABILITY/ FUNCTIONALITY prior to entering the mode of applicability for the component.
The TRSs are defined to be performed at the specified Frequency to ensure that the Structural Integrity requirements are maintained.
The Frequency for the TRS is defined by the ISi Program.
SUSQUEHANNA - UNIT 2 TRM / B 3.7-39
Rev. 4 BASES REFERENCES
- 1.
Structural Integrity B 3.7.11
- 2.
Regulatory Issue Summary 2005-20, Revision 1, "Revision to Guidance Formerly Contained in NRC Generic Letter 91-18,
'Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operability."'
SUSQUEHANNA - UNIT 2 TRM / B 3.7-40
Rev. 3 Primary Containment Penetration Conductor Overcurrent Protective Devices B 3.8.1 B 3.8.1 Primary Containment Penetration Conductor Overcurrent Protective Devices BASES TRO ACTIONS TRO 3.8.1 requires that all primary containment penetration conductor overcurrent protective devices are FUNCTIONAL. This assures that the design limits of the containment electrical penetrations will not be challenged as a result of electrical faults on the penetration conductors.
Primary containment electrical penetrations and penetration conductors are protected by either de-energizing circuits not required during reactor operation or demonstrating the FUNCTIONALITY of primary and backup overcurrent protection circuit breakers by periodic surveillance.
The ACTIONS are defined to ensure proper corrective measures are taken in response to the nonfunctional components.
The ACTIONS have been modified by a Note to clarify the application of Completion Time rules. The Conditions of this TRO may be entered independently for each affected protective device. The Completion Time(s) of the nonfunctional primary containment penetration conductor overcurrent protective device will be tracked separately for each affected device starting from the time the Condition was entered for that device as a result of discovery of a nonfunctional device.
A.1 and A.2 With one or more required primary containment penetration conductor overcurrent protective devices nonfunctional, the circuit(s) associated with the nonfunctional protection device(s) must be placed in a condition that would preclude the possibility of a fault that could overload the circuit(s).
To accomplish this, the circuit is deenergized. Since systems or components supplied by the affected circuit will no longer have power, they must be declared inoperable or nonfunctional, as applicable. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time takes into account the design of the electrical penetration for maximum fault current, the availability of backup circuit protection on the distribution system and the low probability of a design basis accident occurring during this period. This Completion Time is also considered reasonable to perform the necessary repairs or circuit alterations to restore or otherwise deenergize the affected circuit.
In order to assure that any electrical penetration which is not protected by an overcurrent device remains deenergized, it is necessary to periodically verify that its alternate circuit breaker is opened, or that the nonfunctional circuit breaker is opened. A Completion Time of once per 7 days is considered sufficient due to the infrequency of plant operations that could result in reenergizing a circuit that has been deenergized in this manner.
SUSQUEHANNA - UNIT 2 TRM / B 3.8-1
Rev. 3 BASES ACTIONS
( continued)
TRS Primary Containment Penetration Conductor Overcurrent Protective Devices B 3.8.1 B.1 In the event that the Required Actions and associated Completion Times of Condition A are not met, TRO 3.0.3 must be entered.
The TRSs are performed at the specified Frequency to ensure that the required overcurrent protective devices are maintained FUNCTIONAL.
TRS 3.8.1.1 This surveillance requires the performance of a functional test on a representative sample of ::::: 10% of each type of lower voltage circuit breaker used as penetration protection. This sample size is sufficiently large to represent the actual failure distribution within the whole population of circuit breakers of a given type used in the plant. Circuit breakers selected for functional testing should be selected on a rotating basis.
A representative sample is determined based upon each manufacturer's brand of circuit breaker. Each manufacturer's molded case and metal case circuit breakers are grouped into representative samples, which are then tested on a rotating basis to ensure that all breakers are tested. If a wide variety exists within any manufacturer's brand of circuit breakers, it is necessary to divide that manufacturer's breakers into groups and treat each group as a separate type of breaker for surveillance purposes.
This surveillance has been modified by a Note stating that for each circuit breaker found nonfunctional during these functional tests, an additional representative sample of at least 10% of all circuit breakers of the same type shall be functionally tested until no more failures are found or all circuit breakers of that type have been tested. The expansion of the test population ensures that a failure discovered in the representative sample was not caused by a failure mechanism that could systematically affect other breakers in the overall population of breakers of the same type.
SUSQUEHANNA - UNIT 2 TRM / B 3.8-2
Rev. 3 BASES TRS
( continued)
REFERENCES Primary Containment Penetration Conductor Overcurrent Protective Devices B 3.8.1 The functional tests required by TRS 3.8.1.1 consist of injecting a current with a value equal to 300% of the pickup of the thermal (long term time delay) element of Types 150A Frame and 250A Frame (thermal magnetic) circuit breakers, and verifying that the circuit breaker operates within the time delay band-width specified by the manufacturer for the test current. The magnetic (instantaneous) element is tested by injecting a current in excess of 120% of the pickup value of the magnetic (instantaneous) element and verifying that the circuit breaker trips instantaneously with no intentional time delay. Type 150A Frame (magnetic only) circuit breaker testing also follows this procedure except that no thermal trip elements are involved. Circuit breakers found nonfunctional during functional testing should be restored to FUNCTIONAL status prior to resuming operation.
If there are any failure mechanisms that could affect the FUNCTIONALITY of the circuit breaker(s), they are likely to have occurred in the sample tested. The 24 month Frequency takes into consideration the infrequent operation of the breakers and their correspondingly low failure rate.
TRS 3.8.1.2 This surveillance requires the performance of a functional test on each required overcurrent relay. The functional test consists of injecting a current sufficient to actuate the relay, verify that the pickup current is less than 120% of the nominal relay pickup current, and that the measured response time is within +/-10% of the specified value. The 24 month Frequency takes into consideration the infrequent operation of the breakers and their correspondingly low failure rate.
TRS 3.8.1.3 This surveillance requires the inspection of each circuit breaker and the performance of procedures prepared in conjunction with the manufacturer's recommendations. By performance of recommended maintenance, the likelihood for the circuit breakers to become nonfunctional can be minimized. The 120 month Frequency takes into consideration the low frequency of operation of the circuit breakers and the low likelihood that operation and maintenance activities could adversely affect the FUNCTIONALITY of the circuit breakers. Provisions of TRS 3.0.2 are not applicable.
None.
SUSQUEHANNA - UNIT 2 TRM / B 3.8-2a