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{{#Wiki_filter:Feb. 20, 2014Page1 of 2MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2014-6829 USER INFORMATION:
{{#Wiki_filter:Feb. 20, 2014 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2014-6829 USER INFORMATION:
GERLACH*ROSEY MEMPL#:028401 CA#: 0363Address:
GERLACH*ROSEY M EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION:
NUCSA2Phone#: 254-3194TRANSMITTAL INFORMATION:
TO: GERLACH*ROSEY M 02/20/2014 LOCATION:
TO: GERLACH*ROSEY M 02/20/2014 LOCATION:
USNRCFROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)
USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU. HARDCOPY USERS
THE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNEDTO YOU. HARDCOPY USERS MUST ENSURE THE DOCUMENTS PROVIDED MATCH THE INFORMATION ONTHIS TRANSMITTAL.
WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY
SUSQUEHANNA  
SUSQUEHANNA  
-UNIT 2TS / B 3.4-31Revision 1
-UNIT 2 TS / B 3.4-31 Revision 1 PPL Rev. 4 RCS Leakage Detection Instrumentation B 3.4.6 BASES LCO (continued)
PPL Rev. 4RCS Leakage Detection Instrumentation B 3.4.6BASESLCO(continued)
The reactor coolant contains radioactivity that, when released to the primary containment, can be detected by the gaseous or particulate primary containment atmospheric radioactivity monitor. Only one of the two detectors is required to be OPERABLE.
The reactor coolant contains radioactivity that, when released to theprimary containment, can be detected by the gaseous or particulate primary containment atmospheric radioactivity monitor.
Radioactivity detection systems are included for monitoring both particulate and gaseous activities because of their sensitivities and rapid responses to RCS LEAKAGE, but have recognized limitations.
Only one of thetwo detectors is required to be OPERABLE.
Reactor coolant radioactivity levels will be low during initial reactor startup and for a few weeks thereafter, until activated corrosion products have been formed and fission products appear from fuel element cladding contamination or cladding defects. If there are few fuel element cladding defects and low levels of activation products, it may not be possible for the gaseous or particulate primary containment atmospheric radioactivity monitors to detect a 1 gpm increase within 1 hour during normal operation.
Radioactivity detection systems are included for monitoring both particulate and gaseousactivities because of their sensitivities and rapid responses to RCSLEAKAGE, but have recognized limitations.
However, the gaseous or particulate containment primary atmospheric radioactivity monitor is OPERABLE when it is capable of detecting a 1 gpm increase in unidentified LEAKAGE within 1 hour given an RCS activity equivalent to that assumed in the design calculations for the monitors (Reference 6).The LCO is satisfied when monitors of diverse measurement means are available.
Reactor coolant radioactivity levels will be low during initial reactor startup and for a few weeksthereafter, until activated corrosion products have been formed and fissionproducts appear from fuel element cladding contamination or claddingdefects.
Thus, the drywell floor drain sump monitoring system, in combination with a gaseous or particulate primary containment atmospheric radioactivity monitor provides an acceptable minimum.APPLICABILITY In MODES 1, 2, and 3, leakage detection systems are required to be OPERABLE to support LCO 3.4.4. This Applicability is consistent with that for LCO 3.4.4.ACTIONS A.1 With the drywell floor drain sump monitoring system inoperable, the primary containment atmospheric activity monitor will provide indication of changes in leakage.With the drywell floor drain sump monitoring system inoperable, operation may continue for 30 days. However, RCS unidentified and total LEAKAGE is still required to be determined every 12 hours (SR 3.4.4.1).The 30 day Completion Time of Required Action A.1 is acceptable, based on operating experience, considering the multiple forms of leakage detection that are still available.(continued)
If there are few fuel element cladding defects and low levels ofactivation
SUSQUEHANNA-UNIT2 TS / B 3.4-32 Revision 2 PPL Rev. 4 RCS Leakage Detection Instrumentation B 3.4.6 BASES ACTIONS B.1 and B.2 (continued)
: products, it may not be possible for the gaseous or particulate primary containment atmospheric radioactivity monitors to detect a 1 gpmincrease within 1 hour during normal operation.  
With both gaseous and particulate primary containment atmospheric monitoring channels inoperable, grab samples of the primary containment atmosphere must be taken and analyzed to provide periodic leakage information.
: However, the gaseous orparticulate containment primary atmospheric radioactivity monitor isOPERABLE when it is capable of detecting a 1 gpm increase inunidentified LEAKAGE within 1 hour given an RCS activity equivalent tothat assumed in the design calculations for the monitors (Reference 6).The LCO is satisfied when monitors of diverse measurement means areavailable.
Provided a sample is obtained and analyzed once every 12 hours, the plant may be operated for up to 30 days to allow restoration of at least one of the required monitors.The 12 hour interval provides periodic information that is adequate to detect LEAKAGE. The 30 day Completion Time for restoration recognizes that at least one other form of leakage detection is available.
Thus, the drywell floor drain sump monitoring system, incombination with a gaseous or particulate primary containment atmospheric radioactivity monitor provides an acceptable minimum.APPLICABILITY In MODES 1, 2, and 3, leakage detection systems are required to beOPERABLE to support LCO 3.4.4. This Applicability is consistent withthat for LCO 3.4.4.ACTIONSA.1With the drywell floor drain sump monitoring system inoperable, theprimary containment atmospheric activity monitor will provide indication ofchanges in leakage.With the drywell floor drain sump monitoring system inoperable, operation may continue for 30 days. However, RCS unidentified and totalLEAKAGE is still required to be determined every 12 hours (SR 3.4.4.1).
C.1, C.2 and C.3 With the drywell floor drain sump monitoring system inoperable, the only means of detecting LEAKAGE is the primary containment atmospheric gaseous radiation monitor. A Note clarifies this applicability of the Condition.
The 30 day Completion Time of Required Action A.1 is acceptable, basedon operating experience, considering the multiple forms of leakagedetection that are still available.
The primary containment atmospheric gaseous radiation monitor typically cannot detect a 1 gpm leak within one hour when RCS activity is low. In addition, this configuration does not provide the required diverse means of leakage detection.
(continued)
Indirect methods of monitoring RCS leakage must be implemented.
SUSQUEHANNA-UNIT2 TS / B 3.4-32Revision 2
Grab samples of the primary containment atmosphere must be taken and analyzed and monitoring of RCS leakage by administrative means must be performed every 12 hours to provide alternate periodic information.
PPL Rev. 4RCS Leakage Detection Instrumentation B 3.4.6BASESACTIONS B.1 and B.2(continued)
Administrative means of monitoring RCS leakage include monitoring and trending parameters that may indicate an increase in RCS leakage. There are diverse alternative mechanisms from which appropriate indicators may be selected based on plant conditions.
With both gaseous and particulate primary containment atmospheric monitoring channels inoperable, grab samples of the primary containment atmosphere must be taken and analyzed to provide periodic leakageinformation.
It is not necessary to utilize all of these methods, but a method or methods should be selected considering-the current plant conditions and historical or expected sources of unidentified leakage. The administrative methods are primary containment pressure, temperature, Component Cooling Water System outlet temperatures and makeup, Reactor Recirculation System pump seal pressure and temperature and motor cooler temperature indications, Drywell cooling fan outlet temperatures, Reactor Building Chiller amperage, Control Rod Drive System flange temperatures, Safety Relief Valve tailpipe temperature, flow, pressure, or other approved methods.These indications, coupled with the atmospheric grab samples, are sufficient to alert the operating staff to an unexpected increase in unidentified LEAKAGE.(continued)
Provided a sample is obtained and analyzed once every12 hours, the plant may be operated for up to 30 days to allow restoration of at least one of the required monitors.
The 12 hour interval provides periodic information that is adequate todetect LEAKAGE.
The 30 day Completion Time for restoration recognizes that at least one other form of leakage detection is available.
C.1, C.2 and C.3With the drywell floor drain sump monitoring system inoperable, the onlymeans of detecting LEAKAGE is the primary containment atmospheric gaseous radiation monitor.
A Note clarifies this applicability of theCondition.
The primary containment atmospheric gaseous radiation monitor typically cannot detect a 1 gpm leak within one hour when RCSactivity is low. In addition, this configuration does not provide the requireddiverse means of leakage detection.
Indirect methods of monitoring RCSleakage must be implemented.
Grab samples of the primary containment atmosphere must be taken and analyzed and monitoring of RCS leakageby administrative means must be performed every 12 hours to providealternate periodic information.
Administrative means of monitoring RCS leakage include monitoring andtrending parameters that may indicate an increase in RCS leakage.
Thereare diverse alternative mechanisms from which appropriate indicators maybe selected based on plant conditions.
It is not necessary to utilize all ofthese methods, but a method or methods should be selected considering
-the current plant conditions and historical or expected sources ofunidentified leakage.
The administrative methods are primarycontainment
: pressure, temperature, Component Cooling Water Systemoutlet temperatures and makeup, Reactor Recirculation System pumpseal pressure and temperature and motor cooler temperature indications, Drywell cooling fan outlet temperatures, Reactor Building Chilleramperage, Control Rod Drive System flange temperatures, Safety ReliefValve tailpipe temperature, flow, pressure, or other approved methods.These indications, coupled with the atmospheric grab samples, aresufficient to alert the operating staff to an unexpected increase inunidentified LEAKAGE.(continued)
SUSQUEHANNA  
SUSQUEHANNA  
-UNIT 2TS / B 3.4-33Revision 2
-UNIT 2 TS / B 3.4-33 Revision 2 PPL Rev. 4 RCS Leakage Detection Instrumentation B 3.4.6 BASES ACTIONS C.1. C.2 and C.3 (continued)
PPL Rev. 4RCS Leakage Detection Instrumentation B 3.4.6BASESACTIONS C.1. C.2 and C.3 (continued)
The 12 hour interval is sufficient to detect increasing RCS leakage. The Required Action provides 7 days to restore another RCS leakage monitor to OPERABLE status to regain the intended leakage detection diversity.
The 12 hour interval is sufficient to detect increasing RCS leakage.
The 7 day Completion Time ensures that the plant will not be operated in a degraded configuration for a lengthy time period.D.1 and D.2 If any Required Action of Condition A, B or C cannot be met within the associated Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours and MODE 4 within 36 hours.The allowed Completion Times are reasonable, based on operating experience, to perform the actions in an orderly manner and without challenging plant systems.E.1 With all required monitors inoperable, no required automatic means of monitoring LEAKAGE are available, and immediate plant shutdown in accordance with LCO 3.0.3 is required.SURVEILLANCE REQUIREMENTS This SR is for the performance of a CHANNEL CHECK of the required primary containment atmospheric monitoring system. The check gives reasonable confidence that the channel is operating properly.
TheRequired Action provides 7 days to restore another RCS leakage monitorto OPERABLE status to regain the intended leakage detection diversity.
The Frequency of 12 hours is based on instrument reliability and is reasonable for detecting off normal conditions.
The 7 day Completion Time ensures that the plant will not be operated ina degraded configuration for a lengthy time period.D.1 and D.2If any Required Action of Condition A, B or C cannot be met within theassociated Completion Time, the plant must be brought to a MODE inwhich the LCO does not apply. To achieve this status, the plant must bebrought to at least MODE 3 within 12 hours and MODE 4 within 36 hours.The allowed Completion Times are reasonable, based on operating experience, to perform the actions in an orderly manner and withoutchallenging plant systems.E.1With all required monitors inoperable, no required automatic means ofmonitoring LEAKAGE are available, and immediate plant shutdown inaccordance with LCO 3.0.3 is required.
SR 3.4.6.2 This SR is for the performance of a CHANNEL FUNCTIONAL TEST of the required RCS leakage detection instrumentation.
SURVEILLANCE REQUIREMENTS This SR is for the performance of a CHANNEL CHECK of the requiredprimary containment atmospheric monitoring system. The check givesreasonable confidence that the channel is operating properly.
The test ensures that the monitors can perform their function in the desired manner. The Frequency of 31 days considers instrument reliability, and operating experience has shown it proper for detecting degradation.(continued)
TheFrequency of 12 hours is based on instrument reliability and is reasonable for detecting off normal conditions.
SR 3.4.6.2This SR is for the performance of a CHANNEL FUNCTIONAL TEST of therequired RCS leakage detection instrumentation.
The test ensures thatthe monitors can perform their function in the desired manner. TheFrequency of 31 days considers instrument reliability, and operating experience has shown it proper for detecting degradation.
(continued)
SUSQUEHANNA  
SUSQUEHANNA  
-UNIT 2TS / B 3.4-34Revision 1
-UNIT 2 TS / B 3.4-34 Revision 1 PPL Rev. 4 RCS Leakage Detection Instrumentation B 3.4.6 BASES SURVEILLANCE SR 3.4.6.3 REQUIREMENTS (continued)
PPL Rev. 4RCS Leakage Detection Instrumentation B 3.4.6BASESSURVEILLANCE SR 3.4.6.3REQUIREMENTS (continued)
This SR is for the performance of a CHANNEL CALIBRATION of required leakage detection instrumentation channels.
This SR is for the performance of a CHANNEL CALIBRATION of requiredleakage detection instrumentation channels.
The calibration verifies the accuracy of the instrument string, including the instruments located inside containment.
The calibration verifies theaccuracy of the instrument string, including the instruments located insidecontainment.
The Frequency of 24 months is a typical refueling cycle and considers channel reliability.
The Frequency of 24 months is a typical refueling cycle andconsiders channel reliability.
REFERENCES  
REFERENCES  
: 1. 10 CFR 50, AppendixA, GDC 30.2. Regulatory Guide 1.45, Revision 0, "Reactor Coolant PressureBoundary Leakage Detection Systems,"
: 1. 10 CFR 50, AppendixA, GDC 30.2. Regulatory Guide 1.45, Revision 0, "Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973.3. GEAP-5620, April 1968.4. NUREG-75/067, October 1975.5. FSAR, Section 5.2.5.4.6. FSAR, Section 5.2.5.1.2 7. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).SUSQUEHANNA  
May 1973.3. GEAP-5620, April 1968.4. NUREG-75/067, October 1975.5. FSAR, Section 5.2.5.4.6. FSAR, Section 5.2.5.1.2
-UNIT 2 TS I B 3.4-34a Revision 0}}
: 7. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).SUSQUEHANNA  
-UNIT 2TS I B 3.4-34aRevision 0}}

