ML033070341

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TRM1 - Technical Requirements Manual, Susquehanna, Unit 1
ML033070341
Person / Time
Site: Susquehanna Talen Energy icon.png
Issue date: 10/27/2003
From:
Susquehanna
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML033070341 (42)
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Text

Oct. 27, 2003 Page 1 of 2 K> bs/0 fr MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2003-50181 USER INFORMATIONM GER rH*RO M EMPL#:28401 CA#: 0363 Address UCSA2 Phon 254 94 TRANSMITTAL INFORMATION:

TO: a 1 10/27/2003 LOCATION: USNRC vROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER NUCSA-2)

K1-HE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU:

TRM1 - TECHNICAL REQUIREMENTS MANUAL UNIT 1 REMOVE MANUAL TABLE OF CONTENTS DATE: 10/03/2003 ADD MANUAL TABLE OF CONTENTS DATE: 10/24/2003 CATEGORY: DOCUMENTS TYPE: TRM1 ID: TEXT 2.2 REMOVE: REV:0 ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRMI ID: TEXT 3.3.11 REMOVE: REV:0 ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM1 ID: TEXT 3.3.6 REMOVE: REV:0 ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM1 ID: TEXT 3.3.8 REMOVE: REV:O DD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM1

Oct. 27, 2003 Page 2 of 2 ID: TEXT B3.3.11 REMOVE: REV:0 ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM1 ID: TEXT B3.3.6 REMOVE: REV:0 ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM1 ID: TEXT B3.3.8 REMOVE: REV:0 ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM1 ID: TEXT LOES REMOVE: REV:0 ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM1 ID: TEXT TOC REMOVE: REV:0 ADD: REV: 1 UPDATES FOR HARD COPY MANUALS WILL BE DISTRIBUTED WITHIN 5 DAYS IN ACCORDANCE WITH DEPARTMENT PROCEDURES. PLEASE MAKE ALL CHANGES AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX UPON RECEIPT OF HARD COPY. FOR ELECTRONIC MANUAL USERS, ELECTRONICALLY REVIEW THE APPROPRIATE DOCUMENTS AND ACKNOWLEDGE COMPLETE IN YOUR NIMS INBOX.

SUSQUEHANNA STEAM ELECTRIC STATION TABLE OF COITENTS (TECHNICAL REQUIREMENTS MANUAL)

SECTION TITLE PAGE 1.0 USE AND APPLICATION .................................. TRM/1.0-1 1.1 Definitions .............  ; TRM/1.0-2 2.0 PLANT PROGRAMS ............. 2.0-1 2.1 Planf Programs ............. 2.0-1 2.2 Instrument Trip Setpoint Table .. TRM/2.0-5 3.0 APPLICABILITY . . .TRM/3.0-1 3.0 . TRO) - TR for Operation (TRO) Applicability . TRM13.0-1 3.0 (TRS) - TR Surveillance (TRS) Applicability .....................................TRM/3.0-3 3.1 REACTIVITY CONTROL SYSTEMS .................... ................................. 3.1-1 3.1.1 Alternate Rod Injection....................:............ ............................ 3.1-1 3.1.2 CRD Housing Support..............................3............ .............................. 3.1-4 3.1.3 Control Rod Block Instrumentation . ............... ........... 3.1-5 3.1.4 Control Rod Scram Accumulators Instrumentation and Check Valve ............................................... TRM/3.1 -9 A ~~ I,!

/

3.2 - CORE OPERATING LIMITS REPO .................................................. TRM/3.2-1 3.2.1 Core Operating Limits Report ...................... . TRM/3.2-1 3.3 INSTRUMENTATION.... .... ................... ,.';.;. TRM/3.3-1 3.3.1 Radiation Monitoning Instrumentation.  ; ..... TRM/3.3-1 3.3.2 Seismic Monitoring Iristrumentation ..........................  ;--------;---------TRM/3.3-4 3.3.3 Meteorologica Monitorifig Instrumentation ................................ 3.3-7 3.3.4 TRM Post-Accide'htMonitoing Instrumentation .................................. TRM/3.3-9 3.3.5 Sectio 'Not Used ............... ........ TRM/3.3-12 3.3.6 TRM Containment Isolation Instrumentation .TRM/3.3-13 3.3.7 TurbineOverspeed Protection System . TRM/3.3-17 3.3.8 Iecion Not Used .TRM/3.3-19 3.3.9 s-'LPRM'Upscale Alarm Instrumentation .3.3-22 3.3.10 v Reactor Recirculation Pump MG Set Electrical and Mechanical Stops .......................... TRM/3.3-23 3.3.11 A.MVP Isolation Instrumentation .TRM/3.3-25 3.4 REACTOR COOLANT SYSTEM ........................... 3.4-1 3.4.1 Reactor Coolant System Chemistry ........................ 3.4-1 3.4.2 Structural Integrity ........................ 3.4-6

