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| author name =  
| author name =  
| author affiliation = Susquehanna Steam Electric Station
| author affiliation = Susquehanna Steam Electric Station
| addressee name = Gerlach R M
| addressee name = Gerlach R
| addressee affiliation = NRC/NRR
| addressee affiliation = NRC/NRR
| docket = 05000387
| docket = 05000387
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=Text=
=Text=
{{#Wiki_filter:* MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2017-9571 USER INFORMATION:
{{#Wiki_filter:v ,_'
GERLACH*ROSEY M Address: NUCSA2 Phone#: 542-3194 EMPL#: 028401 CA#: 0363 TRANSMITTAL INFORMATION:
Page    1      of
TO: GERLACH*ROSEY M 06/01/2017 LOCATION:
* 2
USNRC FROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER (NUCSA-2) v ,_' 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.
* MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2017-9571 USER INFORMATION:
WHEN REPLACING THIS MATERIAL IN YOUR HARDCOPY MANUAL, ENSURE
GERLACH*ROSEY M          EMPL#: 028401  CA#:  0363 Address: NUCSA2 Phone#:  542-3194 TRANSMITTAL INFORMATION:
TO:      GERLACH*ROSEY M      06/01/2017 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 .
TENTION: "REPLACE" directions do not affect the Table of Contents, Therefore no
* C will be issued with the updated material.
TSBl - TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL REMOVE MANUAL TABLE OF CONTENTS    DATE: 05/25/2017 ADD      MANUAL TABLE OF CONTENTS  DATE: 05/31/2017 CATEGORY: DOCUMENTS    TYPE: TSBl ID: TEXT 3.5.3 REMOVE:    REV:4 ADD:    REV: 5
 
VJ../
Page    2      of 2
*CATEGORY: DOCUMENTS ID: TEXT LOES REMOVE:    REV:l25 TYPE: TSBl ADD:    REV: 126 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS@ X3107 OR X3171 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:  TSBl
~anual
 
==Title:==
TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL Table Of Contents Issue
* 83.6.1.5
* 83.6.1.5
* Drywell Air Temperature  
* Drywell Air Temperature ..................................................................................... 2 83.6.1.6   Suppression Chamber-to-Drywell Vacuum Breakers ........................................... 1 83.6.2.1   Suppression Pool Average Temperature ....................................;....................... 3 83.6.2.2   Suppression Pool Water Level... ......................................................................... 1 83.6.2.3   Residual Heat Removal (RHR) Suppression Pool Cooling ................................ 2 83.6.2.4   Residual Heat Removal (RHR) Suppression Pool Spray .................................... 1 83.6.3.1 *Not Used     ..........................................................~ ............................................ 2 83.6.3.2   Drywell Air Flow System ..................................................................................... 2 83.6.3.3   Primary Containment Oxygen Concentration ............................ :......................... 2 83.6.4.1   Secondary Containment ....................................................................................13 83.6.4.2   Secondary Containment Isolation Valves (SCIVs) .............................................12 83.6.4.3   Standby Gas Tree;ltment (SGT) System .............................................................. 5
.....................................................................................
* SUSQUEHANNA - UNIT 1                               TS/B LOES-2                                                     Revision 126
2 83.6.1.6 Suppression Chamber-to-Drywell Vacuum Breakers ...........................................
 
1 83.6.2.1 Suppression Pool Average Temperature  
SUSQUEHANNA STEAM ELECTRIC STATION
....................................  
* LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)
; .......................
Section B3.7 Title PLANT SYSTEMS BASES Revision 83.7.1     Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) ...................................................................... 5 83.7.2     Emergency Service Water (ESW) System .......................................................... 3 83.7.3     Control Room Emergency Outside Air Supply (CREOAS} System ..................... 2 83.7.4     Control Room Floor Cooling System ................................................................... 1 83.7.5   ,Main Condenser Offgas ........................................: ............................................. 2 83.7.6     Main Turbine Bypass System .....................,........................................................ 3 83.7.7     Spent Fuel Storage Pool Water Level ................................................................. 2 83.7.8     Main Turbine Pressure Regulation System ......................................................... 1 83.8       ELECTRICAL POWER SYSTEMS BASES 83.8.1     AC Sources - Operating ..................................................................................... 8 83.8.2     AC Sources,- Shutdown ......................................................................; .............. O 83.8.3   . Diesel Fuel Oil, Lube Oil, and Starting Air........................................................... 5 83.8.4     DC Saurces-Operating ...................................................................................... 4 83.8.5     DC Sources - Shutdown .................................................................................... 1 B3.8.6     Battery Cell Parameters ....................................................................................... 2 83.8.7     Distribution Systems - Operating ....................................................................... 2 83.8.8    Distribution Systems - Shutdown ...'. ................................................................... 1 83.9       REFUELING OPERATIONS BASES 83.9.1     Refueling Equipment Interlocks .......................................................................... 1 83.9.2     Refuel Position One-Rod-Out h1terlock ............................................................... 1 83.9.3     Control Rod Position ............................... .'........................................................... 1 83.9.4   Control Rod Position Indication ........................................................................... O 83.9.5   Control Rod OPERABILITY - Refueling ............................................................. 1 83.9.6   Reactor Pressure Vessel (RPV) Water Level.. .................................................... 2 83.9.7   Residual Heat Removal (RHR) - High Water Level ............................................ 1 83.9.8   Residual Heat Removal (RHR)-Low Water Level. ............................................ 1 83.10     SPECIAL OPERATIONS BASES 83.10.1   lnservice Leak and Hydrostatic Testing Operation .............................................. 1 83.10.2   Reactor Mode Switch Interlock Testing ......-. ........................................................ 1 83.10.3   Single Control Rod Withdrawal - Hot Shutdown ................................................. 1 83.10.4   Single Control Rod Withdrawal - Cold Shutdown ............................................... 1 83.10.5   Single Control Rod Drive (CRD) Removal - Refueling ....................................... 1 83.10.6   Multiple Control Rod Withdrawal - Refueling ...................................................... 1 83.10.7   Control Rod Testing-Operating .......................................................................;1 83.10.8   Shutdown Margin (SOM) Test-Refueling .......................................................... 2
3 83.6.2.2 Suppression Pool Water Level... .........................................................................
* SUSQUEHANNA - UNIT 1                         TS/ B LOES-3                                                   , Revision 126
1 83.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling ................................
 
