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SSES MANUAL Manual Name:

TSB2 Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL Table Of Contents Issue Date:

07/09/2010 Procedure Name Rev TEXT LOES 100

Title:

LIST OF EFFECTIVE SECTIONS Issue Date 07/09/2010 Change ID Change Number TEXT TOC

Title:

TABLE OF CONTENTS 16 03/10/2010 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

CONTROL SYSTEMS 03/24/2005 ROD PATTERN CONTROL Pagel of 8

Report Date: 07/09/10 Page 1 of

.8 Report Date: 07/09/10

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 4

05/06/2009

Title:

POWER DISTRIBUTION LIMITS AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)

TEXT 3.2.2 3

05/06/2009

Title:

POWER DISTRIBUTION 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 4

05/06/2009

Title:

INSTRUMENTATION 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 1

05/06/2009

Title:

INSTRUMENTATION FEEDWATER -

MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 7

10/27/2008

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: 07/09/10

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

Title:

INSTRUMENTATION 4

08/20/2009 EMERGENCY CORE COOLING SYSTEM (ECCS)

INSTRUMENTATION TEXT 3.3.5.2 0

11/18/2002

Title:

INSTRUMENTATION REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM INSTRUMENTATION TEXT 3.3.6.1

Title:

INSTRUMENTATION 4

05/06/2009 PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.6.2 3

10/27/2008

Title:

INSTRUMENTATION SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.7.1

Title:

INSTRUMENTATION INSTRUMENTATION 2

10/27/2008 CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS)

SYSTEM TEXT 3.3.8.1 3

12/17/2007

Title:

INSTRUMENTATION LOSS OF POWER (LOP)

INSTRUMENTATION TEXT 3.3.8.2 0

11/18/2002

Title:

INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS)

ELECTRIC POWER MONITORING TEXT 3.4.1

Title:

REACTOR COOLANT 3

04/09/2007 SYSTEM (RCS)

RECIRCULATION LOOPS OPERATING TEXT 3.4.2 1

05/06/2009

Title:

REACTOR COOLANT SYSTEM (RCS)

JET PUMPS TEXT 3.4.3

Title:

REACTOR COOLANT TEXT 3.4.4

Title:

REACTOR COOLANT 2

05/06/2009 SYSTEM (RCS)

SAFETY/RELIEF VALVES (S/RVS) 0 11/18/2002 SYSTEM (RCS)

RCS OPERATIONAL LEAKAGE Page~

of ~

Report Date: 07/09/10 Page 3 of 8

Report Date: 07/09/10

SSES MANUJAL Manual Name:

TSB2 Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3. 4.5

Title:

REACTOR COOLANT 3

SYSTEM (RCS) 03/10/2010 RCS PRESSURE ISOLATION VALVE (PIV)

LEAKAGE TEXT 3.4.6 2

08/20/2009

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 1

SYSTEM (RCS) 0 SYSTEM (RCS) 04/18/2005 RESIDUAL HEAT REMOVAL (RHR)

SHUTDOWN COOLING SYSTEM 11/18/2002 RESIDUAL HEAT REMOVAL (RHR)

SHUTDOWN COOLING SYSTEM0 TEXT 3.4.10 3

05/06/2009

Title:

REACTOR COOLANT SYSTEM (RCS)

RCS PRESSURE AND TEMPERATURE (P/T) LIMITS TEXT 3.4.11 0

11/18/2002

Title:

REACTOR COOLANT SYSTEM (RCS)

REACTOR STEAM DOME PRESSURE TEXT 3. 5. 1 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)

TEXT 3.6.1.1 3

05/06/2009

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT TEXT 3.6.1.2 1

05/06/2009

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCK Page4 of 8 Report Date: 07/09/10 Page 4 of 8

Report Date: 07/09/10

S-ES 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 3.6.2.4

Title:

CONTAINMENT TEXT 3.6.3.1

Title:

CONTAINMENT TEXT 3.6.3.2

Title:

CONTAINMENT TEXT 3.6.3.3

Title:

CONTAINMENT TEXT 3.6.4.1

Title:

CONTAINMENT 11 04/14/2010 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 0

