PLA-5785, Table of Contents Revisions Proposed Amendment No. 259 and Proposed Amendment No. 224 Revised Response to GL 94-02: Long-Term Stability Solution PLA-5785

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Table of Contents Revisions Proposed Amendment No. 259 and Proposed Amendment No. 224 Revised Response to GL 94-02: Long-Term Stability Solution PLA-5785
ML042160218
Person / Time
Site: Susquehanna  Talen Energy icon.png
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)
v • d • e


Text

Bryce L Shriver PPL Susquehanna, LLC Senior Vice President and 769 Salem Boulevard Chief Nuclear Officer Berwick, PA 18603 Tel. 570.542.3120 Fax 570.542.1504 bishriver@pplweb.com pP IIm-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, "ProposedAmendenent No. 259 to License NFP-14and ProposedAmendment 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

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is ; - v Attachment A Proposed Technical Specification Changes (Markups)

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 1.2 Logical Connectors ............  ;; 1.2-1 1.3 Completion Times ............ 1.3-1 1.4 Frequency............................................................................................. 1.4-1 2.0 SAFETY LIMITS (SLs) .................  ;- /2.0-1 2.1 SLs .. fi;,( 2.0-1 2.2 SL Violations.........................;......................................................... 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ...... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY.................... . 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 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 3.3.2.1 Control Rod Block Instrumentation ......................................... 3.3-16 I

3.3.2.2 Feedwater- Main Turbine High Water Level Trip Instrumentation.........3.3-21 Instrumentation~~~.........................................................................................332 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

System Instrumentation .......................................... 3.3-67

3. 3. 1 3

'-(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~~~~~.7PATSSES. .............................................. 3.7-1 3......-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 Amendment 484-

- /To-+

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 1.0 USE AND APPLICATION ................. 1.1-1 1.1 Definitions.... .. . 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) .. ................. ./ 2.0-1 2.1 SLs ................................................................................ zT3;Z/2-0-1 2.2 S.s.

'SL Violations.........................................-./.TV 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY.....; ....... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ......................... 431.3.0-4 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 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

.3.2.1 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 ............................................ 3.3-27 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 ........ ra/. 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 '...........................

q:j.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 4 e..ltz 74S*eu m-.* , 4r1 .. . . - -- (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 ..............................13.0-9 ..

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-

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 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....................................................................... 5.0-24

-Nft0UFIrL Text I..du.--

pfM-sz 2 4 Tv

-TS.doc SUSQUEHANNA - UNIT 2 Amendment 1A1, 1*Toc - +

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)

UNIT 11 TS/TOC-1 Amendment 1%4, g* I SUSQUEHANNA - UNIT SUSQUEHANNA -

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)

UNIT 1 TS/TOC-3 Amendment 1,84 I SUSQUEHANNA -UNIT SUSQUEHANNA -

1 TS /TOC -3 Amendment 1At4 l

.4 TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 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 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 i..............................

Con`e tors.........................................o 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)

TS/TOC-1 Amendment i1, 1%8, 19A I SUSQUEHANNA -UNIT SUSQUEHANNA - UNIT 2 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)

UNIT 2 TSITOC -2 Amendment ii, 1X8 I SUSQUEHANNA 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)

TSITOC -3 Amendment 1, 1..'8 I SUSQUEHANNA SUSQUEHANNA -UNIT

- UNIT 22 TS/TOG - 3 Amendment 1R1, tW85 I

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 5.0 ADMINISTRATIVE CONTROLS ...................... 5.0-1 5.1 Responsibility....................................................................................... 5.0-1 5.2 Organization .!..; .................. i:;;.:.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 ................. TS/5.0-24 I NFM TS2 Text TOC TS.doc SUSQUEHANNA - UNIT 2 TS/TOC - 4 Amendment 1di', le8 I

Text

Bryce L Shriver PPL Susquehanna, LLC Senior Vice President and 769 Salem Boulevard Chief Nuclear Officer Berwick, PA 18603 Tel. 570.542.3120 Fax 570.542.1504 bishriver@pplweb.com pP IIm-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, "ProposedAmendenent No. 259 to License NFP-14and ProposedAmendment 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 USE AND APPLICATION ................. 1.1-1 1.1 Definitions............................................................................................ 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) .................  ;- /2.0-1 2.1 SLs .. fi;,( 2.0-1 2.2 SL Violations.........................;......................................................... 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY ...... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY.................... . 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 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 3.3.2.1 Control Rod Block Instrumentation ......................................... 3.3-16 I

3.3.2.2 Feedwater- Main Turbine High Water Level Trip Instrumentation.........3.3-21 Instrumentation~~~.........................................................................................332 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

System Instrumentation .......................................... 3.3-67

3. 3. 1 3

'-(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~~~~~.7PATSSES. .............................................. 3.7-1 3......-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 Amendment 484-

- /To-+

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 1.0 USE AND APPLICATION ................. 1.1-1 1.1 Definitions.... .. . 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) .. ................. ./ 2.0-1 2.1 SLs ................................................................................ zT3;Z/2-0-1 2.2 S.s.

'SL Violations.........................................-./.TV 2.0-1 3.0 LIMITING CONDITION FOR OPERATION (LCO) APPLICABILITY.....; ....... 3.0-1 3.0 SURVEILLANCE REQUIREMENT (SR) APPLICABILITY ......................... 431.3.0-4 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 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

.3.2.1 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 ............................................ 3.3-27 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 ........ ra/. 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 '...........................

q:j.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 4 e..ltz 74S*eu m-.* , 4r1 .. . . - -- (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 ..............................13.0-9 ..

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-

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 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....................................................................... 5.0-24

-Nft0UFIrL Text I..du.--

pfM-sz 2 4 Tv

-TS.doc SUSQUEHANNA - UNIT 2 Amendment 1A1, 1*Toc - +

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)

UNIT 11 TS/TOC-1 Amendment 1%4, g* I SUSQUEHANNA - UNIT SUSQUEHANNA -

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)

UNIT 1 TS/TOC-3 Amendment 1,84 I SUSQUEHANNA -UNIT SUSQUEHANNA -

1 TS /TOC -3 Amendment 1At4 l

.4 TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 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 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 i..............................

Con`e tors.........................................o 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)

TS/TOC-1 Amendment i1, 1%8, 19A I SUSQUEHANNA -UNIT SUSQUEHANNA - UNIT 2 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)

UNIT 2 TSITOC -2 Amendment ii, 1X8 I SUSQUEHANNA 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)

TSITOC -3 Amendment 1, 1..'8 I SUSQUEHANNA SUSQUEHANNA -UNIT

- UNIT 22 TS/TOG - 3 Amendment 1R1, tW85 I

TABLE OF CONTENTS (TECHNICAL SPECIFICATIONS) 5.0 ADMINISTRATIVE CONTROLS ...................... 5.0-1 5.1 Responsibility....................................................................................... 5.0-1 5.2 Organization .!..; .................. i:;;.:.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 ................. TS/5.0-24 I NFM TS2 Text TOC TS.doc SUSQUEHANNA - UNIT 2 TS/TOC - 4 Amendment 1di', le8 I

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