2 83.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray ....................................
Rev.5 RCICSystem B 3.5.3 B 3.5   EMERGENCY CORE COOLIN(3 SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM B 3.5.3 RCICSystem 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.
1 83.6.3.1 *Not Used .......................................................... ............................................
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 RCJC systems perform similar functions. The RCJC System design requirements ensure that the criteria of Reference 1 are satisfied.
2 83.6.3.2 Drywell Air Flow System .....................................................................................
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
2 83.6.3.3 Primary Containment Oxygen Concentration  
* 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 supply 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 i_ncreases, 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.
: .........................
* SUSQUEHANNA - UNIT 1               TS I B 3.5-25 (continued)
2 83.6.4.1 Secondary Containment  
Revision 1
....................................................................................
 
13 83.6.4.2 Secondary Containment Isolation Valves (SCIVs) .............................................
Rev.5 RCICSystem
12 83.6.4.3 Standby Gas Tree;ltment (SGT) System ..............................................................
* BASES BACKGROUND    The RCIC pump is provided with a minimum flow bypass line, which B3.5.3 (continued)  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.
5 SUSQUEHANNA  
APPLICABLE      The function of the RCIC System is to respond to transient events by SAFETY        providing makeup coolant to the reactor. The RCIC System is not an ANALSES        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).
-UNIT 1 TS/B LOES-2 Revision 126 SUSQUEHANNA STEAM ELECTRIC STATION
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 even of RPV isolation accompanied by a loss of feedwater flow. The RCIC System has sufficient capacity for maintaining RPV inventory during an isolation event.
* LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES) Section Title Revision B3.7 PLANT SYSTEMS BASES 83.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) ......................................................................
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.
5 83.7.2 Emergency Service Water (ESW) System ..........................................................
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 .
3 83.7.3 Control Room Emergency Outside Air Supply (CREOAS} System .....................
* SUSQUEHANNA - UNIT 1             TS I B 3.5-26 (continued}
2 83.7.4 Control Room Floor Cooling System ...................................................................
Revision 3
1 83.7.5 , Main Condenser Offgas ........................................  
 
