ML042160218
| ML042160218 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/15/2004 |
| From: | Shriver B Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| GL-94-002, PLA-5785 | |
| Download: ML042160218 (19) | |
Text
Bryce L Shriver Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3120 Fax 570.542.1504 bishriver@pplweb.com pP I Im-v..U JUL 15 2004 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station OP1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION TABLE OF CONTENTS REVISIONS PROPOSED AMENDMENT NO. 259 TO LICENSE NFP-14 AND PROPOSED AMENDMENT NO. 224 TO LICENSE NFP-22:
REVISED RESPONSE TO GL 94-02:
LONG-TERM STABILITY SOLUTION Docket Nos. 50-387 PLA-5785 and 50-388
References:
- 1)
PLA-5686, B. L Shriver (PPL) to USNRC, "Proposed Amendenent No. 259 to License NFP-14 and Proposed Amendment No. 224 to License NFP-22: Revised Response to GL-94-02: Long-Term Stability Solution, " dated December 22, 2003.
The license amendment requested in Reference 1 incorporates the Operational Power Range Monitor (OPRM) into the SSES Technical Specifications. Attached are updated Table of Contents (TOC) pages for the Unit 1 and Unit 2 Technical Specifications.
Accordingly, the mark-ups of these pages are included in Attachment A, and Camera Ready TOC pages based on these mark-ups are provided in Attachment B.
If you have any questions, please contact Mr. Duane L. Filchner at (610) 774-7819.
Sincerely, B. L. Shriver Ac Attachments:
Attachment A - Proposed TOC Changes (Mark-ups)
Attachment B - Proposed TOC Changes (Camera-Ready) copy: NRC Region I Mr. A. J. Blamey, NRC Sr. Resident Inspector Mr. R. V. Guzman, NRC Project Manager Mr. R. Janati, DEP/BRP
,0)l
is v
Attachment A Proposed Technical Specification Changes (Markups)
Table of Contents (TOC)
(Units 1 & 2)
- . TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 1.0 1.1 1.2 1.3 1.4 2.0 2.1 2.2 3.0 3.0 3.1 3.1.1 3.1.2 3.1.3 3.1.4 3.1.5 3.1.6 3.1.7 3.1.8 3.2 3.2.1 3.2.2 3.2.3 3.2.4 USE AND APPLICATION.................
1.1-1 Definitions............................................................................................ 1.1-1 Logical Connectors............
1.2-1 Completion Times............
1.3-1 Frequency.............................................................................................
1.4-1 SAFETY LIMITS (SLs).................
- - /2.0-1 SLs..
fi;,( 2.0-1 SL Violations.........................;.........................................................
2.0-1 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY......
3.0-1 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY....................
3.0-4 REACTIVITY CONTROL SYSTEMS
......................... 3.1-1 Shutdown Margin (SDM)................
3.1-1 Reactivity Anomalies 3.1-5 Control Rod OPERABILITY..................
3.1-7 Control Rod Scram Times.......................
3.1-12 Control Rod Scram Accumulators.......................
3.1-15 Rod Pattern Control.
3.1-18 Standby Liquid Control (SLC) System..........................
3.1-20 Scram Discharge Volume (SDV) Vent and Drain Valves..
3.1-25 POWER DISTRIBUTION LIMITS..
3.2-1 Average Planar Linear Heat Generation Rate (APLHGR).
3.2-1 Minimum Critical Power Ratio (MCPR)..
3.2-3 Linear Heat Generation Rate (LHGR)..
3.2-5 Average Power Range Monitor (APRM) Gain and Setpoints...
3.2-7
- 3.3 3.3.1.1 3.3.1.2 3.3.2.1 3.3.2.2 3.3.3.1 3.3.3.2 3.3.4.1 3.3.4.2
- 3.3.5.1 3.3.5.2 3.3.6.1 3.3.6.2 3.3.7.1
- 3. 3. 1 3 INSTRUMENTATION............................................ 3.3-1 Reactor Protection System (RPS) Instrumentation............................ 3.3-1 Source Range Monitor (SRM) Instrumentation.................................. 3.3-10 I
Control Rod Block Instrumentation.........................................
3.3-16 Feedwater-Main Turbine High Water Level Trip Instrumentation.........3.3-21 Instrumentation~~~.........................................................................................332 Post Accident Monitoring (PAM) Instrumentation.............................. 3.3-23 Remote Shutdown System.................
3.3-26 End of Cycle Recirculation Pump Trip (EOC-RPT)
Instrumentation..............
3.3-29 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation....................................
3.3-33 Emergency Core Cooling System (ECCS) Instrumentation............... 3.3-36 Reactor Core Isolation Cooling (RCIC) System Instrumentation......................................... 3.3-48 Primary Containment Isolation Instrumentation.......................... 3.3-52 Secondary Containment Isolation Instrumentation............................ 3.3-63 Control Room Emergency Outside Air Supply (CREOAS)
System Instrumentation..........................................