Revision as of 22:53, 9 July 2018

Susquehanna, Unit 2, Revision to Technical Specifications Bases Manual
ML14063A428
Person / Time
Site: Susquehanna Talen Energy icon.png
Issue date: 02/20/2014
From: Gerlach R M
Susquehanna
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
2014-6829
Download: ML14063A428 (25)
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Text

Feb. 20, 2014 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2014-6829 USER INFORMATION:

GERLACH*ROSEY M EMPL#:028401 CA#: 0363 Address: NUCSA2 Phone#: 254-3194 TRANSMITTAL INFORMATION:

TO: GERLACH*ROSEY M 02/20/2014 LOCATION:

USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2)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 ERRORS.ATTENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no TOC will be issued with the updated material.TSB2 -TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL REMOVE MANUAL TABLE OF CONTENTS DATE: 12/10/2013 ADD MANUAL TABLE OF CONTENTS DATE: 02/19/2014 CATEGORY:

DOCUMENTS TYPE: TSB2 IJ~L Feb. 20, 2014 Page 2 of 2 ID: TEXT 3.4.6 ADD: REV: 4 REMOVE: REV:3 CATEGORY: ID: TEXT REMOVE: DOCUMENTS TYPE: TSB2 LOES REV:116 ADD: REV: 117 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS @ X3107 OR X3136 FOR ASSISTANCE.