  • 3.4.3 High/Low Pressure Interface Leakage Monitors ................................. 3.4-9 3.4.4 Reactor Recirculation Flow and Rod Line Limit ................................. 3.4-12 3.4.5 Reactor Vessel Material Surveillances Program ................................. 3.4-13 EFFECTIVE DATE 10/2/2003 SUSQUEHANNA - UNIT SUSQUEHANNA -

UNIT 1 i EFFECTIVE DATE 10/22/2003

SUSQUEHANNA STEAM ELECTRIC STATION TABLE OFCONTENTS (TECHNICAL REQUIREMENTS MANUAL)

SECTION TITLE PAGE 3.5 EMERGENCY CORE COOLING AND RCIC ........................................ ; 3.5-1 3.5.1 ADS Manual Inhibit ....................................... 3.5-1 3.5.2 ECCS and RCIC System Monitoring Instrumentation .3.5-3 3.5.3 Long Term Nitrogen Supply to ADS ....................................... 3.5-6 3.6 CONTAINMENT .3.6-1 3.6.1 VENTING or PURGING. 3.6-1 3.6.2 Suppression Chamber-to-Drywell Vacuum Breaker Position Indication .3.6-2 3.6.3 Suppression Pool Alarm Instrumentation .3.6-3 3.6.4 Primary Containment Closed System Boundaries .............................. TRMJ3.6-6 3.7 PLANT SYSTEMS ................................... 3.7-1 3.7.1 Emergency Service Water System (Shutdown) ................................... 3.7-1 3.7.2 Ultimate Heat Sink and Ground Water Level ................................... 3.7-3 3.7.3.1 Fire Suppression Water Supply System .............................TRM/3.7-4 3.7.3.2 Spray and Sprinkler Systems ............................. TRM/3.7-8 3.7.3.3 C02 systems..................................................................................... TRM/3.7-12 3.7.3.4 Halon Systems ............................ TRM/3.7-16 3.7.3.5 Fire Hose Stations ........... TRM/3.7-18 3.7.3.6 Yard Fire Hydrants and Hydrant Hose Houses ................................ TRM/3.7-22 3.7.3.7 Fire Rated Assemblies ................ TRM/3.7-24 3.7.3.8 Fire Detection Instrumentation ...................... TRM/3.7-26 3.7.4 Solid Radwaste System . ................ TRM/3.7-35 3.7.5.1 Main Condenser Offgas Hydrogen Monitor .............................. 3.7-38 3.7.5.2 Main Condenser Explosive Gas Mixture ............................. 3.7-39 3.7.5.3 Liquid Holdup Tanks ..................

.;.3.7-40 3.7.6 ESSWPuniphouse Ventilation.......................
.. TRM/3.7-41 3.7.7 Main Condenser Offgas Pretreatment Logarithmic Radiation Monitoring Instrumentation ................. 3.7-42 3.7.8 Snubbers ................. 3.7-44 3.7.9 Control Structure HVAC ................. TRM/3.7-50 3.7.10 Spent Fuel Storage Pools ................. TRM/3.7-52 ii EFFECTIVE DATE 10/22/2003 UNIT 11 SUSQUEHANNA - UNIT ii .EFFECTIVE DATE 10/22/2003

SUSQUEHANNA STEAM ELECTRIC STATION TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)

SECTION TITLE PAGE 3.8 ELECTRICAL POWER . . . TRM/3.8-1 3.8.1 Primary Containment Penetration Conductor Overcurrent Protective Devices ..... TRM/3.8-1 3.8.2.1 Motor Operated Valves Thermal Overload Protection -

Contfinuous ....... TRM/3.8-5 3.8.2.2 Motor Operated Valves Thermal Overload Protection -