: .............................................
Rev. 5 RCICSystem B 3.5.3 BASES ACT JONS       A.1 and A.2 (continued)
2 83.7.6 Main Turbine Bypass System ..................... , ........................................................
If the RCIC 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 HPC.1 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
3 83.7.7 Spent Fuel Storage Pool Water Level .................................................................
* 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
2 83.7.8 Main Turbine Pressure Regulation System .........................................................
* control of the RPV water level. Therefore, a limited time is allowed to restore the inoperable RCIC to OPERABLE status.
1 83.8 ELECTRICAL POWER SYSTEMS BASES 83.8.1 AC Sources -Operating  
The 14 day Completion Time is based on a reliability study (Ref. 3) that evaluated the impact on EGGS availability, assuming various components.
.....................................................................................
8 83.8.2 AC Sources,-Shutdown ......................................................................  
; ..............
O 83.8.3 . Diesel Fuel Oil, Lube Oil, and Starting Air ...........................................................
5 83.8.4 DC Saurces-Operating  
......................................................................................
4 83.8.5 DC Sources -Shutdown ....................................................................................
1 B3.8.6 Battery Cell Parameters  
.......................................................................................
2
* 83.8.7 83.8.8 Distribution Systems -Operating  
.......................................................................
2 Distribution Systems -Shutdown ... '. ...................................................................
1 83.9 REFUELING OPERATIONS BASES 83.9.1 Refueling Equipment Interlocks  
..........................................................................
1 83.9.2 Refuel Position One-Rod-Out h1terlock  
...............................................................
1 83.9.3 Control Rod Position ...............................  
.' ...........................................................
1 83.9.4 Control Rod Position Indication  
...........................................................................
O 83.9.5 Control Rod OPERABILITY  
-Refueling  
.............................................................
1 83.9.6 Reactor Pressure Vessel (RPV) Water Level.. ....................................................
2 83.9.7 Residual Heat Removal (RHR) -High Water Level ............................................
1 83.9.8 Residual Heat Removal (RHR)-Low Water Level. ............................................
1 83.10 SPECIAL OPERATIONS BASES 83.10.1 lnservice Leak and Hydrostatic Testing Operation  
..............................................
1 83.10.2 Reactor Mode Switch Interlock Testing ...... -. ........................................................
1 83.10.3 Single Control Rod Withdrawal  
-Hot Shutdown .................................................
1 83.10.4 Single Control Rod Withdrawal  
-Cold Shutdown ...............................................
1 83.10.5 Single Control Rod Drive (CRD) Removal -Refueling  
.......................................
1 83.10.6 Multiple Control Rod Withdrawal  
-Refueling  
......................................................
1 83.10.7 Control Rod Testing-Operating  
.......................................................................  
;1 83.10.8 Shutdown Margin (SOM) Test-Refueling  
..........................................................
2
* SUSQUEHANNA  
-UNIT 1 TS/ B LOES-3 , Revision 126
* *
* B 3.5 B 3.5.3 BASES Rev.5 RCICSystem B 3.5.3 EMERGENCY CORE COOLIN(3 SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM RCICSystem 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 RCJC systems perform similar functions.
The RCJC 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 supply 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 i_ncreases, 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 1 TS I B 3.5-25 Revision 1
* *
* BASES BACKGROUND (continued)
APPLICABLE SAFETY ANAL SES LCO APPLICABILITY ACTIONS Rev.5 RCICSystem B3.5.3 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. 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). 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 even of RPV isolation accompanied by a loss of feedwater flow. The RCIC System has sufficient capacity for maintaining RPV inventory during an isolation event. 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 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. 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 1 TS I B 3.5-26 Revision 3
* *
* BASES ACT JONS (continued)
A.1 and A.2 Rev. 5 RCICSystem B 3.5.3 If the RCIC 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 HPC.1 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 EGGS 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).
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 AOTs (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 hours and reactor steam dome pressure reduced to::;; 150 psig within 36 hours. The allowed Completion Times (continued)
Because of similar functions of HPCI and RCIC, the AOTs (i.e., Completion Times) determined for HPCI are also applied to RCIC.
SUSQUEHANNA  
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 hours and reactor steam dome pressure reduced to::;; 150 psig within 36 hours. The allowed Completion Times
-UNIT 1 TS I B 3.5-27 Revision 2
* SUSQUEHANNA - UNIT 1             TS I B 3.5-27 (continued)
* *
Revision 2
* BASES ACTIONS B.1 and B.2 (continued)
 
Rev.5 RCIC System B 3.5.3 are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in a 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 Surveillance Frequency is controlled under the Surveillance Frequency Control Program . SR3.5.3.2 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.
Rev.5 RCIC System
The SR does not apply to valves that are Jocked, sealed, or otherwise secured in position since these valves were verified to be in the correct position prior to locking, sealing, or securing.
* BASES B 3.5.3 ACTIONS       B.1 and B.2 (continued) are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in a orderly manner and without challenging plant systems.
A valve that receives an initiation signal is allowed to be in a nonaccident 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.
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 Surveillance Frequency is controlled under the Surveillance Frequency Control Program .
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.
* SR3.5.3.2 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. The SR does not apply to valves that are Jocked, 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 nonaccident 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 Surveillance Frequency is controlled under the Surveillance Frequency Control Program . {continued) . SUSQUEHANNA  
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program .
-UNIT 1 TS I B 3.5-28 Revision 1
* SUSQUEHANNA - UNIT 1             TS I B 3.5-28
* *
{continued) .
* BASES SURVEILLANCE REQUIREMENTS SR 3.5.3.3 and SR 3.5.3.4 Rev.5 RCIC System B 3.5.3 The RCIC pump flow rates ensure that the system can maintain reactor coolant inventory during pressurized conditions with the RPV isolated.
Revision 1
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 920 psig to perform SR 3.5.3.3and::?: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 these 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.
Rev.5 RCIC System B 3.5.3 BASES SURVEILLANCE REQUIREMENTS 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 wh~n ~ 920 psig to perform SR 3.5.3.3and::?: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, these SRs are modified by Notes that state the Surveillances are not required to be performed until 12 hours after the reactor steam pressure and flow are adequate to perform the test. The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. * (continued)
* Therefore, sufficient time is allowed after adequate pressure and flow are achieved to perform these 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.
SUSQUEHANNA  
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 hours after the reactor steam pressure and flow are adequate to perform the test.
-UNIT 1 TS I B 3.5-29 Revision 2
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.                 *
* *
* SUSQUEHANNA - UNIT 1             TS I B 3.5-29 (continued)
* BASES SURVEILLANCE REQUIREMENTS
Revision 2
* REFERENCES SR 3.5.3.5 Rev.5 RCICSystem B 3.5.3 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.
Rev.5 RCICSystem
This test also ensures the RCIC System will automatically restart on an 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 Surveillance Frequency is controlled under the Surveillance Frequency Control Program. This SR is modified by a Note that excludes vessel injection during the Surveillance.
* B 3.5.3 BASES SURVEILLANCE REQUIREMENTS
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.  
* 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 an 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
: 1. 10 CFR 50, Appendix A, GDC 33. 2 . FSAR, Section 5.4.6. {continued)
* assumed safety function .
SUSQUEHANNA  
The Surveillance Frequency is controlled under the Surveillance Frequency Control Program.
-UNIT 1 TS I B 3.5-30 Revision 1
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 CFR 50, Appendix A, GDC 33.
* BASES REFERENCES (continued)
: 2.       FSAR, Section 5.4.6.
: 3. Rev. 5 RCICSystem B 3.5.3 Memorandum from R. L. Baer (NRG) to. V. Stello, Jr. (NRG), "Recommended Interim Revisions to LCOs for EGGS Components," December 1, 1975. 4. Final Policy Statement on Technical Specifications Improvements, July 22, *1993 (58 FR 39132) . SUSQUEHANNA  
* SUSQUEHANNA - UNIT 1               TS I B 3.5-30
-UNIT 1 TS I B 3.5-31 Revision O}}
{continued)
Revision 1
 