11/18/2002 SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION 7

10/04/2007 SYSTEMS SECONDARY CONTAINMENT Page ~

of 8

Report Date: 07/09/10 Page5 of 8 Report Date: 07/09/10

SSES MANUAL Manual Name:

TSB2 Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3.6.4.2 3

03/10/2010

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 3.8.1 4

04/05/2010 SYSTEMS RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW)

SYSTEM AND THE

\\TE 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 2

05/06/2009 SYSTEMS MAIN TURBINE BYPASS SYSTEM 1

10/04/2007 SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL 8

05/06/2009

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES -

OPERATING TEXT 3.7.8 0

05/06/2009

Title:

MAINE TURBINE PRESSURE REGULATION SYSTEM TEXT 3.8.2 0

11/18/2002

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES -

SHUTDOWN Page~

of 8 Report Date: 07/09/10 Page 6 of 8

Report Date: 07/09/10

SSES MANUAL Manual Name:

TSB2 Manual

Title:

TECHNICAL SPECIFICATIONS BASES UNIT 2 MANUAL TEXT 3. 8.3

Title:

ELECTRICAL 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 C TEXT 3.9.3

Title:

REFUELING TEXT 3.9.4

Title:

REFUELING TEXT 3.9.5

Title:

REFUELING TEXT 3.9.6

Title:

REFUELING C 2

04/14/2010 POWER SYSTEMS DIESEL FUEL OIL LUBE OIL AND STARTING AIR POWER SYST POWER SYST POWER SYST POWER SYST POWER SYST OPERATIONS DPERATIONS OPERATIONS OPERATIONS OPERATIONS OPERATIONS 3

01/19/2009 PEMS DC SOURCES -

OPERATING 1

12/14/2006

'EMS DC SOURCES -

SHUTDOWN 1

12/14/2006

'EMS BATTERY CELL PARAMETERS 3

03/31/2006

'EMS DISTRIBUTION SYSTEMS -

OPERATING 0

11/18/2002 PEMS DISTRIBUTION SYSTEMS -

SHUTDOWN 0

11/18/2002 REFUELING EQUIPMENT INTERLOCKS 0

11/18/2002 REFUEL POSITION ONE-ROD-OUT INTERLOCK 0

11/18/2002 CONTROL ROD POSITION 0

11/18/2002 CONTROL ROD POSITION INDICATION 0

11/18/2002 CONTROL ROD OPERABILITY -

REFUELING 1

10/04/2007 REACTOR PRESSURE VESSEL (RPV) WATER LEVEL Pagel of 8 Report Date: 07/09/10 Page 7 of.8 Report Date: 07/09/10

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 0

0 Page ~

of 8 Report Date: 07/09/10 Page8 of 8 Report Date: 07/09/10

SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Revision TOC Table of Contents 16 B 2.0 SAFETY LIMITS BASES Page TS / B 2.0-1 1

Pages TS I 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 I B 3.0-4 0

Pages TS / B 3.0-5 through TS / B 3.0-7 1

Page TS I B 3.0-8 3

Pages TS I B 3.0-9 through Page TS / B 3.0-11 2

Page TS / B 3.0-11 a 0

Page TS / B 3.0-12 1

Pages TS I B 3.0-13 through TS / B 3.0-15 2

Pages TS I 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 I 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

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Pages TS / B 3.1.34 through TS / B 3.1-36 1

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Page TS / B 3.1-40a 0

Page TS / B 3.1-41 1

Page TS / B 3.1-42 2

SUSQUEHANNA

- UNIT 2 TSIBLOES-1 Revision 100 SUSQUEHANNA - UNIT 2 TS / B LOES-1 Revision 100

SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section Title Revision Pages TS / B 3.1-43 1

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Pages TS I 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 I 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 I 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 I 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 I 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 I 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 I B 3.3-36 2

Pages TS / B 3.3-37 and TS / B 3.3-38 1

SUSQUEHANNA

- UNIT 2 TSIBLOES-2 Revision 100 SUSQUEHANNA - UNIT 2 TS / B, LOES-2 Revision 100

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 I 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 1

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Pages TS / B 3.3-64 and TS / B 3.3-65 2

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Pages TS / B 3.3-72 and TS / B 3.3-73 2

Page TS I 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 5

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 B 3.3-81 0

Page TS / B 3.3-82 1

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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