3.3-67
'-(continued)
SUSQUEHANNA - UNIT I Amendment 1,84, ?*'5 73 /7c-I
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.3 INSTRUMENTATION (continued) 3.3.8.1 Loss of Power (LOP) Instrumentation.
3.3-72 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring.3.3-75 3.4 REACTOR COOLANT SYSTEM (RCS)................................ :.i.l.
3.4-1 3.4.1 Recirculation Loops Operating................................................. ;,. 3.4-1 3.4.2 Jet Pumps
........... 3.4-6 3.4.3 Safety/Relief Valves (S/RVs)...............................
3.4-8 3.4.4 RCS Operational LEAKAGE...............................
3.4-10 3.4.5 RCS Pressure Isolation Valve (PIV) Leakage................................
3.4-12 3.4.6 RCS Leakage Detection Instrumentation...............................
3.4-14 3.4.7 RCS Specific Activity..............
3.4-17 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown.3.4-19 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown.3.4-22 3.4.10 RCS Pressure and Temperature (PIT) Limits................................ ;.3.4-24 3.4.11 Reactor. Steam Dome Pressure...............................
3.4-31 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM.....
....................... 3.5-1 3.5.1 k
ECCS - Operating.3.5-1 3.5.2 ECCS - Shutdown...................................
3.5-8 3.5.3 RCIC System..................................
3.5-12 3.6 CONTAINMENT SYSTEMS..................................
3.6-1 3.6.1.1 Primary Containment.3.6-1 3.6.1.2 Primary Containment Air Lock..
3.6-4 3.6.1.3 Primary Containment Isolation Valves (PCI Vs)
.3.6-8 3.6.1.4 Containment Pressure.3.6-17 3.6.1.5 Drywell Air Temperature................................... ;.3.6-18 3.6.1.6 Suppression-Chamber-to-Drywell Vacuum Breakers.3.6-19 3.6.2.1 Suppression Pool Average Temperature.
3.6-22 3.6.2.2 Suppression Pool Water Level.3.6-25 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling... '.3.6-26 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray.3.6-28 3.6.3.1 Primary Containment Hydrogen Recombiners.3.6-30 3.6.3.2 Drywell Air Flow System.
3.6-32 3.6.3.3 Primary Containment Oxygen Concentration.
3.6-34 3.6.4.1 Secondary Containment.
3.6-35 3.6.4.2 Secondary Containment Isolation Valves (SCIVs).3.6-38 3.6.4.3 Standby Gas Treatment (SGT) System.3.6-42 (continued)
SUSQUEHANNA - UNIT 1 Amendment 4:4 T/ To - 7Z
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.7 PLANT SYSTEMS..
3......-1..
3~~~~~.7PATSSES.
.............................................. 3.7-1 3.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS)........................................ 4/
3.7-1 3.7.2 Emergency Service Water (ESW) System.............................
3.7-4 3.7.3 Control Room Emergency Outside Air Supply (CREOAS) System............................................................
/.. 3.7-6 3.7.4 Control Room Floor Cooling System.
3.7-10 3.7.5 Main Condenser Offgas.
3.7-13 3.7.6 Main Turbine Bypass System..
all. 3.7-15 3.7.7 Spent Fuel Storage Pool Water Level.
3.7-17 3.8 ELECTRICAL POWER SYSTEMS........................
3.8-1 3.8.1 AC Sources - Operating.
3.8-1 3.8.2 AC Sources - Shutdown.
3.8-17 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air......................................
3.8-20 3.8.4 DC Sources - Operating..........................................
3.8-23 3.8.5 DC Sources - Shutdown.........................................
3.8-29 3.8.6 Battery Cell Parameters.........................................
3.8-32 3.8.7 Distribution Systems - Operating.........................................
3.8-37 3.8.8 Distribution Systems - Shutdown.........................................
3.841 3.9 REFUELING OPERATIONS.........................................
3.9-1 3.9.1 Refueling Equipment Interlocks.........................................
3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock.........................................
3.9-3 3.9.3 Control Rod Position.........................................
3.9-5 3.9.4 Control Rod Position Indication.........................................
3.9-6 3.9.5 Control Rod OPERABILITY - Refueling..............
.......... 3.9-8 3.9.6 Reactor Pressure Vessel (RPV) Water Level.................................... 3.9-9 3.9.7 Residual Heat Removal (RHR) - High Water Level.......................... 3.9-10 3.9.8 Residual Heat Removal (RHR) - Low Water Level........................... 3.9-13 3.10 SPECIAL OPERATIONS.........................................
3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation............................ 3.10-1 3.10.2 Reactor Mode Switch Interlock Testing.........................................