Rev. 5 RCICSystem
**                                                                                  B 3.5.3 BASES REFERENCES    3. Memorandum from R. L. Baer (NRG) to. V. Stello, Jr. (NRG),
(continued)        "Recommended Interim Revisions to LCOs for EGGS Components,"
December 1, 1975.
: 4. Final Policy Statement on Technical Specifications Improvements, July 22, *1993 (58 FR 39132).
* SUSQUEHANNA - UNIT 1           TS I B 3.5-31                                 Revision O}}

Latest revision as of 16:20, 4 February 2020

Transmittal of Technical Specification Bases Unit 1 Manual
ML17163A176
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Issue date: 06/01/2017
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To: Gerlach R
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  • CATEGORY: DOCUMENTS ID: TEXT LOES REMOVE: REV:l25 TYPE: TSBl ADD: REV: 126 ANY DISCREPANCIES WITH THE MATERIAL PROVIDED, CONTACT DCS@ X3107 OR X3171 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: TSBl

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Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL Table Of Contents Issue Date: 05/31/2017 Procedure Name Rev Issue Date Change ID Change Nwnber TEXT LOES 126 05/31/2017

Title:

LIST OF EFFECTIVE SECTIONS TEXT TOC

Title:

TABLE OF CONTENTS 23 07/02/2014 k)"!

TEXT 2.1.l 6 01/22/2015 ~~~

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Title:

SAFETY LIMITS (SLS) REACTOR CORE SLS 0 ',,~1*

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LIMITING CONDITION FOR OPERATWN/(LGO) 'APPLICABILITY

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REACTIVITY CONTROL SYSTEMS SHUTB. OWN MARGIN (SDM) 7 TEXT 3.1.2

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~" REACTIVITY ANOMALIES

Title:

REACTIVITY CONTROL'-,SYSTEMS

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  • v TEXT 3.1.3 11/16/2016

Title:

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REACTIVIT'\~L

<'\ SYSTEMS CONTROL ROD OPERABILITY TEXT 3.1.4 5 11/16/2016

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM TIMES TEXT 3.1.5 2 11/16/2016

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS TEXT 3.1.6 4 11/16/2016

Title:

REACTIVITY CONTROL SYSTEMS ROD PATTERN CONTROL Pagel of 8 Report Date: 05/31/17

SSES MANUAL Manual Name: TSBl

~anual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.1.7 4 11/16/2016

Title:

REACTIVITY CONTROL SYSTEMS STANDBY LIQUID CONTROL (SLC) SYSTEM TEXT 3.1.8 4 11/16/2016

Title:

REACTIVITY CONTROL SYSTEMS SCRAM DISCHARGE VOLUME (SDV) VENT AND DRAIN VALVES TEXT 3.2.l 3 11/16/2016

Title:

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

TEXT 3.2.2 4 11/16/2016

Title:

POWER DISTRIBUTION LIMITS MINIMUM CRITICAL POWER RATIO (MCPR)

TEXT 3.2.3 .3 11/16/2016

Title:

POWER DISTRIBUTION LIMITS LINEAR HEAT GENERATION RATE (LHGR)

. E X T 3. 3 .1.1 7 11/16/2016

Title:

INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) INSTRUMENTATION TEXT 3 . 3 . 1. 2 3 11/16/2016

Title:

INSTRUMENTATION SOURCE RANGE MONITOR (SRM) INSTRUMENTATION TEXT 3.3.2.1 5 11/16/2016

Title:

INSTRUMENTATION CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.3.2.2 3 11/16/2016

Title:

INSTRUMENTATION FEEDWATER MAIN TURBINE HIGH WATER LEVEL TRIP INSTRUMENTATION TEXT 3.3.3.1 10 11/16/2016

Title:

INSTRUMENTATION POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT 3.3.3.2 2 11/16/2016

Title:

INSTRUMENTATION REMOTE SHUTDOWN SYSTEM TEXT 3.3.4.1 3 11/16/2016

Title:

INSTRUMENTATION END OF CYCLE RECIRCULATION PUMP TRIP (EOC-RPT) INSTRUMENTATION Page~ of 8 Report Date: 05/31/17

SSES MANUAL Manual Name: TSBl

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Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.3.4.2 1 11/16/2016

Title:

INSTRUMENTATION ANTICIPATED TRANSIENT WITHOUT SCRAM RECIRCULAT~ON PUMP TRIP (ATWS-RPT) INSTRUMENTATION TEXT 3.3.5.l 4 11/16/2016

Title:

INSTRUMENTATION EMERGENCY CORE COOLING SYSTEM (ECCS) INSTRUMENTATION TEXT 3.3.5.2 1 11/16/2016

Title:

INSTRUMENTATION REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM INSTRUMENTATION TEXT 3.3.6.l 8 11/16/2016