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

SUSQUEHANNA - UNIT 2 TS / B LOES-3 Revision 100

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Section Title Revision 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

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Page TS / B 3.3-132 2

Pages TS / B 3.3-133 and TS / B 3.3-134 1

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Pages TS / B 3.3-165 and TS / B 3.3-166 2

Pages TS / B 3.3-167 and TS I B 3.3-168 1

Pages TS I B 3.3-169 and TS I B 3.3-170 2

Pages TS I B 3.3-171 through TS / B 3.3-177 1

Page TS / B 3.3-178 2

Page TS I B 3.3-179 3

Page TS I B 3.3-179a 2

Page TS I B 3.3-180 1

Page TS I B 3.3-181 3

Page TS I B 3.3-182 1

Page TS I B 3.3-183 2

Page TS I B.3.3-184 1

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Page TS / B 3.3-193 1

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Page TS / B 3.3-196 2

SUSQUEHANNA

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Section Title Revision Pages TS / B 3.3-197 through TS / B, 3.3-205 0

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TSB2 Text LOESA=oc 716110 SUSQUEHANNA - UNIT 2 TS / B LOES-9 Revision 100

PPL Rev. 2 RCIC System B 3.5.3 B 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM B 3.5.3 RCIC System BASES BACKGROUND The RCIC System is not part of the ECCS; however, the RCIC System is included with the ECCS section because of their similar functions.

The RCIC System is designed to operate either automatically or manually following reactor pressure vessel (RPV) isolation accompanied by a loss of coolant flow from the feedwater system to provide adequate core cooling and control of the RPV water level. Under these conditions, the High Pressure Coolant Injection (HPCI) and RCIC systems perform similar functions. The RCIC System design requirements ensure that the criteria of Reference 1 are satisfied.

The RCIC System (Ref. 2) consists of a steam driven turbine pump unit, piping, and valves to provide steam to the turbine, as well as piping and valves to transfer water from the suction source to the core via the feedwater system line, where the coolant is distributed within the RPV through the feedwater sparger. Suction piping is provided from the condensate storage tank (CST) and the suppression pool. Pump suction is normally aligned to the CST to minimize injection of suppression pool water into the RPV. However, if the CST water supply is low, an automatic transfer to the suppression pool water source ensures an adequate suction head for the pump and an uninterrupted water supply for continuous operation of the RCIC System. The steam to the turbine is piped from a main steam line upstream of the associated inboard main steam line isolation valve.

The RCIC System is designed to provide core cooling for a wide range of reactor pressures (165 psia to 1225 psia). Upon receipt of an initiation signal, the RCIC turbine accelerates to a specified speed. As the RCIC flow increases, the turbine control valve is automatically adjusted to maintain design flow. Exhaust steam from the RCIC turbine is discharged to the suppression pool. A full flow test line is provided to route water to the CST to allow testing of the RCIC System during normal operation without injecting water into the RPV.

(continued)

SUSQUEHANNA - UNIT 2 TS / B 3.5-25 Revision 1

PPL Rev. 2 RCIC System B 3.5.3 BASES BACKGROUND (continued)

The RCIC pump is provided with a minimum flow bypass line, which discharges to the suppression pool. The valve in this line automatically opens to prevent pump damage due to overheating when other discharge line valves are closed. To ensure rapid delivery of water to the RPV and to minimize water hammer effects, the RCIC System discharge piping is kept full of water. The RCIC System is normally aligned to the CST. The RCIC discharge line is kept full of water using a "keep fill" system supplied by the condensate transfer system.

APPLICABLE SAFETY ANALYSES The function of the RCIC System is to respond to transient events by providing makeup coolant to the reactor. The RCIC System is not an Engineered Safety Feature System and no credit is taken in the safety analyses for RCIC System operation. Based on its contribution to the reduction of overall plant risk, however, the system is included in the Technical Specifications, as required by the NRC Policy Statement (Ref. 4).

LCO The OPERABILITY of the RCIC System provides adequate core cooling such that actuation of any of the low pressure ECCS subsystems is not required in the event of RPV isolation accompanied by a loss of feedwater flow. The RCIC System has sufficient capacity for maintaining RPV inventory during an isolation event.