3.10-4 3.10.3 Single Control Rod Withdrawal - Hot Shutdown............................... 3.10-6 3.10.4 Single Control Rod Withdrawal - Cold Shutdown.............................. 3.10-9 3.10.5 Single Control Rod Drive (CRD) Removal - Refueling...................... 3.10-13 3.10.6 Multiple Control Rod Withdrawal - Refueling.................................... 3.10-16 3.10.7 Control Rod Testing-Operating.................................
3.10-18 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling................................ 3.10-20 4.0 DESIGN FEATURES.
4.0-1 4.1 Site Location........
4.0-1 4.2 Reactor Core........
4.0-1 43 Fuel Storage........
4.0-1 (continued)
SUSQUEHANNA - UNIT 1
.,r Amendment $84
/Tc. -3
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 5.0 D
I I
T A
I E C
~
R 5.0 5.0-ADMINISTRATIVE CONTROLS.5.0-1 5.1 Responsibility..................
5.0-1 5.2 Organization.
5.0-2 5.3 Unit Staff Qualifications................
5.0-5 5.4 Procedures.
5.0-6 5.5 Programs and Manuals.................
.. 5.0-7 5.6 Reporting Requirements.................
.. 5.0-19 5.7 High Radiation Area.
5.0-27 INrM TS I lat TOT.J w FMrsI 444 TocTh.4oe.
SUSQUEHANNA - UNIT 1
- /To-+
Amendment 484-
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 1.0 1.1 1.2 1.3 1.4 2.0 2.1 2.2 3.0 3.0 3.1 3.1.1 3.1.2 3.1.3 3.1.4 3.1.5 3.1.6.
3.1.7 3.1.8 3.2 3.2.1 3.2.2 3.2.3 3.2.4 3.3 3.3.1.1 3.3.1.2
.3.2.1 3.3.2.2 3.3.3.1 3.3.3.2 3.3.4.1-3.3.4.2 3.3.5.1 3.3.5.2 3.3.6.1 3.3.6.2 3.3.7.1 USE AND APPLICATION.................
1.1-1 Definitions....
1.1-1 Logical Connectors............
1.2-1 Completion Times............
1.3-1 Frequency............
1.4-1 SAFETY LIMITS (SLs)..
./ 2.0-1 SLs................................................................................ zT 3;Z/ 2-0-1 S.s.
'SL Violations.........................................-./.TV 2.0-1 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY.....;....... 3.0-1 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY.........................
431.3.0-4 REACTIVITY CONTROL SYSTEMS................................................
3.1-1 Shutdown Margin (SDM)................................................
3.1-1 Reactivity Anomalies................................................
3.1-5 Control Rod OPERABILITY................................................
3.1-7 Control Rod Scram Times................................................
3.1-12 Control Rod Scram Accumulators................................................
3.1-15 Rod Pattern Control................................................
3.1-18 Standby Liquid Control (SLC) System............................................... 3.1-20 Scram Discharge Volume (SDV) Vent and Drain Valves................... 3.1-25 POWER DISTRIBUTION LIMITS................................................
3.2-1 Average Planar Linear Heat Generation Rate (APLHGR)................. 3.2-1 Minimum Critical Power Ratio (MCPR).............................................. 3.2-3 Linear Heat Generation Rate (LHGR)................................................ 3.2-5 Average Power Range Monitor (APRM) Gain and Setpoints............. 3.2-7 INSTRUMENTATION............................................
3.3-1 Reactor Protection System (RPS) Instrumentation............................ 3.3-1 Source Range Monitor (SRM) Instrumentation.................................. 3.3-10 Control Rod Block Instrumentation............................................
3.3-16 Feedwater - Main Turbine High Water Level Trip Instrumentation............................................
3.3-21 Post Accident Monitoring (PAM) Instrumentation.............................. 3.3-23 Remote Shutdown System............................................
3.3-27 End of Cycle Recirculation Pump Trip (EOC-RPT)
Instrumentation............................................ 3.3-30 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation.................................... 3.3-34 Emergency Core Cooling System (ECCS) Instrumentation........ ra/. 3.3-37 Reactor Core Isolation Cooling (RCIC) System Instrumentation............................................
3.3-48 Primary Containment Isolation Instrumentation q:j.3.3-52 Secondary Containment Isolation Instrumentation............................. 3.3-63 Control Room Emergency Outside Air Supply (CREOAS)
System Instrumentation............................................
3.3-67 74S*eu 4 e..ltz 4r1 m-.*
(continued)
SUSQUEHANNA - UNIT 2 Amendment 10, 1g8,40i
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.3 INSTRUMENTATION (continued) 3.3.8.1 Loss of Power (LOP) Instrumentation..................................
3.3-72 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring..................................
3.3-75 3.4 REACTOR COOLANT SYSTEM (RCS)...........................
3.4-1 3.4.1 Recirculation Loops Operating...............................................
3.4-1 3.4.2 Jet Pumps................................
3.4-6 3.4.3 Safety/Relief Valves (SIRVs).