Title:

INSTRUMENTATION PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION TEXT 3.3.6.2 5 11/16/2016

Title:

INSTRUMENTATION SECONDARY CONTAINMENT ISOLATION INSTRUMENTATION

.EXT 3.3.7.l 3 11/16/2016

Title:

INSTRUMENTATION CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM INSTRUMENTATION TEXT 3.3.8.1 3 11/16/2016

Title:

INSTRUMENTATION LOSS OF POWER (LOP) INSTRUMENTATION TEXT 3.3.8.2 1 11/16/2016

Title:

INSTRUMENTATION REACTOR PROTECTION SYSTEM (RPS) ELECTRIC POWER MONITORING TEXT 3.4.l 5 li/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) RECIRCULATION LOOPS OPERATING TEXT 3.4.2 4 11/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) JET PUMPS TEXT 3.4.3 3 01/13/2012

Title:

REACTOR COOLANT SYSTEM RCS SAFETY RELIEF VALVES S/RVS TEXT 3.4.4 1 11/16/2016

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Title:

REACTOR COOLANT SYSTEM (RCS) RCS OPERATIONAL LEAKAGE o_-_-

Page}. of 8 Report Date: 05/31/17

SSES MANUAL Manual Name: TSBl

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Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.4.5 2 04/13/2016

Title:

REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE ISOLATION VALVE (PIV) LEAKAGE TEXT 3.4.6 5 11/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) .RCS LEAKAGE DETECTION INSTRUMENTATION TEXT 3.4.7 3 11/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) RCS SPECIFIC ACTIVITY TEXT 3.4.8 3 11/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM

- HOT SHUTDOWN TEXT 3.4.9 2 11/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) RESIDUAL HEAT REMOVAL (RHR) SHUTDOWN COOLING SYSTEM

- COLD SHUTDOWN

~EXT 3.4.10 5 11/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) RCS PRESSURE AND TEMPERATURE (P/T) LIMITS TEXT 3.4.11 1 11/16/2016

Title:

REACTOR COOLANT SYSTEM (RCS) REACTOR STEAM DOME PRESSURE TEXT 3.5.1 5 11/16/2016

Title:

EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM ECCS - OPERATING TEXT 3.5.2 1 11/16/2016

Title:

EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM ECCS - SHUTDOWN TEXT 3.5.3 5 05/31/2017

Title:

EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC)

SYSTEM RCIC SYSTEM TEXT 3.6.1.1 6 11/16/2016

Title:

PRIMARY CONTAINMENT TEXT 3.6.1.2 2 11/16/2016

~

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR*LOCK Page! of 8 Report Date: 05/31/17

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Manual Name: TSBl

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Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.1.3 13 11/16/2016

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT ISOLATION VALVES (PCIVS)

TEXT 3.6.1.4 2 11/16/2016

Title:

.CONTAINMENT SYSTEMS CONTAINMENT PRESSURE TEXT 3.6.1.5 2 11/16/2016

Title:

CONTAINMENT SYSTEMS DRYWELL AIR TEMPERATURE TEXT 3.6.1.6 1 11/16/2016

Title:

CONTAINMENT SYSTEMS SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKERS TEXT 3.6.2.1 3 11/16/2016

Title:

CONTAINMENT SYSTEMS SUPPRESSION POOL AVERAGE TEMPERATURE

~EXT 3.6.2.2 1 11/16/2016

Title:

CONTAINMENT SYSTEMS SUPPRESSION POOL WATER LEVEL TEXT 3.6.2.3 2 11/16/2016

Title:

CONTAINMENT SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL COOLING TEXT 3.6.2.4 1 11/16/2016

Title:

CONTAINMENT SYSTEMS RESIDUAL HEAT REMOVAL (RHR) SUPPRESSION POOL SPRAY TEXT 3.6.3.1 06/13/2006

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT HYDROGEN RECOMBINERS TEXT 3.6.3.2 2 11/16/2016

Title:

CONTAINMENT SYSTEMS DRYWELL AIR FLOW SYSTEM TEXT 3.6.3.3 2 11/16/2016

Title:

CONTAINMENT SYSTEMS PRIMARY CONTAINMENT OXYGEN CONCENTRATION TEXT 3 6 4 1 13 04/19/2017

~ Tit~e~ ~ONTAINMENT SYSTEMS SECONDARY CONTAINMENT Page~ of 8 Report Date: 05/31/17

SSES MANUAL Manual Name: TSBl

~anual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.6.4.2 12 04/19/2017

Title:

CONTAINMENT SYSTEMS SECONDARY CONTAINMENT ISOLATION VALVES (SCIVS)

TEXT 3.6.4.3 5 11/16/2016

Title:

CONTAINMENT SYSTEMS STANDBY GAS TREATMENT (SGT) SYSTEM TEXT 3.7.1 5 11/16/2016

Title:

PLANT SYSTEMS RESIDUAL HEAT REMOVAL SERVICE WATER (RHRSW) SYSTEM AND THE ULTIMATE HEAT SINK (UHS)

TEXT 3.7.2 3 11/16/2016

Title:

PLANT SYSTEMS EMERGENCY SERVICE WATER (ESW) SYSTEM TEXT 3.7.3 2 11/16/2016

Title:

PLANT SYSTEMS CONTROL ROOM EMERGENCY OUTSIDE AIR SUPPLY (CREOAS) SYSTEM

~EXT 3.7.4 1 11/16/2016

Title:

PLANT SYSTEMS CONTROL ROOM FLOOR COOLING SYSTEM TEXT 3.7.5 2 11/16/2016

Title:

PLANT SYSTEMS MAIN CONDENSER OFFGAS TEXT 3.7.6 3 11/16/2016

Title:

PLANT SYSTEMS MAIN TURBINE BYPASS SYSTEM TEXT 3.7.7 2 11/16/2016

Title:

PLANT SYSTEMS SPENT FUEL STORAGE POOL WATER LEVEL TEXT 3.7.8 1 11/16/2016

Title:

PLANT SYSTEMS TEXT 3.8.1 8 11/16/2016

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES - OPERATING TEXT 3.8.2 0 11/15/2002

~

Title:

ELECTRICAL POWER SYSTEMS AC SOURCES - SHUTDOWN

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Page §_ of 8 Report Date: 05/31/17

SSES MANUAL Manual Name: TSBl

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Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.8.3 5 11/16/2019

Title:

ELECTRICAL POWER SYSTEMS DIESEL FUEL OIL, LUBE OIL, AND STARTING AIR TEXT 3.8.4 4 11/16/2016

Title:

ELECTRICAL POWER SYSTEMS DC SOURCES - OPERATING TEXT 3.8.5 1 12/14/2006

Title:

ELECTRICAL POWER SYSTEMS DC SOURCES - SHUTDOWN TEXT 3.8.6 2 11/16/201-6 Title.: ELECTRICAL POWER SYSTEMS BATTERY CELL PARAMETERS TEXT 3.8.7 2 11/16/2016

Title:

ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS, - OPERATING

~EXT 3.8.8 1 11/i6/2016

Title:

ELECTRICAL POWER SYSTEMS DISTRIBUTION SYSTEMS - SHUTDOWN TEXT 3.9.1 1 11/16/2016

Title:

REFUELING OPERATIONS REFUELING EQUIPMENT INTERLOCKS TEXT 3.9.2 2 11/:).6/2016

Title:

REFUELING OPERATIONS REFUEL POSITION ONE-ROD-OUT INTERLOCK TEXT .3.9.3 1 11/16/2016

Title:

REFUELING OPERATIONS CONTROL ROD POSITION TEXT 3.9.4 0 11/15/2002

Title:

REFUELING OPERATIONS CONTROL ROD POSITION INDICATION TEXT 3.9.5 1 11/16/2016

Title:

REFUELING OPERATIONS CONTROL ROD OPERABILITY - REFUELING TEXT 3 9 6 2 11/16/2016

~ Tit~e; REFUELING OPERATIONS REACTOR PRESSURE VESSEL (RPV) WATER LEVEL Pagel of 8 Report Date: 05/31/17

SSES MANUAL Manual Name: TSBl

~~anual

Title:

TECHNICAL SPECIFICATION BASES UNIT 1 MANUAL TEXT 3.9.7 1 11/16/2016

Title:

REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) - HIGH WATER LEVEL TEXT 3.9.8 1 11/16/2016

Title:

REFUELING OPERATIONS RESIDUAL HEAT REMOVAL (RHR) - LOW WATER LEVEL TEXT 3.10.1 1 01/23/2008

Title:

SPECIAL OPERATIONS INSERVICE LEAK AND HYDROSTATIC TESTING OPERATION TEXT 3.10.2 1 11/16/2016

Title:

SPECIAL OPERATIONS REACTOR MODE SWITCH INTERLOCK TESTING TEXT 3.10.3 1 11/16/2016

Title:

SPECIAL OPERATIONS SINGLE CONTROL ROD WITHDRAWAL - HOT SHUTDOWN

.EXT 3.10.4 1 11/16/2016

Title:

SPECIAL OPERATIONS SINGLE CONTROL ROD WITHDRAWAL - COLD SHUTDOWN TEXT 3.10.5 1 11/16/2016

Title:

SPECIAL OPERATIONS SINGLE CONTROL ROD DRIVE (CRD) REMOVAL - REFUELING TEXT 3.10.6 1 11/16/2016

Title:

SPECIAL OPERATIONS MULTIPLE CONTROL ROD WITHDRAWAL - REFUELING TEXT 3.10.7 1 04/18/2006

Title:

SPECIAL OPERATIONS CONTROL ROD TESTING - OPERATING TEXT 3.10.8 2 11/16/2016

Title:

SPECIAL OPERATIONS SHUTDOWN MARGIN (SDM) TEST - REFUELING Page _§_ of 8 Report Date: 05/31/17