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.

SSES MANUAL Manual Name: TSB2 Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL Table Of Contents Issue Date: 02/19/2014 Procedure Name Rev TEXT LOES 117 Title: LIST OF EFFECTIVE SECTIONS C"NTROLLED Issue Date 02/19/2014 Change ID Change Number TEXT TOC Title: TABLE OF CONTENTS 20 03/28/2013 TEXT 2.1.1 4 Title: SAFETY LIMITS (SLS) REACTOR TEXT 2.1.2 1 Title: SAFETY LIMITS (SLS) REACTOR 05/06/2009 CORE SLS 10/04/2007 COOLANT SYSTEM (RCS) PRESSURE SL TEXT 3.0 3 08/20/2009 Title: LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY TEXT 3.1.1 Title: REACTIVITY TEXT 3.1.2 Title: REACTIVITY TEXT 3.1.3 Title: REACTIVITY TEXT 3.1.4 Title: REACTIVITY TEXT 3.1.5 Title: REACTIVITY TEXT 3.1.6 Title: REACTIVITY 1 03/24/2005 CONTROL SYSTEMS SHUTDOWN MARGIN (SDM)0 11/18/2002 CONTROL SYSTEMS REACTIVITY ANOMALIES 2 01/19/2009 CONTROL SYSTEMS CONTROL ROD OPERABILITY 4 01/30/2009 CONTROL SYSTEMS CONTROL ROD SCRAM TIMES 1 07/06/2005 CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS 2 03/24/2005 CONTROL SYSTEMS ROD PATTERN CONTROL Pagel of 8 Report Date: 02/20/14 Page I of .8 Report Date: 02/20/14 SSES MANUAL Manual Name: TSB2 Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.1.7 3 10/04/2007 Title: REACTIVITY CONTROL SYSTEMS STANDBY LIQUID CONTROL (SLC) SYSTEM TEXT 3.1.8 3 05/06/2009 Title: REACTIVITY CONTROL SYSTEMS SCRAM DISCHARGE VOLUME (SDV) VENT AND DRAIN VALVES TEXT 3.2.1 Title: POWER DISTRIBUTION TEXT 3.2.2 Title: POWER DISTRIBUTION 4 05/06/2009 LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)3 05/06/2009 LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)TEXT 3.2.3 2 05/06/2009 Title: POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE LHGR TEXT 3.3.1.1 Title: INSTRUMENTATION 4 05/06/2009 REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT 3.3.1.2 2 01/19/2009 Title: INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.2.1 2 04/09/2007 Title: INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.3.2.2 2 02/22/2012 Title: INSTRUMENTATION FEEDWATER

-MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 8 02/28/2013 Title: INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT 3.3.3.2 1 04/18/2005 Title: INSTRUMENTATION REMOTE SHUTDOWN SYSTEM TEXT 3.3.4.1 1 05/06/2009 Title: INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT)

INSTRUMENTATION Page 2 of .8 Report Date: 02/20/14 SSES MANUAL.Manual Name: TSB2 Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.3.4.2 0 11/18/2002 Title: INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULATION PUMP TRIP (ATWS-RPT)