3.4-8 3.4.4 RCS Operational LEAKAGE.3.4-10 3.4.5 RCS Pressure Isolation Valve (PIV) Leakage.
3.4-12 3.4.6 RCS Leakage Detection Instrumentation.3.4-14 3.4.7 RCS'Specific Activity.
3.4-17 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown 3.4-19 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown.3.4-22 3.4.10 RCS Pressure and Temperature (P/T) Limits.3.4-24 3.4.11 Reactor Steam Dome Pressure.....................
3.4-31 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM...................................... 3.5-1 3.5.1 ECCS - Operating............................................
3.5-1 3.5.2 ECCS - Shutdown............................................
3.5-8 3.5.3 RCIC System........
3.5-12 3.6 CONTAINMENT SYSTEMS........
3.6-1 3.6.1.1 Primary Containment........
3.6-1 3.6.1.2 Primary Containment Air Lock........
3.6-4 3.6.1.3 Primary Containment Isolation Valves (PCIVs)....
.TS. 3.6-8 3.6.1.4 Containment Pressure........
3.6-17 3.6.1.5 Drywell Air Temperature........
3.6-18 3.6.1.6 Suppression-Chamber-to-Drywell Vacuum Breakers........
3.6-19.
3.6.2.1 Suppression Pool Average Temperature........
3.6-22 3.6.2.2 Suppression Pool Water Level.......
. 3.6-25 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling.......... 3.6-26 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray........
3.6-28 3.6.3.1 Primary Containment Hydrogen Recombiners........
3.6-30 3.6.3.2 Drywell Air Flow System........
3.6-32 3.6.3.3 Primary Containment Oxygen Concentration.3.6-34 3.6.4.1 Secondary Containment........
3.6-35 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)............................. 3.6-38 3.6.4.3 Standby Gas Treatment (SGT) System...................................
3.6-42 (continued)
SUSQUEHANNA-UNIT 2 Amendment 1i1, i.
1trbc-- z
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.7 PLANT SYSTEMS..................................
.3.7-1 3.7.1 Residual Heat Removal Service Water (RHRSW) System and the Ultimate Heat Sink (UHS)...............................3.7-1 3.7.2 Emergency Service Water (ESW) System
.......................... 3.7-4 3.7.3 Control Room Emergency Outside Air Supply (CREOAS) System...........................-/3.7-6 3.7.4 Control Room Floor Cooling System..
3.7-10 3.7.5 Main Condenser Offgas.
3.7-13 3.7.6 Main Turbine Bypass System.................................. M;... 3.7-15 3.7.7 Spent Fuel Storage Pool Water Level..
3.7-17 3.8 ELECTRICAL POWER SYSTEMS.
3.8-1 3.8.1 AC Sources - Operating.
3.8-1 3.8.2 AC Sources - Shutdown.
3.8-19 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air 3.8-23 3.8.4 DC Sources - Operating..
3.8-26 3.8.5 DC Sources - Shutdown.
3.8-34 3.8.6 Battery Cell Parameters.3.8-39 3.8.7 Distribution Systems - Operating.
3.8-44 3.8.8 Distribution Systems - Shutdown.................................
3.8-50 3.9 REFUELING OPERATIONS..
3.9-1 3.9.1 Refueling Equipment Interlocks..
3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock..
3.9-3 3.9.3 Control Rod Position 3.9-5 3.9.4 Control Rod Position Indication 3.9-6 3.9.5 Control Rod OPERABILITY - Refueling 3.9-8 3.9.6 Reactor Pressure Vessel (RPV) Water Level 3.9-9 3.9.7.
Residual Heat Removal (RHR) - High Water Level.
3.9-10 3.9.8 Residual Heat Removal (RHR) - Low Water Level.
3.9-13 3.10 SPECIAL OPERATIONS.............................................
- 3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation............................. 3.10-1 3.10.2 Reactor Mode Switch Interlock Testing............................................
3.10-4 3.10.3 Single Control Rod Withdrawal - Hot Shutdown................................ 3.10-6 3.10.4 Single Control Rod Withdrawal - Cold Shutdown..............................1..
3.0-9 3.10.5 Single Control Rod Drive (CRD) Removal - Refueling...................... 3.10-13 3.10.6 Multiple Control Rod Withdrawal - Refueling.................................... 3.10-16 3.10.7 Control Rod Testing -Operating............................................
3.10-18 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling................................ 3.10-20 4.0 DESIGN FEATURES...........................................................................
- /.. 4.0-1 4.1 Site Location................................................................................
4.0-1 4.2 Reactor Core.................
0-1 4.3 Fuel Storage.
4.0-1 (continued)
SUSQUEHANNA-UNIT 2 Amendment 151, *B-
'13 1Toc-3
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 5.0 5.1 5.2 5.3 5.4 5.5 5.6 5.7 ADMINISTRATIVE CONTROLS......................
5.0-1 Responsibility....................................................................................... 5.0-1 Organization......................