APPLICABILITY The RCIC System is required to be OPERABLE during MODE 1, and MODES 2 and 3 with reactor steam dome pressure >150 psig, since RCIC is the primary non-ECCS water source for core cooling when the reactor is isolated and pressurized. In MODES 2 and 3 with reactor steam dome pressure *< 150 psig, and in MODES 4 and 5, RCIC is not required to be OPERABLE since the low pressure ECCS injection/spray subsystems can provide sufficient flow to the RPV.

ACTIONS A Note prohibits the application of LCO 3.0.4.b to an inoperable RCIC system. There is an increased risk associated with entering a MODE or other specified condition in the Applicability with an inoperable RCIC system and the provisions of LCO 3.0.4.b, which allow entry into a MODE or other specified condition in the Applicability with the LCO not met after performance of a risk assessment addressing inoperable systems and components, should not be applied in this circumstance.

(continued)

SUSQUEHANNA - UNIT 2 TS / B 3.5-26 Revision 1

PPL Rev. 2 RCIC System B 3.5.3 BASES ACTIONS A.1 and A.2 (continued)

If the RCIC System is inoperable during MODE 1, or MODE 2 or 3 with reactor steam dome pressure >150 psig, and the HPCI System is verified to be OPERABLE, the RCIC System must be restored to OPERABLE status within 14 days. In this Condition, loss of the RCIC System will not affect the overall plant capability to provide makeup inventory at high reactor pressure since the HPCI System is the only high pressure system assumed to function during a loss of coolant accident (LOCA). OPERABILITY of HPCI is therefore verified immediately when the RCIC System is inoperable. This may be performed as an administrative check, by examining logs or other information, to determine if HPCI is out of service for maintenance or other reasons. It does not mean it is necessary to perform the Surveillances needed to demonstrate the OPERABILITY of the HPCI System. If the OPERABILITY of the HPCI System cannot be verified, however, Condition B must be immediately entered. For transients and certain abnormal events with no LOCA, RCIC (as opposed to HPCI) is the preferred source of makeup coolant because of its relatively small capacity, which allows easier control of the RPV water level. Therefore, a limited time is allowed to restore the inoperable RCIC to OPERABLE status.

The 14 day Completion Time is based on a reliability study (Ref. 3) that evaluated the impact on ECCS availability, assuming various components and subsystems were taken out of service. The results were used to calculate the average availability of ECCS equipment needed to mitigate the consequences of a LOCA as a function of allowed outage times (AOTs). Because of similar functions of HPCI and RCIC, the AOYs (i.e., Completion Times) determined for HPCI are also applied to RCIC.

B.1 and B.2 If the RCIC System cannot be restored to OPERABLE status within the associated Completion Time, or if the HPCI System is simultaneously inoperable, the plant must be brought to a condition 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and reactor steam dome pressure reduced to

150 psig within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months . The allowed Completion Times (continued)

SUSQUEHANNA - UNIT 2 TS / B 3.5-27 Revision 1

PPL Rev. 2 RCIC System B 3.5.3 BASES ACTIONS B.1 and B.2 (continued)

Are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.

SURVEILLANCE SR 3.5.3.1 REQUIREMENTS The flow path piping has the potential to develop voids and pockets of entrained air. Maintaining the pump discharge line of the RCIC System full of water ensures that the system will perform properly, injecting its full capacity into the Reactor Coolant System upon demand. This will also prevent a water hammer following an initiation signal. One acceptable method of ensuring the line is full is to vent at the high points. The 31 day Frequency is based on the gradual nature of void buildup in the RCIC piping, the procedural controls governing system operation, and operating experience.

SR 3.5.3.2 Verifying the correct alignment for manual, power operated, and automatic valves in the RCIC flow path provides assurance that the proper flow path will exist for RCIC operation. This SR does not apply to valves that are locked, sealed, or otherwise secured in position since these valves were verified to be in the correct position prior to locking, sealing, or securing.

A valve that receives an initiation signal is allowed to be in a non-accident position provided the valve will automatically reposition in the proper stroke time. This SR 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 SR does not apply to valves that cannot be inadvertently misaligned, such as check valves. For the RCIC System, this SR also includes the steam flow path for the turbine and the flow controller position.