INSTRUMENTATION TEXT 3.3.5.1 4 08/20/2009 Title: INSTRUMENTATION EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATION TEXT 3.3.5.2 Title: INSTRUMENTATION TEXT 3.3.6.1 Title: INSTRUMENTATION TEXT 3.3.6.2 Title: INSTRUMENTATION TEXT 3.3.7.1 Title: INSTRUMENTATION INSTRUMENTATION TEXT 3.3.8.1 Title: INSTRUMENTATION TEXT 3.3.8.2 Title: INSTRUMENTATION TEXT 3.4.1 Title: REACTOR COOLANT TEXT 3.4.2 Title: REACTOR COOLANT TEXT 3.4.3 Title: REACTOR COOLANT.TEXT 3.4.4 Title: REACTOR COOLANT 0 11/18/2002 REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM INSTRUMENTATION 5 07/23/2013 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION 4 09/01/2010 SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION 2 10/27/2008 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM 3 12/17/2007 LOSS OF POWER (LOP) INSTRUMENTATION 0 11/18/2002 REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORING 4 07/20/2010 SYSTEM (RCS)3 SYSTEM (RCS)3 SYSTEM (RCS)0 SYSTEM (RCS)RECIRCULATION LOOPS OPERATING 10/23/2013 JET PUMPS 01/13/2012 SAFETY/RELIEF VALVES (S/RVS)11/18/2002 RCS OPERATIONAL LEAKAGE Page3 of 8 Report Date: 02/20/14 Page 3 of .8 Report Date: 02/20/14 SSES MANUJAL Manual Name: TSB2 Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.4.5 3 03/10/2010 Title: REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE TEXT 3.4.6 4 02/19/2014 Title: REACTOR COOLANT SYSTEM (RCS) RCS LEAKAGE DETECTION INSTRUMENTATION TEXT 3.4.7 2 10/04/2007 Title: REACTOR COOLANT SYSTEM (RCS) RCS SPECIFIC ACTIVITY TEXT 3.4.8 Title: REACTOR COOLANT-HOT SHUTDOWN TEXT 3.4.9 Title: REACTOR COOLANT-COLD SHUTDOWN TEXT 3.4.10 Title: REACTOR COOLANT TEXT 3.4.11 Title: REACTOR COOLANT TEXT 3.5.1 2 SYSTEM (RCS)1 SYSTEM (RCS)3 SYSTEM (RCS)03/28/2013 RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM 03/28/2013 RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING 05/06/2009 RCS PRESSURE AND TEMPERATURE (P/T) LIMITS SYSTEM 0 0 11/18/2002 SYSTEM (RCS) REACTOR STEAM DOME PRESSURE 3 01/16/2006 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION SYSTEM ECCS -OPERATING TEXT 3.5.2 0 11/18/2002 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION SYSTEM ECCS -SHUTDOWN TEXT 3.5.3 2 07/09/2010 Title: EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION SYSTEM RCIC SYSTEM COOLING (RCIC)COOLING (RCIC)COOLING (RCIC)TEXT 3.6.1.1 Title: PRIMARY CONTAINMENT 4 11/09/2011 TEXT 3.6.1.2 1 05/06/2009 Title: CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCK Page4 of 8 Report Date: 02/20/14 Page 4 of .8 Report Date: 02/20/14 SSES MANUAL.Manual Name: TSB2 Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.6.1.3 Title: CONTAINMENT TEXT 3.6.1.4 Title: CONTAINMENT TEXT 3.6.1.5 Title: CONTAINMENT TEXT 3.6.1.6 Title: CONTAINMENT TEXT 3.6.2.1 Title: CONTAINMENT TEXT 3.6.2.2 Title: CONTAINMENT TEXT 3.6.2.3 Title: CONTAINMENT TEXT 3.6.234 Title: CONTAINMENT TEXT 3.6.3.1 Title: CONTAINMENT TEXT 3.6.3.2 Title: CONTAINMENT TEXT 3.6.343 Title: CONTAINMENT STEXT 3.6.4.1 Title: CONTAINMENT 12 05/29/2013 SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)1 05/06/2009 SYSTEMS CONTAINMENT PRESSURE 1 10/05/2005 SYSTEMS DRYWELL AIR TEMPERATURE 0 11/18/2002 SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS 2 12/17/2007 SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE 0 11/18/2002 SYSTEMS SUPPRESSION POOL WATER LEVEL 1 01/16/2006 SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL COOLING 0 11/18/2002 SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL SPRAY 2 06/13/2006 SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS 1 04/18/2005 SYSTEMS DRYWELL AIR FLOW SYSTEM 1 02/28/2013 SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION 9 12/10/2013 SYSTEMS SECONDARY CONTAINMENT Page~ of 8 Report Date: 02/20/14 Page a of 8 Report Date: 02/20/14 SSES MANUAL Manual Name: TSB2 Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.6.4.2 8 03/28/2013 Title: CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)TEXT 3.6.4.3 4 09/21/2006 Title: CONTAINMENT SYSTEMS STANDBY GAS TREATMENT (SGT) SYSTEM TEXT 3.7.1 Title: PLANT ULTIMA TEXT 3.7.2 Title: PLANT TEXT 3.7.3 Title: PLANT TEXT 3.7.4 Title: PLANT TEXT 3.7.5 Title: PLANT TEXT 3.7.6 Title: PLANT TEXT 3.7.7 Title: PLANT TEXT 3.7.8 Title: MAINE 5 04/27/2012 SYSTEMS RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) SYSTEM AND THE ATE HEAT SINK (UHS)2 05/02/2008 SYSTEMS EMERGENCY SERVICE WATER (ESW) SYSTEM 1 01/08/2010 SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM 0 11/18/2002 SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM 1 10/04/2007 SYSTEMS MAIN CONDENSER OFFGAS 3 01/25/2011 SYSTEMS MAIN TURBINE BYPASS SYSTEM 1 10/04/2007 SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL 0 05/06/2009 TURBINE PRESSURE REGULATION SYSTEM TEXT 3.8.1 8 05/06/2009 Title: ELECTRICAL POWER SYSTEMS AC SOURCES -OPERATING TEXT 3.8.2 0 11/18/2002 Title: ELECTRICAL POWER SYSTEMS AC SOURCES -SHUTDOWN Page~ of 8 Report Date: 02/20/14 Page 6 of 8 Report Date: 02/20/14 SSES MANUAL.Manual Name: TSB2 Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.8.3 Title: ELECTRICAL 4 10/23/2013 POWER SYSTEMS DIESEL FUEL OIL LUBE OIL AND STARTING AIR TEXT 3.8.4 Title: ELECTRICAl TEXT 3.8.5 Title: ELECTRICAL TEXT 3.8.6 Title: ELECTRICAl TEXT 3.8.7 Title: ELECTRICAL TEXT 3.8.8 Title: ELECTRICAl TEXT 3.9.1 Title: REFUELING TEXT 3.9.2 Title: REFUELING TEXT 3.9.3 Title: REFUELING TEXT 3.9.4 Title: REFUELING TEXT 3.9.5 Title: REFUELING 3 01/19/2009 POWER SYSTEMS DC SOURCES -OPERATING 1 12/14/2006 POWER SYSTEMS DC SOURCES -SHUTDOWN 1 12/14/2006 POWER SYSTEMS BATTERY CELL PARAMETERS 4 04/27/2012 POWER SYSTEMS DISTRIBUTION SYSTEMS -OPERATING 0 11/18/2002 POWER SYSTEMS DISTRIBUTION SYSTEMS -SHUTDOWN 0 11/18/2002 OPERATIONS REFUELING EQUIPMENT INTERLOCKS 1 09/01/2010 OPERATIONS REFUEL POSITION ONE-ROD-OUT INTERLOCK 0 11/18/2002 OPERATIONS CONTROL ROD POSITION 0 11/18/2002 OPERATIONS CONTROL ROD POSITION INDICATION 0 11/18/2002 OPERATIONS CONTROL ROD OPERABILITY

-REFUELING TEXT 3.9.6 1 10/04/2007 Title: REFUELING OPERATIONS REACTOR PRESSURE VESSEL (RPV) WATER LEVEL Page7 of .~ Report Date: 02/20/14 Page 7 of 8 Report Date: 02/20/14 SSES .MANUAL Manual Name: TSB2 Manual Title: TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.9.7 0 11/18/2002 Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) -HIGH WATER LEVEL TEXT 3.9.8 0 11/18/2002 Title: REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) -LOW WATER LEVEL TEXT 3.10.1 Title: SPECIAL TEXT 3.10.2 Title: SPECIAL TEXT 3.10.3 Title: SPECIAL TEXT 3.10.4 Title: SPECIAL TEXT 3.10.5 Title: SPECIAL TEXT 3.10.6 Title: SPECIAL TEXT 3.10.7 Title: SPECIAL TEXT 3.10.8 Title: SPECIAL OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS 1 01/23/2008 INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION 0 11/18/2002 REACTOR MODE SWITCH INTERLOCK TESTING 0 11/18/2002 SINGLE CONTROL ROD WITHDRAWAL

-HOT SHUTDOWN 0 11/18/2002 SINGLE CONTROL ROD WITHDRAWAL

-COLD SHUTDOWN 0 11/18/2002 SINGLE CONTROL ROD DRIVE (CRD) REMOVAL -REFUELING 0 11/18/2002 MULTIPLE CONTROL ROD WITHDRAWAL

-REFUELING 1 03/24/2005 CONTROL ROD TESTING -OPERATING 2 04/09/2007 SHUTDOWN MARGIN (SDM) TEST -REFUELING Page~ of 8 Report Date: 02/20/14 Page 8 of .8 Report Date: 02/20/14 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision TOC Table of Contents 20 B 2.0 SAFETY LIMITS BASES Page TS / B 2.0-1 1 Pages TS / B 2.0-2 and TS / B 2.0-3 4 Page TS / B 2.0-4 6 Pages TS / B 2.0-5 through TS / B 2.0-8 1 B 3.0 LCO AND SR APPLICABILITY BASES Page TS / B 3.0-1 1 Pages TS / B 3.0-2 through TS / B 3.0-4 0 Pages TS / B-3.0-5 through TS / B 3.0-7 1 Page TS / B 3.0-8 3 Pages TS / B 3.0-9 through Page TS / B 3.0-11 2 Page TS / B 3.0-1 la 0 Page TS / B 3.0-12 1 Pages TS / B 3.0-13 through TS / B 3.0-15 2 Pages TS / B 3.0-16 and TS / B 3.0-17 0 B 3.1 REACTIVITY CONTROL BASES Pages B 3.1-1 through B 3.1-4 0 Page TS / B 3.1-5 1 Pages TS / B 3.1-6 and TS / B 3.1-7 2 Pages B 3.1-8 through B 3.1-13 0 Page TS / B 3.1-14 1 Page TS / B 3.1-15 0 Page TS / B 3.1-16 1 Pages TS / B 3.1-17 through TS / B 3.1-19 0 Pages TS / B 3.1-20 and TS / B 3.1-21 1 Page TS / B 3.1-22 0 Page TS / B 3.1-23 1 Page TS / B 3.1-24 0 Pages TS / B 3.1-25 through TS / B 3.1-27 1 Page TS / B 3.1-28 2 Page TS / 3.1-29 1 Pages B 3.1-30 through B 3.1-33 0 Pages TS / B 3.1.34 through TS / B 3.1-36 1 Pages TS / B 3.1-37 and TS / B 3.1-38 2 Pages TS / B 3.1-39 and TS / B 3.1-40 2 Page TS / B 3.1-40a 0 Page TS / B 3.1-41 1 Page TS / B 3.1-42 2 SUSQUEHANNA