5.0-2 Unit Staff Qualifications......................
5.0-5 Procedures........................................................................................... 5.0-6 Programs and Manuals......................
5.0-7 Reporting Requirements......................
5.0-19 High Radiation Area.......................................................................
5.0-24
-Nft0UF IrL Text I..du.--
pfM-sz 2
4 Tv
-TS.doc SUSQUEHANNA - UNIT 2 1*Toc - +
Amendment 1A1,
jucx
Attachment B Proposed Technical Specification Changes (Camera Ready)
Table of Contents (TOC)
(Units 1 & 2)
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 1.0 USE AND APPLICATION................................................
1.1-1 1.1 Definitions...'..-1.1..-1.................................................................................... 1.1-1 1.2 Logical Connectors.................................................
1.2-1 1.3 Completion Times.................................................
1.3-1 1.4 Frequency................................................
1.4-1 2.0 SAFETY LIMITS (SLs).................................................. TS/2.0-1 2.1 SLs................................................
TS/2.0-1 2.2 SL Violations................................................
TS/2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY.............. 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY....................... TS/3.0-4 3.1 REACTIVITY CONTROL SYSTEMS................................................
3.1-1 3.1.1 Shutdown Margin (SDM)................................................
3.1-1 3.1.2 Reactivity Anomalies................................................
3.1-5 3.1.3 Control Rod OPERABILITY..........................
....................... 3.1-7 3.1.4 Control Rod Scram Times................................................
3.1-12 3.1.5 Control Rod Scram Accumulators................................................. 3.1-15 3.1.6 Rod Pattern Control................................................ 3.1-18 3.1.7 Standby Liquid Control (SLC) System............................................... 3.1-20 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves................... 3.1-25 3.2 POWER DISTRIBUTION LIMITS................................................
3.2-1 3.2.1 Avrage Planar Linear Heat Generation Rate (APLHGR)..........
....... 3.2-1 3.2.2 Minimum Critical Power Ratio (MCPR).............................................. 3.2-3 3.2.3 Linear Heat Generation Rate (LHGR)...............................................
3.2-5 3.2.4 Average Power Range Monitor (APRM) Gain and Setpoints............. 3.2-7 3.3 INSTRUMENTATION................................................ 3.3-1 3.3.1.1 Reactor Protection System (RPS) Instrumentation............................ 3.3-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation.................................. 3.3-10 3.3.1.3 Oscillation Power Range Monitor (OPRM)
Instrumentation.
TS/3.3-1 5a 3.3.2.1 Control Rod Block Instrumentation.3.3-16 3.3.2.2 Feedwater - Main Turbine High Water Level Trip Instrumentation..................................
3.3-21 3.3.3.1 Post Accident Monitoring (PAM) Instrumentation.............................. 3.3-23 3.3.3.2 Remote Shutdown System..................................
3.3-26 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)
Instrumentation..
3.3-29 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation..................................... 3.3-33 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation............... 3.3-36 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation...................................
3.3-48 3.3.6.1 Primary Containment Isolation Instrumentation............................ TS/3.3-52 3.3.6.2 Secondary Containment Isolation Instrumentation............................
3.3-63 (continued)
SUSQUEHANNA - UNIT 1 TS/TOC-1 Amendment 1%4, g* I SUSQUEHANNA - UNIT 1 TS/ TOC-I Amendment 1y/4, 2,*
l
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.3.7.1 Control Room Emergency Outside Air Supply (CREOAS)
Systerm Instrumentation......................................
3.3-67 3.3 INSTRUMENTATION (continued) 3.3.8.1 Loss of Power (LOP) Instrumentation.
3.3-72 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring.3.3-75 3.4 REACTOR COOLANT SYSTEM (RCS).
TS/3.4-1 3.4.1 Recirculation Loops Operating.TS/3.4-1 3.4.2 Jet Pumps.3.4-6 3.4.3 Safety/Relief Valves (S/RVs).3.4-8 3.4.4 RCS Operational LEAKAGE.
3.4-10 3.4.5 RCS Pressure Isolation Valve (PIV) Leakage.
3.4-12 3.4.6 RCS Leakage Detection Instrumentation.
3.4-14 3.4.7 RCS Specific Activity.3.4-17 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown...............
3.4-19 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling System - Cold Shutdown.
3.4-22 3.4.10 RCS Prsssure and Temperature (PIT) Limits.3.4-24 3.4.11 Reactor Steam Dome Pressure.
3.4-31 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM.3.5-1 3.5.1 ECCS - Operating.
3.5-1 3.5.2 ECCS - Shutdown.
3.5-8 3.5.3 RCIC System.
3.5-12 3.6 CONTAINMENT SYSTEMS....................................................................3.6-1 3.6.1.1 Primary Containment.
3.6-1 3.6.1.2 Primary Containment Air Lock.3.6-4 3.6.1.3 Primary Containment Isolation Valves (PCIVs).