The 31 day Frequency of this SR was derived from the Inservice Testing Program requirements for performing valve testing at least once every 92 days. The Frequency of (continued)

SUSQUEHANNA - UNIT 2 TS / B 3.5-28 Revision 0

PPL Rev. 2 RCIC System B 3.5.3 BASES SURVEILLANCE SURVEQIRENEN SR 3.5.3.2 (continued)

REQUIREMENTS 31 days is further justified because the valves are operated under procedural control and because improper valve position would affect only the RCIC System. This Frequency has been shown to be acceptable through operating experience.

SR 3.5.3.3 and SR 3.5.3.4 The RCIC pump flow rates ensure that the system can maintain reactor coolant inventory during pressurized conditions with the RPV isolated.

The flow tests for the RCIC System are performed at two different pressure ranges such that system capability to provide rated flow is tested both at the higher and lower operating ranges of the system. Additionally, adequate steam flow must be passing through the main turbine or turbine bypass valves to continue to control reactor pressure when the RCIC System diverts steam flow. Reactor steam pressure is considered adequate when Ž920 psig to perform SR 3.5.3.3 and Ž_ 150 psig to perform SR 3.5.3.4. However, the requirements of SR 3.5.3.4 are met by a successful performance at any pressure *< 165 psig. Adequate steam flow is represented by at least 1.25 turbine bypass valves open.

Therefore, sufficient time is allowed after adequate pressure and flow are achieved to perform those SRs. Reactor startup is allowed prior to performing the low pressure Surveillance because the reactor pressure is low and the time allowed to satisfactorily perform the Surveillance is short.

The reactor pressure is allowed to be increased to normal operating pressure since it is assumed that the low pressure Surveillance has been satisfactorily completed and there is no indication or reason to believe that RCIC is inoperable. Therefore, these SRs are modified by Notes that state the Surveillances are not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after the reactor steam pressure and flow are adequate to perform the test.

The Frequency for SR 3.5.3.3 is determined by the Inservice Testing Program requirements. The 24 month Frequency for SR 3.5.3.4 is based on the need to perform the Surveillance under conditions that apply just prior to or during a startup from a plant outage. Operating experience has shown that these components usually pass the SR when performed at the 24 month Frequency, which is base on the refueling (continued)

SUSQUEHANNA - UNIT 2 TS / B 3.5-29 Revision 1

PPL Rev. 2 RCIC System B 3.5.3 BASES SURVEILLANCE SR 3.5.3.3, and SR 3.5.3.4 (continued)

REQUIREMENTS cycle. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

SR 3.5.3.5 The RCIC System is required to actuate automatically in order to verify its design function satisfactorily. This Surveillance verifies that, with a required system initiation signal (actual or simulated), the automatic initiation logic of the RCIC System will cause the system to operate as designed, including actuation of the system throughout its emergency operating sequence; that is, automatic pump startup and actuation of all automatic valves to their required positions. This test also ensures the RCIC System will automatically restart on a n RPV low water level (Level 2) signal received subsequent to an RPV high water level (Level 8) trip and that the suction is automatically transferred from the CST to the suppression pool. The LOGIC SYSTEM FUNCTIONAL TEST performed in LCO 3.3.5.2 overlaps this Surveillance to provide complete testing of the assumed safety function.

The 24 month Frequency is based on the need to perform portions of the Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the Surveillance were performed with the reactor at power. Operating experience has shown that these components usually pass the SR when performed at the 24 month Frequency, which is based on the refueling cycle. Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

This SR is modified by a Note that excludes vessel injection during the Surveillance. Since all active components are testable and full flow can be demonstrated by recirculation through the test line, coolant injection into the RPV is not required during the Surveillance.

REFERENCES

1.

10 CFE 50, Appendix A, GDC 33.

2.

FSAR, Section 5.4.6.

(continued)

SUSQUEHANNA - UNIT 2 TS / B 3.5-30 Revision 1

PPL Rev. 2 RCIC System B 3.5.3 BASES REFERENCES

3.

Memorandum from R.L. Baer (NRC) to V. Stello, Jr. (NRC),

(continued)

"Recommended Interim Revisions to LCOs for ECCS Components,"

December 1, 1975.

4.

Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 39132).

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