-UNIT 2 TS/BLOES-1 Revision 117 SUSQUEHANNA

-UNIT 2 TS / B LOES-1 Revision 117 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Pages TS / B 3.1-43 1 Page TS / B 3.1-44 0 Page TS / B 3.1-45 3 Page TS / B 3.1-46 0 Page TS / B 3.1-47 1 Pages TS / B 3.1-48 and TS / B 3.1-49 1 Page B 3.1-50 0 Page TS / B 3.1-51 3 B 3.2 POWER DISTRIBUTION LIMITS BASES Pages TS / B 3.2-1 and TS / B 3.2-2 2 Page TS / B 3.2-3 4 Page TS / B 3.2-4 1 Page TS / B 3.2-5 3 Page TS / B 3.2-6 4 Page TS / B 3.2-7 3 Pages TS / B 3.2-8 and TS / B 3.2-9 4 Pages TS / B 3.2-10 through TS / B 3.2-12 2 Page TS / B 3.2-13 1 B 3.3 INSTRUMENTATION Pages TS / B 3.3-1 through TS / B 3.3-4 1 Page TS / B 3.3-5 2 Page TS / B 3.3-6 1 Page TS / B 3.3-7 3 Page TS / B 3.3-8 4 Pages TS / B 3.3-9 through TS / B 3.3-13 3 Page TS / B 3.3-14 4 Pages TS / B 3.3-15 and TS / B 3.3-16 2 Pages TS / B 3.3-17 through TS / B 3.3-21 3 Pages TS / B 3.3-22 through TS / B 3.3-27 2 Page TS / B 3.3-28 3 Page TS / B 3.3-29 4 Pages TS / B 3.3-30 and TS / B 3.3-31 3 Pages TS / B 3.3-32 and TS / B 3.3-33 4 Page TS / B 3.3-34 2 Page TS / B 3.3-34a 1 Pages TS / B 3.3-34b through TS / B 3.3-34d 0 Page TS / B 3.3-34e 1 Pages TS / B 3.3-34f through TS / B 3.3-34i 0 Pages TS / B 3.3-35 and TS / B 3.3-36 2 Pages TS / B 3.3-37 and TS / B 3.3-38 1 SUSQUEHANNA

-UNIT 2 TS/BLOES-2 Revision 117 SUSQUEHANNA

-UNIT 2 TS / B LOES-2 Revision 117 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Page TS / B 3.3-39 2 Pages TS / B 3.3-40 through TS / B 3.3-43 2 Pages TS / B 3.3-44 through TS / B 3.3-54 3 Pages TS / B 3.3-54a through TS / B 3.3-54e 0 Page TS / B 3.3-55 2 Page TS / B 3.3-56 0 Page TS / B 3.3-57 1 Page TS / B 3.3-58 0 Page TS / B 3.3-59 1 Page TS / B 3.3-60 0 Page TS / B 3.3-61 1 Pages TS / B 3.3-62 and TS / B 3.3-63 0 Pages TS / B 3.3-64 and TS / B 3.3-65 2 Page TS / B 3.3-66 4 Page TS / B 3.3-67 3 Page TS / B 3.3-68 4 Page TS / B 3.3.69 5 Page TS / B 3.3-70 4 Page TS / B 3.3-71 3 Pages TS / B 3.3-72 and TS / B 3.3-73 2 Page TS / B 3.3-74 3 Page TS / B 3.3-75 2 Pages TS / B 3.3-75a and TS / B 3.3-75 b 6 Page TS / B 3.3-75c 6 Pages B 3.3-76 and TS / B 3.3-77 0 Page TS / B 3.3-78 1 Pages B 3.3-79 through 8 3.3-81 0 Page TS / B 3.3-82 1 Page B 3.3-83 0 Pages TS / B 3.3-84 and TS / B 3.3-85 1 Page 3.3-86 0 Page TS / B 3.3-87 1 Page B 3.3-88 0 Page TS / B 3.3-89 1 Pages B 3.3-90 and B 3.3-91 0 Pages TS / B 3.3-92 through TS / B 3.3-103 1 Page TS / B 3.3-104 3 Pages TS / B 3.3-105 and TS /B 3.3-106 1 Page TS / B 3.3-107 2 Page TS / B 3.3-108 1 Page TS / B 3.3-109 2 Pages TS / B 3.3-110 through TS / B 3.3-112 1 Page TS / B 3.3-113 2 SUSQUEHANNA

-UNIT 2 TS / B LOES-3 Revision 117 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Page TS / B 3.3-114 1 Page TS / B 3.3-115 2 Page TS / B 3.3-116 3 Pages TS / B 3.3-117 and TS / B 3.3-118 2 Pages TS / B 3.3-119 through TS / B 3.3-120 1 Pages TS / B 3.3-121 and TS / B 3.3-122 2 Page TS / B 3.3-123 1 Page TS / B 3.3-124 2 Page TS / B 3.3-124a 0 Page TS / B 3.3-125 1 Page TS / B 3.3-126 2 Page TS / 8 3.3-127 3 Page TS / B 3.3-128 2 Pages TS / B 3.3-129 through TS / B 3.3-131 1 Page TS / B 3.3-132 2 Pages TS / B 3.3-133 and TS / 83.3-134 1 Pages B 3.3-135 through B 3.3-137 0 Page TS / 8 3.3-138 1 Pages B 3.3-139 through B 3.3-149 0 Pages TS/B 3.3-150 and TS / B 3.3-151 1 Pages TS / B 3.3-152 through TS / B 3.3-154 2 Page TS / 8 3.3-155 1 Pages TS / B 3.3-156 through TS / B 3.3-158 2 Pages TS / B 3.3-159 through TS / B 3.3-161 1 Page TS / 8 3.3-162 1 Pages TS / B 3.3-163 through TS / B 3.3-166 2 Pages TS / 8 3.3-167 and TS / B 3.3-168 1 Pages TS / B 3.3-169 and TS / B 3.3-170 2 Pages TS / B 3.3-171 through TS / B 3.3-177 1 Page TS / 8 3.3-178 2 Page TS / B 3.3-179 3 Page TS / B 3.3-179a 2 Page TS / B 3.3-180 1 Page TS / 8 3.3-181 3 Page TS / 8 3.3-182 1 Page TS / 8 3.3-183 2 Page TS/ 8 3.3-184 1 Page TS / 8 3.3-185 4 Page TS / B 3.3-186 1 Pages TS / 8 3.3-187 and TS / 83.3-188 2 Pages TS / B 3.3-189 through TS / B 3.3-191 1 SUSQUEHANNA