Automatic ................................  ; TRM/3.8-1 1 3.8.3 Diesel Generator (DG) Maintenance Activities. 3.8-13 3.8.4 . 24VDC Electrical Power Subsystem .TRM/3.8-15 3.8.5 Degraded Voltage Protection . ' TRM/3.8-21, 3.8.6 Emergency Switchgear Room Cooling .......................... 3.8-24 3.9 REFUELING OPERATIONS .................. 3.9-1 3.9.1 Decay Time ........... 3.9-1 3.9.2 Communications ........... ' 3.9-2 3.9.3 Refueling Platform ........... 3.9-3 3.10 MISCELLANEOUS ........................................ 3.10-1 3.10.1 Sealed Source Contamination ......................................... 3.10-1 3.10.2 MODE 5 Shutdown Margin Test RPS Instrumentation ............................... 3.10-4 3.10.3 Independent Spent Fuel Storage Installation (ISFSI) ......................... TRM/3.10-7 3.10.4 Leading Edge Flow Meter (LEFM) ....................... TRM/3.10-8 3.11 RADIOACTIVE EFFLUENTS .; .........................  ; . ; .;. 3.11-1 3.11.1.1 Liquid Effluents Concentration ........................ 3.11-1 3.11.1.2 Liquid Effluents Dose .....................  ; 3.11-4 3.11.1.3 Liquid Waste Treatment System ...................... ..  ; 3.11-6 3.11.1.4 Liquid Radwaste Effluent Monitoring Instrumentation.:.................................... 3.11-8 3.11.1.5 Radioactive Liquid Process Monitoring Instrumentation .............................. 3.11-13 3.11.2.1 Dose Rate .............  : 3.11-17 3.11.2.2 Dose - Noble Gases. 3.11-20 3.11.2.3 Dose - Iodine, Tritium, and Radionuclides in Particulate Form .......... 3.11-21 3.11.2.4 Gaseous Radwaste Treatment System ............................. TRM/3.11-22 3.11.2.5 Ventilation Exhaust Treatment System ............................TRM/3.11-23 3.11.2.6 Radioactive Gaseous Effluent Monitoring Instrumentation ............................ 3.11-26 3.11.3 Total Dose ............................ 3.11-33 3.11.4.1 Monitoring Program ............................ 3.11-35 3.11.4.2 Land Use Census ............................ 3.11-45 3.11.4.3 Interlaboratory Comparison Program ............................ 3.11-47 iii EFFECTIVE DATE 10/22/2003 SUSQUEHANNA - UNIT SUSQUEHANNA -

UNIT 11 Hi EFFECTIVE DATE 10/22/2003

SUSQUEHANNA STEAM ELECTRIC STATION TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)

SECTION TITLE PAGE 3.12 LOADS CONTROL PROGRAM ............................. TRM/3.12-1 3.12.1 Crane Travel - Spent Fuel Storage Pool ............................ ; TRM/3.12-1 3.12.2 Heavy Loads Requirements ........................... TRM/3.12-3 3.12.3 Light Loads Requirements ...........................  ; TRM/3.12-5 4.0 ADMINISTRATIVE CONTROLS ...................... 4.0-1 4.1 Organization ...................... 4.0-1 4.2 Reportable Event Action ...................... 4.0-2 4.3 . Safety Limit Violation ...................... 4.0-3 4.4 Procedures and Programs ...................... . 4.0-4 4.5 Reporting Requirements ...................... 4.0-5 4.6 Radiation Protection Program ....................... 4.0-7 4.7 Training ...................... 4.0-8 iv EFFECTIVE DATE 10/22/2003 SUSQUEHANNA--UNIT SUSQUEHANNA UNIT 1 1 iv EFFECTIVE DATE 10/22/2003

SUSQUEHANNA STEAM ELECTRIC STATION TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)

SECTION TITLE PAGE B3.0 Applicability ..................................  ; B 3.0-1 B3.0 (TRO) - TR for Operation (TRO) Applicability . ................................. B 3.0-1