SUSQUEHANNA STEAM ELECTRIC STATION

  • LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section TOG Title Revision Table of Contents ...............................................................................................23 82.0 SAFETY LIMITS BASES 82.1.1 Reactor Core SLs ............................................................................................... 6 82.1.2 Reactor Coolant System {RCS) Pressure SL. ..................................................... 1 83.0 LCO AND SR APPLICABILITY BASES .............................................................. 3 B 3.1 REACTIVITY CONTROL BASES 83.1.1 Shutdown Margin (SOM) .................................................................................... 2 83.1.2 Reactivity Anomalies ..................................................................*........................ 1 83.1.3 Control Rod OPERABILITY ................................................................................ 3 83.1.4 Control Rod Scram Times ......................................................................... ~ .......... 5 83.1.5 Control Rod Scram Accumulators ....................................................................... 2 83.1.6 Rod Pattern Control ............................................................................................ 4 83.1.7 Standby Liquid Control (SLC) System ................................................................ 4 83.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves .................................... 4 B 3.2 POWER DISTRIBUTION LIMITS BASES 832.1 Average Planar Linear Heat Generation Rate (APLHGR) ................................... 3 83.2.2 Minimum Critical Power Ratio (MCPR) ............................................................... 4 83.2.3 Linear Heat Generation Rate (LHGR) ................................................................. 3 8 3.3 INSTRUMENTATION 83.3.1.1 Reactor Protection System (RPS) Instrumentation .................. .-.......................... 7 83.3.1.2 Source Range Monitor (SRM) Instrumentation ................................................... 3 83.3.2.1 Control Rod Block Instrumentation ..................................................................... 5 83.3.2.2 Feedwater - Main Turbine High Water Level Trip Instrumentation ..................... 3 83.3.3.1 Post Accident Monitoring {PAM) Instrumentation ............................................... 1O 83.3.3.2 Remote Shutdown System ................................................................................. 2 83.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT) Instrumentation .................... 3 83.3.4.2 Anticipated Transient Without Scram Recirculation*

Pump Trip (ATWS-RPT) Jnstrumentation ............................................................. 1 83.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation ....... :....................... .4 83.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation ......................... 1 83.3.6.1 Primary Containment Isolation Instrumentation .................................................. 8 83.3.6.2 Secondary Containment Isolation Instrumentation .............................................. 5 83.3.7.1 Control Room Emergency Outside Air Supply (CREOAS) ................................. 3 83.3.8.1 Loss of Power (LOP) Instrumentation ................................................................. 3 83.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring .............................. 1

  • SUSQUEHANNA - UNIT 1 TS/ B LOES-1 Revision 126

SUSQUEHANNA STEAM ELECTRIC STATION

  • LIST OF EFFECTIVE SECTIONS {TECHNICAL SPECI FICATJONS BASES)

Section B 3.4 Title REACTOR COOLANT SYSTEM BASES Revision 83.4.1 Recirculation Loops Operating .............. ~ ............................................................. 5 83.4.2 Jet Pumps ....................................................................................................... 4 83.4.3 Safety/Relief Valves (S/RVs) .............................................................................. 3 83.4.4 RCS Operational LEAKAGE .............................................................................. 1 83.4.5 RCS Pressure Isolation Valve (PIV) Leakage ...... ~ .............................................. 2 83.4.6 RCS Leakage Detection Instrumentation:........................................................... 5 83.4.7 RCS Specific Activity .......................................................................................... 3 83.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown ..................................................................................... 3 83.4.9 Residual Heat Removal {RHR) Shutdown Cooling System - Cold Shutdown ...................................................................... ~ ............ 2 83.4.10 RCS Pressure and Temperature (PIT) Limits ., ................................................... 5 83.4.11 Reactor Steam Dome Pressure .......................................................................... 1 83.5 ECCS AND RCIC BASES 83.5.1 ECCS - Operating .............................................................................................. 5 83.5.2 ECCS- Shutdown .............................................................................................. 1 83.5.3 RCIC System ....................................................................,....*..-.......................... 5 83.6 CONTAINMENT SYSTEMS BASES 83.6.1.1 Primary Containment .......................................................................................... 6 83.6.1.2 Primary Containment Air Lock ............................................................................ 2 83.6.1.3 Primary Containment Isolation Valves (PC IVs) .................................................. 13 83.6.1.4 Containment Pressure ................................................... ~ .................................... 2

  • 83.6.1.5
  • Drywell Air Temperature ..................................................................................... 2 83.6.1.6 Suppression Chamber-to-Drywell Vacuum Breakers ........................................... 1 83.6.2.1 Suppression Pool Average Temperature ....................................;....................... 3 83.6.2.2 Suppression Pool Water Level... ......................................................................... 1 83.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling ................................ 2 83.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray .................................... 1 83.6.3.1 *Not Used ..........................................................~ ............................................ 2 83.6.3.2 Drywell Air Flow System ..................................................................................... 2 83.6.3.3 Primary Containment Oxygen Concentration ............................ :......................... 2 83.6.4.1 Secondary Containment ....................................................................................13 83.6.4.2 Secondary Containment Isolation Valves (SCIVs) .............................................12 83.6.4.3 Standby Gas Tree;ltment (SGT) System .............................................................. 5
  • SUSQUEHANNA - UNIT 1 TS/B LOES-2 Revision 126

SUSQUEHANNA STEAM ELECTRIC STATION

  • LIST OF EFFECTIVE SECTIONS (TECHNICAL SPECIFICATIONS BASES)