-UNIT 2 TS/B LOES-4 Revision 117 SUSQUEHANNA

-UNIT 2 TS / B] LOES-4 Revision 117 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Page TS / B 3.3-192 0 Page TS / B 3.3-193 1 Pages TS / B 3.3-194 and TS / B 3.3-195 0 Page TS / B 3.3-196 2 Pages TS / B 3.3-197 through TS / B 3.3-205 0 Page TS / B 3.3-206 1 Pages B 3.3-207 through B 3.3-209 0 Page TS / B 3.3-210 1 Page TS / B 3.3-211 2 Pages TS / B 3.3-212 and TS / B 3.3-213 1 Pages B 3.3-214 through B 3.3-220 0 B 3.4 REACTOR COOLANT SYSTEM BASES Pages TS / B 3.4-1 and TS / B 3.4-2 2 Pages TS / B 3.4-3 through TS / B 3.4-5 4 Pages TS / B 3.4-6 through TS / B 3.4-9 3 Page TS / B 3.4-10 1 Pages TS / B 3.4-11 and TS / B 3.4-12 0 Page TS / B 3.4-13 2 Page TS / B 3.4-14 1 Page TS / B 3.4-15 2 Pages TS / B 3.4-16 and TS / B 3.4-17 4 Page TS / B 3.4-18 2 Pages B 3.4-19 through B 3.4-23 0 Pages TS / B 3.4-24 through TS / B 3.4-27 0 Page TS / B 3.4-28 1 Page TS / B 3.4-29 3 Page TS / B 3.4-30 2 Page TS / B 3.4-31 1 Pages TS / B 3.4-32 and TS / B 3.4-33 2 Page TS / B 3.4-34 1 Page TS / B 3.4-34a 0 Pages TS / B 3.4-35 and TS / B 3.4-36 1 Page TS / B 3.4-37 2 Page B 3.4-38 1 Pages B 3.4-39 and B 3.4-40 0 Page TS / B 3.4-41 2 Pages TS / B 3.4-42 through TS/ B 3.4-45 0 Page TS / B 3.4.4-46 1 Pages TS / B 3.4.4-47 and TS / B 3.4.4-48 0 Page TS / B 3.4-49 3 Pages TS / B 3.4-50 through TS / B 3.4-52 2 Page TS / B 3.4-53 1 Pages TS / B 3.4-54 through TS / B 3.4-57 2 Pages TS / B 3.4-58 through TS / B 3.4-60 1 SUSQUEHANNA

-UNIT 2 TS / B LOES-5 Revision 117 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision B 3.5 ECCS AND RCIC BASES Pages TS / B 3.5-1 and TS / B 3.5-2 1 Pages TS / B 3.5-3 through TS / B 3.5-6 2 Pages TS / B 3.5-7 through TS / B 3.5-10 1 Pages TS / B 3.5-11 and TS / B 3.5-12 2 Pages TS / B 3.6-13 and TS / B 3.5-14 1 Pages TS / B 3.5-15 and TS / B.3.5-16 2 Page TS / B 3.5-17 3 Page TS / B 3.5-18 1 Pages B 3.5-19 through B 3.5-24 0 Pages TS / B 3.5-25 through TS / B 3.5-27 1 Page TS / B 3.5-28 0 Page TS / B 3.5-29 1 Pages TS / B 3.5-30 and TS / B 3.5-31 0 B 3.6 CONTAINMENT SYSTEMS BASES Page TS / B 3.6-1 2 Page TS / B 3.6-1a 3 Page TS / B 3.6-2 4 Page TS / B 3.6-3 3 Page TS / B 3.6-4 4 Page TS / B 3.6-5 3 Page TS / B 3.6-6 4 Pages TS / B 3.6-6a and TS / B 3.6-6b 3 Page TS / B 3.6-6c 0 Page B 3.6-7 0 Page TS / 3.6-8 1 Pages B 3.6-9 through B 3.6-14 0 Page TS / B 3.6-15 4 Page TS / B 3.6-15a 0 Page TS / B 3.6-15b 3 Pages TS / B 3.6-16 and TS / B 3.6-17 3 Page TS / B 3.6-17a 1 Pages TS / B 3.6-18 and TS / B 3.6-19 1 Page TS / B 3.6-20 2 Page TS / B 3.6-21 3 Pages TS / B 3.6-21a and TS / B 3.6-21b 0 Pages TS / B 3.6-22 and TS / B 3.6-23 2 Pages TS / B 3.6-24 and TS / B 3.6-25 1 Pages TS / B 3.6-26 and TS / B 3.6-27 3 Page TS / B 3.6-28 7 Page TS / B 3.6-29 5 Page TS / B 3.6-29a 0 Page TS / B 3.6-30 2 Page TS / B 3.6-31 3 SUSQUEHANNA

-UNIT 2 TS / B LOES-6 Revision 117 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Pages TS / B 3.6-32 and TS / B 3.6-33 2 Page TS / B 3.6-34 1 Page TS / B 3.6-35 3 Pages TS / B 3.6-36 and TS / B 3.6-37 2 Page TS / B 3.6-38 3 Page TS / B 3.6-39 7 Page TS / B 3.6-39a 0 Page TS / B 3.6-40 1 Pages B 3.6-41 and B 3.6-42 0 Pages TS / B 3.6-43 and TS / B 3.6-44 1 Page TS / B 3.6-45 2 Pages TS / B 3.6-46 through TS / B 3.6-50 1 Page TS / B 3.6-51 2 Pages B 3.6-52 through B 3.6-55 0 Pages TS / B 3.6-56 and TS / B 3.6-57 2 Pages B 3.6-58 through B 3.6-62 0 Pages TS / B 3.6-63 and TS / B 3.6-64 1 Pages B 3.6-65 through B 3.6-68 0 Pages B 3.6-69 through B 3.6-71 1 Page TS / B 3.6-72 2 Pages TS / B 3.6-73 and TS / B 3.6-74 1 Pages B 3.6-75 and B 3.6-76 0 Page TS / B 3.6-77 1 Pages B 3.6-78 and B 3.6-79 0 Page TS / B 3.6-80 1 Pages TS / B 3.6-81 and TS / B 3.6-82 0 Page TS / B 3.6-83 4 Page TS / B 3.6-84 2 Page TS / B 3.6-85 4 Page TS / B 3.6-86 through TS / B 3.6-87a 2 Page TS / B 3.6-88 5 Page TS / B 3.6-89 3 Page TS / B 3.6-89a 0 Pages TS / B 3.6-90 and TS / B 3.6-91 3 Page TS / B 3.6-92 2 Pages TS / B 3.6-93 through TS / B 3.6-95 1 Page TS / B 3.6-96 2 Page TS / B 3.6-97 1 Page TS / B 3.6-98 2 Page TS / B 3.6-99 6 Page TS / B 3.6-99a 5 Page TS / B 3.6-99b 3 Pages TS / B 3.6-100 and TS / B 3.6-101 1 Pages TS / B 3.6-102 and TS / B 3.6-103 2 SUSQUEHANNA-UNIT2 TS / B LOES-7 Revision 117 SUSQUEHANNA