  • B 3.0 (TRS) - TR Surveillance (TRS) Applicability . B 3.0-9 B 3.1.1 Alternate Rod Injection .............. TRM/B 3.1-1 B 3.1.2 CRD Housing Support .................................. , . ........ TRM/B 3.1-4 B 3.1.3 Control Rod Block Instrumentation ........ TRMlB 3.1-5 B 3.1.4 Control Rod Scram Accumulators Instrumentation and Check Valve ........ TRM/B 3.1-8 B 3.2.1 Core Operating Limits Report (COLR) .................................. ......... B 3.2-1 B 3.3.1 Radiation Monitoring Instrumentation ........ TRM/B 3.3-1 B 3.3.2 Seismic Monitoring Instrumentation .................................  ;.........B 3.3-2 B 3.3.3 Meteorological Monitoring Instrumentation ........................................ TRM/B 3.3-3 B 3.3.4 TRM Post-Accident Monitoring Instrumentation ........ TRMIB 3.3-4 B 3.3.5 Section Not Used ......... TRM/B 3.3-7 B 3.3.6 TRM Containment Isolation Instrumentation ........ B 3.3-10 B 3.3.7 Turbine Overspeed Protection System ........................... TRM/B 3.3-14 B 3.3.8 Section Not Used . TRM/B 3.3-15 B 3.3.9 LPRM Upscale Alarm Instrumentation ........................... ;......... TRM/B 3.3-17 B 3.3.10 Reactor Recirculation Pump. MG Set Electrical and Mechanical Stops .......... TRM/B 3.3-18 B 3.3.11 MVP Isolation Instrumentation ......................... ;.:.;.:.TRM/B 3.3-20 B 3.4.1 Reactor Coolant System Chemistry ........................ , B 3.4-1 B 3.4.2 Structural Integrity .....................................  : B 3.4-2 B 3.4.3 High/Low Pressure Interface Leakage Monitors .B 3.4-4 B 3.4.4 Reactor Recirculation Flow and Rod Line Limit ................................. TRM/B 3.4-5 B 3.4.5 Reactor Vessel Material Surveillances Program ....... B 3.4-6 B 3.5.1 ADS Manual Inhibit ....... B 3.5-1 B 3.5.2 ECCS and RCIC System Monitoring Instrumentation ....... B 3.5-3 B 3.5.3 Long Term Nitrogen Supply to ADS ........ B 3.5-4 V EFFECTIVE DATE 10/22/2003

- UNIT 1 SUSQUEHANNA - UNIT SUSQUEHANNA v EFFECTIVE DATE 10/2212003

SUSQUEHANNA STEAM ELECTRIC STATION TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)

SECTION TITLE PAGE B 3.6.1 VENTING or PURGING ................................. TRM/B 3.6-1 B 3.6.2 Suppression Chamber-to-Drywell Vacuum Breaker Position Indication .B 3.6-3 B 3.6.3 Suppression Pool Alarm Instrumentation ....... ....... TRM/B 3.6-4 B 3.6.4 Primary Containment Closed System Boundaries .TRM/B 3.6-6 B 3.7.1 Emergency Service Water System (Shutdown) .B 3.7-1 B 3.7.2 Ultimate Heat Sink and Ground Water Level .. B 3.7-2 B 3.7.3.1 Fire Suppression Water Supply System .TRM/B 3.7-3 B 3.7.3.2 Spray and Sprinkler Systems .TRM/B 3.7-5 B 3.7.3.3 C02 systems..................................................................................... TRM/B 3.7-7 B 3.7.3.4 Halon Systems ................................  ; TRM/B 3.7-8 B 3.7.3.5 Fire Hose Stations.TRM/B 3.7-10 B 3.7.3.6 Yard Fire Hydrants and Hydrant Hose Houses .TRM/B 3.7-11 B 3.7.3.7 Fire Rated Assemblies ...................... TRM/B 3.7-12 B 3.7.3.8 Fire Detection Instrumentation . ..................... TRM/B 3.7-14 B 3.7.4 Solid Radwaste System . TRM/B 3.7-15 B 3.7.5.1 Main Condenser Offgas Hydrogen Monitor .. B 3.7-17 B 3.7.5.2 Main Condenser Explosive Gas Mixture .B 3.7-19.

B 3.7.5.3 Liquid Holdup Tanks.; .................... B 3.7-20 B 3.7.6 ESSW Pumphouse Ventilation .TRM/B 3.7-21 B 3.7.7 Main Condenser Offgas Pretreatment Logarithmic Radiation.

Monitoring Instrumentation .................  ; TRM/B 3.7-22 B 3.7.8 Snubbers ....... ...... B 3.7-24 B 3.7.9 Control Structure HVAC ................... . :.:._.;.TRM/B 3.7-31 B 3.7.10 Spent Fuel Storage Pools . . .. TRM/B 3.7-33 B 3.8.1 Primary Containment Penetration Conductor Overcurtleli Protective Devices. TRM/B 3.8-1 B 3.8.2.1 Motor Operated Valves Therial Overload Protection - -

Continuous ...... TRM/B 3.8-3.