Section B3.7 Title PLANT SYSTEMS BASES Revision 83.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS) ...................................................................... 5 83.7.2 Emergency Service Water (ESW) System .......................................................... 3 83.7.3 Control Room Emergency Outside Air Supply (CREOAS} System ..................... 2 83.7.4 Control Room Floor Cooling System ................................................................... 1 83.7.5 ,Main Condenser Offgas ........................................: ............................................. 2 83.7.6 Main Turbine Bypass System .....................,........................................................ 3 83.7.7 Spent Fuel Storage Pool Water Level ................................................................. 2 83.7.8 Main Turbine Pressure Regulation System ......................................................... 1 83.8 ELECTRICAL POWER SYSTEMS BASES 83.8.1 AC Sources - Operating ..................................................................................... 8 83.8.2 AC Sources,- Shutdown ......................................................................; .............. O 83.8.3 . Diesel Fuel Oil, Lube Oil, and Starting Air........................................................... 5 83.8.4 DC Saurces-Operating ...................................................................................... 4 83.8.5 DC Sources - Shutdown .................................................................................... 1 B3.8.6 Battery Cell Parameters ....................................................................................... 2 83.8.7 Distribution Systems - Operating ....................................................................... 2 83.8.8 Distribution Systems - Shutdown ...'. ................................................................... 1 83.9 REFUELING OPERATIONS BASES 83.9.1 Refueling Equipment Interlocks .......................................................................... 1 83.9.2 Refuel Position One-Rod-Out h1terlock ............................................................... 1 83.9.3 Control Rod Position ............................... .'........................................................... 1 83.9.4 Control Rod Position Indication ........................................................................... O 83.9.5 Control Rod OPERABILITY - Refueling ............................................................. 1 83.9.6 Reactor Pressure Vessel (RPV) Water Level.. .................................................... 2 83.9.7 Residual Heat Removal (RHR) - High Water Level ............................................ 1 83.9.8 Residual Heat Removal (RHR)-Low Water Level. ............................................ 1 83.10 SPECIAL OPERATIONS BASES 83.10.1 lnservice Leak and Hydrostatic Testing Operation .............................................. 1 83.10.2 Reactor Mode Switch Interlock Testing ......-. ........................................................ 1 83.10.3 Single Control Rod Withdrawal - Hot Shutdown ................................................. 1 83.10.4 Single Control Rod Withdrawal - Cold Shutdown ............................................... 1 83.10.5 Single Control Rod Drive (CRD) Removal - Refueling ....................................... 1 83.10.6 Multiple Control Rod Withdrawal - Refueling ...................................................... 1 83.10.7 Control Rod Testing-Operating .......................................................................;1 83.10.8 Shutdown Margin (SOM) Test-Refueling .......................................................... 2

  • SUSQUEHANNA - UNIT 1 TS/ B LOES-3 , Revision 126

Rev.5 RCICSystem B 3.5.3 B 3.5 EMERGENCY CORE COOLIN(3 SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM B 3.5.3 RCICSystem 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 RCJC systems perform similar functions. The RCJC 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 supply 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 i_ncreases, 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.

  • SUSQUEHANNA - UNIT 1 TS I B 3.5-25 (continued)

Revision 1

Rev.5 RCICSystem

  • BASES BACKGROUND The RCIC pump is provided with a minimum flow bypass line, which B3.5.3 (continued) 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 The function of the RCIC System is to respond to transient events by SAFETY providing makeup coolant to the reactor. The RCIC System is not an ANALSES 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 even 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 .

  • SUSQUEHANNA - UNIT 1 TS I B 3.5-26 (continued}

Revision 3

Rev. 5 RCICSystem B 3.5.3 BASES ACT JONS A.1 and A.2 (continued)

If the RCIC 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 HPC.1 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

The 14 day Completion Time is based on a reliability study (Ref. 3) that evaluated the impact on EGGS 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 AOTs (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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and reactor steam dome pressure reduced to::;; 150 psig 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

  • SUSQUEHANNA - UNIT 1 TS I B 3.5-27 (continued)

Revision 2

Rev.5 RCIC System

  • BASES B 3.5.3 ACTIONS B.1 and B.2 (continued) are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in a 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 Surveillance Frequency is controlled under the Surveillance Frequency Control Program .

  • SR3.5.3.2 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. The SR does not apply to valves that are Jocked, 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 nonaccident 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 Surveillance Frequency is controlled under the Surveillance Frequency Control Program .

  • SUSQUEHANNA - UNIT 1 TS I B 3.5-28

{continued) .

Revision 1

Rev.5 RCIC System B 3.5.3 BASES SURVEILLANCE REQUIREMENTS 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 wh~n ~ 920 psig to perform SR 3.5.3.3and::?: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 these 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after the reactor steam pressure and flow are adequate to perform the test.

The Surveillance Frequency is controlled under the Surveillance Frequency Control Program. *

  • SUSQUEHANNA - UNIT 1 TS I B 3.5-29 (continued)

Revision 2

Rev.5 RCICSystem

  • B 3.5.3 BASES SURVEILLANCE REQUIREMENTS
  • 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 an 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 Surveillance Frequency is controlled under the Surveillance Frequency Control Program.

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 CFR 50, Appendix A, GDC 33.

2. FSAR, Section 5.4.6.
  • SUSQUEHANNA - UNIT 1 TS I B 3.5-30

{continued)

Revision 1

Rev. 5 RCICSystem

    • B 3.5.3 BASES REFERENCES 3. Memorandum from R. L. Baer (NRG) to. V. Stello, Jr. (NRG),

(continued) "Recommended Interim Revisions to LCOs for EGGS Components,"

December 1, 1975.

4. Final Policy Statement on Technical Specifications Improvements, July 22, *1993 (58 FR 39132).
  • SUSQUEHANNA - UNIT 1 TS I B 3.5-31 Revision O
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