-UNIT 2 TS / B LOES-7 Revision 117 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Page TS / B 3.6-104 3 Page TS / B 3.6-105 2 Page TS / B 3.6-106 3 B 3.7 PLANT SYSTEMS BASES Page TS / B 3.7-1 3 Page TS / B 3.7-2 4 Pages TS / B 3.7-3 through TS / B 3.7-5 3 Page TS / B 3.7-5a 2 Page TS / B 3.7-6 4 Page TS / B 3.7-6a 3 Page TS / B 3.7-6b 2 Page TS / B 3.7-6c 3 Page TS / B 3.7-7 3 Page TS / B 3.7-8 2 Pages B 3.7-9 through B 3.7-11 0 Pages TS / B 3.7-12 and TS / B 3.7-13 2 Pages TS / B 3.7-14 through TS / B 3.7-18 3 Page TS / B 3.7-18a 1 Pages TS / B 3.7-18b through TS / B 3.7-18e 0 Pages TS / B 3.7-19 through TS / B 3.7-24 1 Pages TS / B 3.7-25 and TS / B 3.7-26 0 Page TS / B 3.7-27 4 Pages TS / B 3.7-28 and TS / B 3.7-29 3 Pages TS / B 3.7-30 and TS / B 3.7-31 1 Page TS / B 3.7-32 0 Page TS / B 3.7-33 1 Pages TS / B 3.7-34 through TS / B 3.7-37 0 B 3.8 ELECTRICAL POWER SYSTEMS BASES Page TS / B 3.8-1 1 Pages B 3.8-2 and B 3.8-3 0 Page TS / B 3.8-4 1 Pages TS / B 3.8-4a and TS / 8 3.8-4b 0 Pages TS / 8 3.8-5 and TS / 8 3.8-6 3 Page TS / 8 3.8-6a 1 Pages 8 3.8-7 and B 3.8-8 0 Page TS / 8 3.8-9 2 Pages TS / B 3.8-10 and TS / 8 3.8-11 1 Pages 8 3.8-12 through B 3.8-18 0 Page TS / B 3.8-19 1 Pages 8 3.8-20 through B 3.8-22 0 Page TS / 8 3.8-23 1 Page 8 3.8-24 0 Pages TS / B 3.8-25 and TS / 8 3.8-26 1 SUSQUEHANNA

-UNIT 2 TS / B] LOES-8 Revision 117 SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)Section Title Revision Pages B 3.8-27 through B 3.8-35 0 Page TS / B 3.8-36 1 Page TS / B 3.8-37 0 Page TS / B 3.8-38 1 Pages TS / B 3.8-39 through TS / B 3.8-46 0 Page TS / B 3.8-47 3 Pages TS / B 3.8-48 through TS / B 3.8-50 0 Pages TS / B 3.8-51 and TS / B 3.8-52 3 Page TS / B 3.8-53 1 Page TS / B 3.8-54 0 Page TS / B 3.8-55 1 Pages TS / B 3.8-56 through TS / B 3.8-59 2 Pages TS / B 3.8-60 through TS / B 3.8-64 3 Page TS / B 3.8-65 4 Page TS / B 3.8-66 5 Pages TS / B 3.8-67 and TS / B 3.8-68 4 Page TS / B 3.8-69 5 Pages TS / B 3.8-70 through TS / B 3.8-83 1 Pages TS / B 3.8-83A through TS / B 3.8-83D 0 Pages B 3.8-84 through B 3.8-85 0 Page TS / B 3.8-86 1 Page TS / B 3.8-87 2 Pages TS / B 3.8-88 and TS / B 3.8-89 1 Page TS / B 3.8-90 2 Pages TS / B 3.8-91 through TS / B 3.8-93 1 Pages B 3.8-94 through B 3.8-99 0 B 3.9 REFUELING OPERATIONS BASES Pages TS / B 3.9-1 and TS / B 3.9-2 1 Pages TS / B 3.9-2a through TS / B 3.9-5 1 Pages TS / B 3.9-6 through TS / B 3.9-8 0 Pages B 3.9-9 through B 3.9-18 0 Pages TS / B 3.9-19 through TS / B 3.9-21 1 Pages B 3.9-22 through B 3.9-30 0 B 3.10 SPECIAL OPERATIONS BASES Page TS / B 3.10-1 2 Pages TS / B 3.10-2 through TS / B 3.10-5 1 Pages B 3.10-6 through B 3.10-32 0 Page TS / B 3.10-33 2 Page B 3.10-34 0 Page B 3.10-35 1 Pages B 3.10-36 and B 3.10-37 0 Page B 3.10-38 1 Page TS / B 3.10-39 2 TSB2 Text LOES.doc 2/11/2014 SUSQUEHANNA

-UNIT 2 TS / B LOES-9 Revision 117 PPL Rev. 4 RCS Leakage Detection Instrumentation B 3.4.6 B 3.4 REACTOR COOLANT SYSTEM (RCS)B 3.4.6 RCS Leakage Detection Instrumentation BASES BACKGROUND GDC 30 of 10 CFR 50, Appendix A (Ref. 1), requires means for detecting and, to the extent practical, identifying the location of the source of RCS LEAKAGE. Regulatory Guide 1.45, Revision 0, (Ref. 2) describes acceptable methods for selecting leakage detection systems.Limits on LEAKAGE from the reactor coolant pressure boundary (RCPB)are required so that appropriate action can be taken before the integrity of the RCPB is impaired (Ref. 2). Leakage detection systems for the RCS are provided to alert the operators when leakage rates above normal background levels are detected and also to supply quantitative measurement of leakage rates. The Bases for LCO 3.4.4, "RCS Operational LEAKAGE," discuss the limits on RCS LEAKAGE rates.Systems for separating the LEAKAGE of an identified source from an unidentified source are necessary to provide prompt and quantitative information to the operators to permit them to take immediate corrective action.LEAKAGE from the RCPB inside the drywell is detected by at least one of two or three independently monitored variables, such as sump level changes and drywell gaseous and particulate radioactivity levels. The primary means of quantifying LEAKAGE in the drywell is the drywell floor drain sump monitoring system which consists of two drywell floor drain sump level Channels.

Both Channels are required to be Operable to satisfy the LCO.The drywell floor drain sump monitoring system monitors the LEAKAGE collected in the floor drain sump. This unidentified LEAKAGE consists of LEAKAGE from control rod drives, valve flanges or packings, floor drains, the Closed Cooling Water System, and drywell air cooling unit condensate drains, and any LEAKAGE not collected in the drywell equipment drain tank.The level of each drywell sump is continuously recorded in the Main Control Room. The change in (continued)

SUSQUEHANNA-UNIT 2 TS / B 3.4-30 Revision 2 PPL Rev. 4 RCS Leakage Detection Instrumentation B 3.4.6 BASES BACKGROUND (continued) sump level per unit time determines the leak rate and is calculated from the recorder.The floor drain sump level indicators have switches that start and stop the sump pumps when required.

If the sump fills to the high high level setpoint, an alarm sounds in the control room.The primary containment air monitoring systems continuously monitor the primary containment atmosphere for airborne particulate and gaseous radioactivity.

A sudden increase of radioactivity, which may be attributed to RCPB steam or reactor water LEAKAGE, is annunciated in the control room.APPLICABLE SAFETY ANALYSES A threat of significant compromise to the RCPB exists if the barrier contains a crack that is large enough to propagate rapidly. LEAKAGE rate limits are set low enough to detect the LEAKAGE emitted from a single crack in the RCPB (Refs. 3 and 4). The allowed LEAKAGE rates are well below the rates predicted for critical crack sizes (Ref. 6).Therefore, these limits provide adequate response before a significant break in the RCPB can occur.RCS leakage detection instrumentation satisfies Criterion 1 of the NRC Policy Statement (Ref. 7).LCO This LCO requires instruments of diverse monitoring principles to be OPERABLE to provide confidence that small amounts of unidentified LEAKAGE are detected in time to allow actions to place the plant in a safe condition, when RCS LEAKAGE indicates possible RCPB degradation.