B 3.8.2.2 Motor Operated Valves Thermal Overload Protection -

Automatic .. TRM/B 3.8-4 B 3.8.3 Diesel Generator (DG) Maintenance Activities.; ........ . B 3.8-5 B 3.8.4 24VDC Electrical Power Subsystem ........ B 3.8-6 B 3.8.5 Degraded Voltage Protection .......... TRM/B 3.8-16 B 3.8.6 Emergency Switchgear Room Cooling .......... TRM/B 3.8-17 B.3.9.1 Decay Time ........... B 3.9-1 B 3.9.2 Communications . ............ ;.;.B 3.9-2 vi EFFECTIVE DATE 10/22/2003 UNIT 1 SUSQUEHANNA - UNIT SUSQUEHANNA vi EFFECTIVE DATE 10/22/2003 -

SUSQUEHANNA STEAM ELECTRIC STATION TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)

SECTION TITLE PAGE B 3.9.3 Refueling Platform ........... B 3.9-3 1B3.10.1 Sealed Source Contamination ........ B 3.10-1 B 3.10.2 MODE 5 Shutdown Margin Test RPS Instrumentation ......... B 3.10-2 B 3.10.3 Independent Spent Fuel Storage Installation (ISFSI) ........ TRM/B 3.10-4 B 3.10.4 Leading Edge Flow Meter (LEFM) ........ TRM/B 3.10-6 B 3.11.1.1 Liquid Effluents Concentration ......... B 3.11-1 B 3.11.1.2 Liquid Effluents Dose ......................  ; B 3.11-4 B 3.11.1.3 Liquid Waste Treatment System ............................ B 3.11-6 B 3.11.1.4 Liquid Radwaste Effluent Monitoring Instrumentation .................................. B 3.11-7 B 3.11.1.5 Radioactive Liquid Process Monitoring Instrumentation . TRM/B 3.11-10 B 3.11.2.1 Dose Rate . TRM/B 3.11-12 B 3.11.2.2 Dose - Noble Gases .B 3.11-16 B 3.11.2.3 Dose - Iodine, Tritium, and Radionuclides in Particulate Form ............................  ;- B 3.11-18 B 3.11.2.4 .Gaseous Radwaste Treatment System . TRM/B 3.11-20 B 3.11.2.5 Ventilation Exhaust Treatment System .TRM/B 3.11-21 B 3.11.2.6 Radioactive Gaseous Effluent Monitoring Instrumentation . ............ B 3.11-24 B 311.3 Total Dose .B 3.11-26 B 3.11.4.1 Monitoring Program ............ B 3.11-28 B 3.11.4.2 Land Use Census .............................  ; B 3.11-34 B 3.11.4.3 Interlaboratory Comparison Program ............................TRM/B 3.11-36 B.3.12.1 Crane Travel - Spent Fuel Storage Pool .. .TRM/B 3.12-1 B.3.12.2 Heavy Loads Requirements . . ........................TRM/B 3.12-2 B.3.12.3 Light Loads Requirements ...................  :;TRM/B 3.12-3 NFM TRMI text TOC vii EFFECTIVE DATE 10/22/2003 SUSQUEHANNA-UNIT SUSQUEHANNA - UNIT 11 - v11 EFFECTIVE DATE 10/22/2003

SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title - - Effective Date TOC TABLE OF CONTENTS 10/22/2003 1.0 IUSE AND APPLICATION Pages TRM / 1.0-1 through TRM / 1.0-3 10/04/2002 2.0 PLANT PROGRAMS Pages 2.0-1 through 2.0-2 08/31/1998 Page TRM 12.0-3 08/01/2001 Page TRM /2.0-4 06/25/2002 Page TRM /2.0-5 ,N> 04/02/1999 Pages TRM /2.0-6 and TRM /2.0-7 10/22/2003 Page TRM / 2.0-8 *' 03/2912000 Page TRM / 2.0-9 ),,g09/04/2002 Pages TRM 2.0-10 and TRM /2.0-11 04102/1999 Page TRM / 2.0-12 10/22/2003 Page TRM I 2.0-13 06/1612000 3.0 APPLICABILITY Pages TRM / 3.0-1 and TRM /3 04/08/1999 Pages TRM / 3.0-3. 03115/2002 Page TRM / 3.0-4 . 04/08/1999 3.1 REACTIVITY CONTROL SYSTEMS Pages 3.1-1 through 3.1-6 ' 08/31/1998 Pages TRM I .. 1-7 ,and TRM /3.1-8 06105/2002 Pages TRM I 3.1-9 adridTRM 13.1-9a 02/18/1999 Page TRM/3.1-10 ,'