TS/3.6-8 3.6.1.4 Containment Pressure.
3.6-17 3.6.1.5 Drywell Air Temperature.
3.6-18 3.6.1.6 Suppression-Chamber-to-Drywell Vacuum Breakers.
3.6-19 3.6.2.1 Suppression Pool Average Temperature.
3.6-22 3.6.2.2 Suppression Pool Water Level.3.6-25 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling.
TS/3.6-26 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray.3.6-28 3.6.3.1 Primary Containment Hydrogen Recombiners.
3.6-30 3.6.3.2 Drywell Air Flow System.
3.6-32 3.6.3.3 Primary Containment Oxygen Concentration.
3.6-34 3.6.4.1 Secondary Containment.3.6-35 3.6.4.2 Secondary Containment Isolation Valves (SCIVs).3.6-38 3.6.4.3 Standby Gas Treatment (SGT) System.3.6-42 (continued)
SUSQUEHANNA -
UNIT 1 TS/TOC-2 Amendment I84 I SUSQUEHANNA -UNIT 1 TS /TOC -2 Amendment W4 I
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.7 PLANT SYSTEMS............................................
TS/3.7-1 3.7.1 Residual Heat Removal Service Water (RHRSW) System and theUltirniate Heat Sink (UHS)
TS/3.7-1 3.7.2 Emergency Service Water (ESW) System.
3.7-4 3.7.3 Control Room Emergency Outside Air Supply (CREOAS) System...........................................
TS/3.7-6 3.7.4 Control Room Floor Cooling System...........................................
3.7-10 3.7.5 Main Condenseai Offgas...........................................
3.7-13 3.7.6 Main Turbine Bypass Systern...........................................
TS/3.7-15 3.7.7 Spent Fuel Storage Pool Water Level...........................................
3.7-17 3.8 ELECTRICAL POWER SYSTEMS............................................
3.8-1 3.8.1 AC Sources - Operating...........................................
3.8-1 3.8.2 AC Sources - Shutdown...........................................
3.8-17 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air.................................... TS/3.8-20 3.8.4 DC Sources - Operating...........................................
3.8-23 3.8.5 DC Sources - Shutdown............................................
3.8-29 3.8.6 Battery Cell Parameters............................................
3.8-32 3.8.7 Distribution Systems - Operating...........................................
3.8-37 3.8.8 Distribution Systems - Shutdown...........................................
3.8-41 3.9 REFUELING OPERATIONS...................................................................3.9-1 3.9.1 Refueling Equipment Interlocks...........................................
3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock...........................................
3.9-3 3.9.3 C
.ontrol Rod Position...........................................
3.9-5 3.9.4 Control Rod Position Indication...........................................
3.9-6 3.9.5 Control Rod OPERABILITY - Refueling........................................... 3.9-8 3.9.6 Reactor Pressure Vesse! (RPV) Water Level.................................... 3.9-9 3.9.7 Residual Heat Removal (RHR) - High Water Level.......... :................ 3.9-10 3.9.8 Residual Heat Removal (RHR) - Low Water Level........................... 3.9-13 3.10 SPECIAL OPERATIONS...........................................
3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation............................ 3.10-1 3.10.2 Reactor Mode Switch Interlock Testing............................................
3.10-4 3.10.3 Single Control Rod Withdrawal - Hot Shutdown............................... 3.10-6 3.10.4 Single Control Rod Withdrawal - Cold Shutdown.............................. 3.10-9 3.10.5 Single Control Rod Drive (CRD) Removal - Refueling...................... 3.10-13 3.10.6 Multiple Control Rod Withdrawal - Refueling.................................... 3.10-16 3.10.7 Control Rod Testing-Operating...........................................
3.10-18 3.10.8 SHUTDOWN MARGIN (SDM) Test-Refueling................................ 3.10-20 4.0 DESIGN FEATURES...........................................
4.0-1 4.1 Site Location...........................................
4.0-1 4.2 Reactor Core...........................................
4.0-1 4.3 Fuel Storage...........................................
4.0-1 (continued)
SUSQUEHANNA
- UNIT 1 TS/TOC-3 Amendment 1,84 I SUSQUEHANNA -UNIT 1 TS /TOC -3 Amendment 1At4 l
.4 TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 5.0 5.1 5.2 5.3 5.4 5.5 5.6 5.7 ADMINISTRATIVE CONTROLS.....................
5.0-1 Responsibility....................................................................................... 5.0-1 Organization.........
5.0-2 Unit Staff Qualifications................
5.0-5 Procedures.......................................................................................... 5.0-6 Programs and Manuals................
5.0-7 Reporting Requirements................
5.0-19 High Radiation Area................
5.0-27 NFM TSI text TOC TS.doc SUSQUEHANNA - UNIT 1 TS /TOC -4 Amendment 18,4 l
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 1.0 USE AND APPLICATION.................