The LCO requires two instruments to be OPERABLE.The drywell floor drain sump monitoring system is required to quantify the unidentified LEAKAGE rate from the RCS. Thus, for the system to be considered OPERABLE, the sump level monitoring portion of the system must be OPERABLE and capable of determining the leakage rate. The identification of an increase in unidentified LEAKAGE will be delayed by the time required for the unidentified LEAKAGE to travel to the drywell floor drain sump and it may take longer than one hour to detect a 1 gpm increase in unidentified LEAKAGE, depending on the origin and magnitude of the LEAKAGE. This sensitivity is acceptable for primary containment sump monitor OPERABILITY.(continued)

SUSQUEHANNA

-UNIT 2 TS / B 3.4-31 Revision 1 PPL Rev. 4 RCS Leakage Detection Instrumentation B 3.4.6 BASES LCO (continued)

The reactor coolant contains radioactivity that, when released to the primary containment, can be detected by the gaseous or particulate primary containment atmospheric radioactivity monitor. Only one of the two detectors is required to be OPERABLE.

Radioactivity detection systems are included for monitoring both particulate and gaseous activities because of their sensitivities and rapid responses to RCS LEAKAGE, but have recognized limitations.

Reactor coolant radioactivity levels will be low during initial reactor startup and for a few weeks thereafter, until activated corrosion products have been formed and fission products appear from fuel element cladding contamination or cladding defects. If there are few fuel element cladding defects and low levels of activation products, it may not be possible for the gaseous or particulate primary containment atmospheric radioactivity monitors to detect a 1 gpm increase within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during normal operation.

However, the gaseous or particulate containment primary atmospheric radioactivity monitor is OPERABLE when it is capable of detecting a 1 gpm increase in unidentified LEAKAGE within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> given an RCS activity equivalent to that assumed in the design calculations for the monitors (Reference 6).The LCO is satisfied when monitors of diverse measurement means are available.

Thus, the drywell floor drain sump monitoring system, in combination with a gaseous or particulate primary containment atmospheric radioactivity monitor provides an acceptable minimum.APPLICABILITY In MODES 1, 2, and 3, leakage detection systems are required to be OPERABLE to support LCO 3.4.4. This Applicability is consistent with that for LCO 3.4.4.ACTIONS A.1 With the drywell floor drain sump monitoring system inoperable, the primary containment atmospheric activity monitor will provide indication of changes in leakage.With the drywell floor drain sump monitoring system inoperable, operation may continue for 30 days. However, RCS unidentified and total LEAKAGE is still required to be determined every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (SR 3.4.4.1).The 30 day Completion Time of Required Action A.1 is acceptable, based on operating experience, considering the multiple forms of leakage detection that are still available.(continued)

SUSQUEHANNA-UNIT2 TS / B 3.4-32 Revision 2 PPL Rev. 4 RCS Leakage Detection Instrumentation B 3.4.6 BASES ACTIONS B.1 and B.2 (continued)

With both gaseous and particulate primary containment atmospheric monitoring channels inoperable, grab samples of the primary containment atmosphere must be taken and analyzed to provide periodic leakage information.

Provided a sample is obtained and analyzed once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the plant may be operated for up to 30 days to allow restoration of at least one of the required monitors.The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval provides periodic information that is adequate to detect LEAKAGE. The 30 day Completion Time for restoration recognizes that at least one other form of leakage detection is available.

C.1, C.2 and C.3 With the drywell floor drain sump monitoring system inoperable, the only means of detecting LEAKAGE is the primary containment atmospheric gaseous radiation monitor. A Note clarifies this applicability of the Condition.

The primary containment atmospheric gaseous radiation monitor typically cannot detect a 1 gpm leak within one hour when RCS activity is low. In addition, this configuration does not provide the required diverse means of leakage detection.

Indirect methods of monitoring RCS leakage must be implemented.

Grab samples of the primary containment atmosphere must be taken and analyzed and monitoring of RCS leakage by administrative means must be performed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to provide alternate periodic information.

Administrative means of monitoring RCS leakage include monitoring and trending parameters that may indicate an increase in RCS leakage. There are diverse alternative mechanisms from which appropriate indicators may be selected based on plant conditions.

It is not necessary to utilize all of these methods, but a method or methods should be selected considering-the current plant conditions and historical or expected sources of unidentified leakage. The administrative methods are primary containment pressure, temperature, Component Cooling Water System outlet temperatures and makeup, Reactor Recirculation System pump seal pressure and temperature and motor cooler temperature indications, Drywell cooling fan outlet temperatures, Reactor Building Chiller amperage, Control Rod Drive System flange temperatures, Safety Relief Valve tailpipe temperature, flow, pressure, or other approved methods.These indications, coupled with the atmospheric grab samples, are sufficient to alert the operating staff to an unexpected increase in unidentified LEAKAGE.(continued)

SUSQUEHANNA

-UNIT 2 TS / B 3.4-33 Revision 2 PPL Rev. 4 RCS Leakage Detection Instrumentation B 3.4.6 BASES ACTIONS C.1. C.2 and C.3 (continued)

The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval is sufficient to detect increasing RCS leakage. The Required Action provides 7 days to restore another RCS leakage monitor to OPERABLE status to regain the intended leakage detection diversity.

The 7 day Completion Time ensures that the plant will not be operated in a degraded configuration for a lengthy time period.D.1 and D.2 If any Required Action of Condition A, B or C cannot be met within the associated Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />.The allowed Completion Times are reasonable, based on operating experience, to perform the actions in an orderly manner and without challenging plant systems.E.1 With all required monitors inoperable, no required automatic means of monitoring LEAKAGE are available, and immediate plant shutdown in accordance with LCO 3.0.3 is required.SURVEILLANCE REQUIREMENTS This SR is for the performance of a CHANNEL CHECK of the required primary containment atmospheric monitoring system. The check gives reasonable confidence that the channel is operating properly.

The Frequency of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is based on instrument reliability and is reasonable for detecting off normal conditions.

SR 3.4.6.2 This SR is for the performance of a CHANNEL FUNCTIONAL TEST of the required RCS leakage detection instrumentation.

The test ensures that the monitors can perform their function in the desired manner. The Frequency of 31 days considers instrument reliability, and operating experience has shown it proper for detecting degradation.(continued)

SUSQUEHANNA

-UNIT 2 TS / B 3.4-34 Revision 1 PPL Rev. 4 RCS Leakage Detection Instrumentation B 3.4.6 BASES SURVEILLANCE SR 3.4.6.3 REQUIREMENTS (continued)

This SR is for the performance of a CHANNEL CALIBRATION of required leakage detection instrumentation channels.

The calibration verifies the accuracy of the instrument string, including the instruments located inside containment.

The Frequency of 24 months is a typical refueling cycle and considers channel reliability.

REFERENCES

1. 10 CFR 50, AppendixA, GDC 30.2. Regulatory Guide 1.45, Revision 0, "Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973.3. GEAP-5620, April 1968.4. NUREG-75/067, October 1975.5. FSAR, Section 5.2.5.4.6. FSAR, Section 5.2.5.1.2 7. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).SUSQUEHANNA

-UNIT 2 TS I B 3.4-34a Revision 0

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