1.1-1 1.1 Definitions.................
1.1-1 1.2 Logical Con`e tors.........................................o i..............................
1.2-1 1.3 Completion Times................
1.3-1 1.4 Frequency................
1.4-1 2.0 SAFETY LIMITS (SLs)..................
TS/2.0-1 2.1 SLs.................
TS/2.0-1 2.2 SL Violations................
TS/2.0-1 3.0 LIMITING CONDITiON FOR OPERATICN (LCO) APPLICABILITY 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY.TS/3.0-4 3.1 REACTIVITY CONTROL SYSTEMS.3.1-1 3.1.1 Shutdown Margin (SDM).3.1-1 3.1.2 Reactiviy Anomalies.3.1-5 3.1.3 Control Rod OPERABILITY.3.1-7 3.1.4 Control Rod Scram Times.3.1-12 3.1.5 Control Rod Scram Accumulators.3.1-15 3.1.6 Rod Pattern Control.3.1-18 3.1.7 Standby Liquid Control (SLC) System.3.1-20 3.1.8 Scram Discharge Volume (SDV) Vent and Drain Valves.
3.1-25 3.2 POWER DISTRIBUTION LIMITS.3.2-1 3.2.1 Average Planar Linear Heat Generation Rate (APLHGR).3.2-1 3.2.2 Minimum Critical Power Ratio (MCPR).3.2-3 3.2.3 Linear Heat Generation Rate (LHGR).3.2-5 3.2.4 Average Power Range Monitor (APRM) Gain and Setpoints 3.2-7 3.3 INSTRUMENTATION.3.3-1 3.3.1.1 Reactor Protection System (RPS) Instrumentation.3.3-1 3.3.1.2 Source Range Monitor (SRM) Instrumentation.................................. 3.3-10 3.3.1.3 Oscillation ?ower Range Monitor (OPRM)
Instrumentation.........................
TS/3.3-1 5a 3.3.2.1 Control Pod Block Instrumentation.......................
3.3-16 3.3.2.2 Feedwater - Main Turbine High Water Level Trip Instrumentation..................................
3.3-21 3.3.3.1 Post Accident Mor itoring (PAM) Instrumentation.............................. 3.3-23 3.3.3.2 Remote Shutdown System..................................
3.3-27 3.3.4.1 End of Cycle Recirculation Pump Trip (EOC-RPT)
Instrumentation..
3.3-30 3.3.4.2 Anticipated Transient Without Scram Recirculation Pump Trip (ATWS-RPT) Instrumentation.................................... 3.3-34 3.3.5.1 Emergency Core Cooling System (ECCS) Instrumentation.......... TS/3.3-37 3.3.5.2 Reactor Core Isolation Cooling (RCIC) System Instrumentation...................................
3.3-48 3.3.6.1 Primary Containment Isolation Instrumentation............................ TS/3.3-52 3.3.6.2 Secondary Containment Isolation Instrumentation............................
3.3-63 3.3.7.1 Control Room Emergency Outside Air Supply (CREOAS)
System Instrumentation..
3.3-67 (continued)
SUSQUEHANNA
- UNIT 2 TS/TOC-1 Amendment i1, 1%8, 19A I SUSQUEHANNA -UNIT 2 TS/TOC - I Amendment I
, 1 ', 19, 1
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.3 INSTRUMENTATION (continued) 3.3.8.1 Loss of Power (LOP) Instrumentation.
3.3-72 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring.3.3-75 3.4 REACTOR COOLANT SYSTEM (RCS)..................................
TS/3.4-1l 3.4.1 Recirculation Loops Operating..................................
TS/3.4-1 3.4.2 Jet Pumps..................................
3.4-6 3.4.3 Safety/Relief Valves (S/RVs)..................................
3.4-8 3.4.4
- RCS Operational LEAKAGE..................................
3.4-10 3.4.5 RCS Pressure Isolation Valve (PIV) Leakage.................................. 3.4-12 3.4.6 RCS Leakago Dotection Instrumentation..................................
3.4-14 3.4.7 RCS Specific Activity...................................
3.4-17 3.4.8 Residual Heat Removal (RHR) Shutdown Cooling System - Hot Shutdown.3.4-19 3.4.9 Residual Heat Removal (RHR) Shutdown Cooling Systern - Cold Shutdown.
3.4-22 3.4.10 RCS Pressure and Temperature (P/T) Limits...............................
3.4-24 3.4.11 Reactor Steam Dome Pressure...............................
3.4-31 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM.................................
3.5-1 3.5.1 ECCS - Operating.
3.5-1 3.5.2 ECCS - Shutdown........................................
3.5-8 3.5.3 RCIC System.
3.5-12 3.6 CONTAINMENT SYSTEMS.3.6-1 3.6.1.1 Primary Containment.
3.6-1
.3.6.1.2 Primary Containment Air Lock.3.6-4 3.6.1.3-Primary Containment Isolation Valves (PCIVs)
.TS/3.6-8 3.6.1.4 Containment Pressure........................................
3.6-17 3.6.1.5 Drywell Air Temperature 3.6-18 3.6.1.6 Suppression-Chamber-to-Drywell Vacuum Breakers.
3.6-19 3.6.2.1 Suppression Pool Average Temperature.
3.6-22 3.6.2.2 Suppression Pool Water Level.3.6-25 3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling.....
TS/3.6-26 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray.....
3.6-28 3.6.3.1 Primary Containment Hydrogen Recombiners.....
3.6-30 3.6.3.2 Drywell Air Flow System..........................................-.
..... 3.6-32 3.6.3.3 Primary Containment Oxygen Concentration.....
3.6-34 3.6.4.1 Secondary Containment.....
3.6-35 3.6.4.2 Secondary Containment Isolation Valves (SCIVs).....
3.6-38 3.6.4.3 Standby Gas Treatment (SGT) System.....
3.6-42 (continued)
SUSQUEHANNA
- UNIT 2 TSITOC -2 Amendment ii, 1X8 I SUSQUEHANNA -UNIT 2 TS/TOC - 2 Amendment 101, 1fiA I
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 3.7 PLANT SYSTEMS................................
TS/3.7-1l 3.7.1 Residual Heat Removal Service Water (RHRSW) System and th6eUfiimate Heat Sink (UHS).............................. '... TS/3.7-1 3.7.2 Emergency Service Water (ESW) System.............................
3.7-4 3.7.3 Control Room Emergency Outside Air Supply (CREOAS) System...........................................
TS/3.7-6 3.7.4 Control Room Floor Cooling System...........................................
3.7-10 3.7.5 Main Condenser Offgas...........................................
3.7-13 3.7.6 Main Turbine Bypass Systom.......................................................TS/3.7-15 3.7.7 Spent Fuel Storage Pool Water Level............................................
3.7-17 3.8 ELECTRICAL. POWER SYSTEMS............................................
3.8-1 3.8.1 AC Sources - Operating............................................
3.8-1 3.8.2 AC Sources - Shutdown.............................................
3.8-19 3.8.3 Diesel Fuel Oil, Lube Oil, and Starting Air.TS/3.8-23 3.8.4 DC Sources - Operating.
3.8-26 3.8.5 DC Sources - Shutdown.3.8-34 3.8.6 Batte.-y Cell Parameters.
3.8-39 3.8.7 Distribution Systems - Operating......................................................3.8-44 3.8.8 Distribution Systems - Shutdown.3.8-50 3.9 REFU1-7ING OPERATIONS.3.9-1 3.9.1 Refueling Equipment Interlocks.3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock.
3.9-3 3.9.3 Control Rod Position.
3.9-5 3.9.4 Control Rod Position Indication.3.9-6 3.9.5 Control Rod OPERABILITY-Refueling............................................3.9-8 3.9.6 Reactor Pressure Vessel (P.PV) Water Level.
3.9-9 3.9.7 Residual Heat Removal (RHR) - High Water Level.
3.9-10 3.9.8 Residual Heat Removal (RHR) - Low Water Level.
3.9-13 3.10 SPECIAL OPERATIONS.
3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation.
3.10-1 3.10.2 Reactor Mode Switch Interlock Testing.
3.10-4 3.10.3 Single Control Rod Withdrawal - Hot Shutdown.
3.10-6 3.10.4 Single Control Rod Withdrawal - Cold Shutdown.3.10-9 3.10.5 Single Control Rod Drive (CRD) Removal - Refueling.3.10-13 3.10.6 Multiple Control Rod Withdrawal - Refueling.
3.10-16 3.10.7 Control Rod Testing - Operating.3.10-18 3.10.8 SHUTDOWN MARGIN (SDM) Test-Refueling.3.10-20 4.0 DESIGN FEATURES.
TS/4.0-1 4.1 Site Location.
TS/4.0-1 4.2 Reactor Core.
TS/4.0-1 4.3 Fuel Storage.
TS/4.0-1 (continued)
SUSQUEHANNA - UNIT 2 TSITOC -3 Amendment 1, 1..'8 I SUSQUEHANNA -UNIT 2 TS/TOG - 3 Amendment 1 R1, tW85 I
TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 5.0 5.1 5.2 5.3 5.4 5.5 5.6 5.7 ADMINISTRATIVE CONTROLS......................
5.0-1 Responsibility....................................................................................... 5.0-1 Organization.!..;
.................. i:;;.:.5.0-2 Unit Staff Qualifications................
5.0-5 Procedures................
5.0-6 Programs and Manuals................
5.0-7 Reporting Requirements......
.. 5.0-19 High Radiation Area.................
TS/5.0-24 I
NFM TS2 Text TOC TS.doc SUSQUEHANNA - UNIT 2 TS/TOC - 4 Amendment 1di', le8 I