  • 02/18/1999 3.2 CORE.OPERATiNG LIMITS REPORT Page TRM 3.2-1' ' .'07/07/1999 Pages TRM /,3.2-2 through TRM I 3.2-35 07/28/2003 3.3 INSTRUMENTATION Pages TRM 3.3-1 through TRM / 3.3-3 07/16/1999 Page TRM 3.3-4 11/28/2000 Pages 3.3-5 through 3.3-8 08/31/1998 Pages TRM / 3.3-9 and TRM / 3.3-9a 12/17/1998 Pages TRM / 3.3-10 and TRM / 3.3-11 12/17/1998 Page TRM / 3.3-12 03/30/2001 Pages TRM / 3.3-13 and TRM / 3.3-14 12114/1998 Page TRM 3.3-15 10122/2003 Page TRM / 3.3-16 06/27/2001 Pages TRM 3.3-17 and TRM / 3.3-18 06/14/2002 Pages TRM 3.3-19 through TRM / 3.3-21 10/22/2003 Page 3.3-22 08/31/1998 Pages TRM / 3.3-23 through TRM / 3.3-25 -05/16/2003 Page TRM 3.3-26 10/22/2003 SUSQUEHANNA - UNIT 1 TRM /LOES-1 EFFECTIVE DATE 10122/2003

SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date 3.4 REACTOR COOLANT SYSTEM Pages 3.4-1 through 3.4-5 10/23/1998 Pages 3.4-6 through 3.4-13 08/31/1998 3.5 EMERGENCY CORE COOLING AND RCIC Pages 3.5-1 through 3.5-3 08/31/1998

- Page TRM / 3.5-4 04/17/2000 Pages 3.5-5 through 3.5-7 08/31/1998 3.6 "CONTAINMENT

- Pages 3.6-1 through 3.6-3 08/31/1998 Page TRM / 3.6-4 01/07/2002

- Page 3.6-5 08/31/1998 Pages TRM / 3.6-6 through TRM / 3.6-8 12/3112002 3.7 - PLANT SYSTEMS Pages 3.7-1 through 3.7-3 08/31/1998 Pages TRM / 3.7-4 through TRM / 3.7-10 08/02/1999 Page TRM / 3.7-11 12/29/1999 Pages TRM / 3.7-12 through TRM / 3.7-27 08/02/1999 Pages TRM / 3.7-28 through TRM / 3.7-34 11/16/2001 Page TRM / 3.7-34a 10/05/2002 Pages TRM / 3.7-35 through TRM / 3.7-37 02/01/1999 Pages 3.7-38 through 3.7-40 08/31/1998 Pages TRM / 3.7-41 and TRM /3.7-41a 08/11/2000 Pages 3.7-42 and 3.7-43 08/31/1998 Pages 3.7-44 through 3.7-48 10/13/1998 Page TRM / 3.7-49 03/08/2003 Pages TRM / 3.7-50 and TRM / 3.7-51 03/09/2001 Pages TRM / 3.7-52 and TRM / 3.7-53 04/15/2003 Page TRM / 3.7-54 07/29/1999 3.8 ELECTRICAL POWER Pages TRM / 3.8-1 and TRM / 3.8-2 04/02/2002 Page 3.8-3 08/31/1998 Page TRM / 3.8-4 12/31/2002 Pages TRM / 3.8-5 and TRM I 3.8-6 04/02/2002 Pages TRM / 3.8-7 through TRM / 3.8-9 08/31/1998 Page TRM / 3.8-10 07/19/2001 Page TRM / 3.8-11 04/02/2002 Page TRM / 3.8-11a 04/02/2002 Pages 3.8-12 through 3.8-14 08/31/1998 Pages TRM / 3.8-15 through TRM / 3.8-17 04/02/2002 Page 3.8-18 08/31/1998 Page TRM / 3.8-19 04/02/2002 SUSQUEHANNA - UNIT TRM / LOES-2 EFFECTIVE DATE 10/22/2003

SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVESECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title Effective Date Page 3.8-20 08/31/1998 Pages TRM / 3.8-21 through TRM / 3.8-23 06/06/1999 Pages 3.8-24 and 3.8-25 08/31/1998 3.9 REFUELING OPERATIONS Pages 3.9-1 through 3.9-3 08/31/1998 3.10 MISCELLANEOUS Pages 3.10-1 through 3.10-4 08/31/1998 Page TRM / 3.10-5 03/08/2003 Page TRM / 3.10-6 06/05/2002 Page TRM / 3.10-7 04/07/2000 Corrected Page TRM / 3.10-8 04/17/2002 3.11 RADIOACTIVE EFFLUENTS Pages 3.11-1 through 3.11-12 08/31/1998 Pages 3.11-13 through 3.11-16

  • 09/01/1998 Pages 3.11-17 through 3.11-21 08/31/1998 Pages TRM /3.11-22 through TRM / 3.11-24 04/02/2002 Pages 3.11-25 through 3.11-32 09/01/1998 Pages 3.11-33 through 3.11-47 08/31/1998 3.12
  • LOADS CONTROL PROGRAM Pages TRM / 3.12-1 through TRM ! 3.12 02/05/1999 4.0 ADMINISTRATIVE CONTROLS-Pages 4.0-1 through 4.0-8 08/31/1998 SUSQUEHANNA - UNIT TRM / LOES-3 EFFECTIVE DATE 10/22/2003

SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVESECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title - Effective Date B 3.0 APPLICABILITY BASES Pages B 3.0-1 through B 3.0-10 08/31/1998 Pages TRM / B 3.0-11 through TRM / B 3.0-15 03/15/2002 B 3.1 REACTIVITY CONTROL SYSTEMS BASES Pages TRM / B 3.1-1 through TRM / B 3.1-3 07/13/1999 Page B 3.1-4 08/31/1998 Pages TRM / B 3.1-5 through TRM / B 3.1-7 07/13/1999 Page TRM / B 3.1-8 02/18/1999 B 3.2 CORE OPERATING LIMITS BASES Page B 3.2-1 08/31/1998 B 3.3 INSTRUMENTATION BASES Page TRM / B 3.3-1 04/07/2000 Page B 3.3-2 08/3111998 Pages TRM / B 3.3-3 and TRM / B3.3-3A 12/29/2000 Pages TRM / B 3.3-4 through TRM / B 3.3-6 03/21/2003 Pages TRM / B 3.3-7 through TRM / B 3.3-9 03/30/2001 Pages B 3.3-10 through B 3.3-12 08/31/1998 Page TRM / B 3.3-13 10/22/2003 Page TRM / B 3.3-14 06/25/2002 Page TRM / B 3.3-14a 06/14/2002 Page TRM / B 3.3-14b 06/14/2002 Pages TRM / B 3.3-15 and TRM-i B 3.3-16 10/22/2003 Page TRM / B 3.3-17 04/07/2000 Pages TRM / B3.3-1 8and TRM / B 3.3-19 05/16/2003 Page TRM / B 3.3-20 10/22/2003 Page TRM / B 3.3-21 * . 05/16/2003 B 3.4 REACTOR COOLANT SYSTEM BASES Pages B 3.4-1 through B 3.4-4 08/31/1998 Page TRM / B 3.4:5 10/15/1999 Page B 3.4-6 08/31/1998 B 3.5 ECCS AND RCIC BASES Pages B 3.5-1 through B 3.5-5 08/31/1998 B 3.6. CONTAINMENT BASES Page TRM / B 3.6-1 07/26/2001 Page TRM / B 3.6-2 02/01/1999 Page B 3.6-3 08/31/1998 Page TRM / B 3.6-4 09/23/1999 Page TRM / B 3.6-5 01/07/2002 Pages TRM / B 3.6-6 through TRM / B 3.6-11 12/31/2002 SUSQUEHANNA - UNIT 1 TRM / LOES-4 EFFECTIVE DATE 10/22/2003

SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title - Effective Date B 3.7 PLANT SYSTEMS BASES Pages B 3.7-1 and B 3.7-2 08/31/1998 Pages TRM / B 3.7-3 through TRM / B 3.7-7 08/02/1999 Page TRM / B 3.7-7a 08/02/1999 Pages TRM / B 3.7-8 through TRM / B 3.7-10 08/02/1999 Page TRM / B 3.7-1 Oa 08/02/1999 Pages TRM / B 3.7-11 and TRM / B 3.7-11a 08/02/1999 Pages TRM I B 3.7-12 through TRM / B 3.7-14 08/02/1999 Pages TRM / B 3.7-14a and TRM / B 3.7-14b 08/02/1999 Pages TRM / B 3.7-15 and TRM / B 3.7-16 02/01/1999 Pages B 3.7-17 through B 3.7-20 08/31/1998 Page TRM/B 3.7-21 through TRM/B 3.7-21a 05/1 1/2001 Pages TRMIB 3.7-22 and TRMIB 3.7-23 04/07/2000 Pages B 3.7-24 through .B 3.7-30 08/31/1998 Pages TRM / B 3.7-31 and TRM / B 3.7-32 03/09/2001 Page TRM / B 3.7-33 04115/2003 Pages TRM / B 3.7-34 and TRM / B 3.7-35 07/05/2000 B 3.8 ELECTRICAL POWER BASES Pages TRM / B 3.8-1 and TRM / B 3.8-2 04/02/2002 Page TRM / B 3.8-2a 04/02/2002 Page TRM / B 3.8-3 04/02/2002 Page TRM / B 3.8-3a 04/02/2002 Page TRM / B 3.8-4 04/02/2002 Page TRM / B 3.8-4a 04/02/2002 Page TRM / B 3.8-5 08/31/1998 Pages TRM / B 3.8-6 through TRM / B 3.8-17 04/02/2002 B.3.9 REFUELING OPERATIONS-BASES Pages B 3.9-1 through B 3.9-7 *-08/31/1998 B-3.10 MISCELLANEOUS BASES Pages B 3.10-1 through B 3.10-2 08/31/1998 Page TRM / B 3.10-3 03/08/2003 Pages TRM / B 3.10-4 and TRM / B 3.10-5 08/23/1999 Pages TRM / B 3.10-6 and TRM / B 3.10-7 04/17/2002 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 08/30/1998 Page TRM / B 3.1 1-10 02/01/1999 Pages TRM/B 3.11-11 and TRM/B 3.11-11a 04/07/2000 Pages TRM/B 3.11-12 and TRM/B 3.11-13 02/01/1999 Page TRM / B 3.11-14 11/01/1999 Page TRM I B 3.11-15 02/01/1999 Pages B 3.11-16 through B 3.11-19 08130/1998 Page TRM / B 3.11-20 04/02/2002 Page TRM / B 3.11-20a 04/02/2002 Page TRM / B 3.11-21 04/02/2002 SUSQUEHANNA - UNIT .TRM I LOES-5 EFFECTIVE DATE 10/22/2003

SUSQUEHANNA STEAM ELECTRIC STATION LIST OF EFFECTIVE SECTIONS (TECHNICAL REQUIREMENTS MANUAL)

Section Title - Effective Date Page TRM / B 3.11-22 09/26/2003 PageTRM/B3.11-23 04/02/2002 Page TRM / B 3.11-23a 04/02/2002 Page TRM / B 3.11-24 03/21/2003 Page TRM / B 3.11-25 04/15/2003 Pages B 3.11-26 through B 3.11-35 08/30/1998 PageTRM/B3.11-36 02/12/1999 B.3.12 LOADS CONTROL PROGRAM BASES Pages TRM I B 3.12-1 through TRM I B 3.12-3 02/05/1999 NFMNTRM1 texd LOES.doc SUSQUEHANNA - UNIT 1 TRM / LOEST6 EFFECTIVE DATE 10/2212003

Instrument Trip Setpoint Program PPL Rev. .., 2.2 2.0 PLANT PROGRAMS AND SETPOINTS 2.2 Instrument Trip Setpoint Table The Instrument Trip Setpoint Limits inTable 2.2-1 are the Trip Setpoint value limits that were contained in the Instrumentation Setpoint tables for protection systems and other functions important to safety that were included in the scope of the original Standard Technical Specifications. Actual instrument setpoints are established utilizing the Allowable Values specified in the Technical Specifications and Technical

'Requirements. Allowable Values are established in the Reference LCOs and TROs identified in this Table. TRO references are enclosed in square brackets.

Instrumentation process setpoints for the listed subsystems and trip functions are set consistent with the Trip Setpoint Limit Column of Table 2.2-1. Actual setpoints are established in accordance with engineering procedures.

Alami setpoints and other non-protection system trip settings asmay be found in the Technical Specifications or in the Technical Requirements are not included in this table.

Reference NDAP-QA-1 104 Setpoint Change Control SUSQUEHANNA - UNIT 1 TRM /12.0-5 UIEFFECTIVE DATE 04/02/1999

Instrument Trp Setpoint Program PPL Rev. 1.. 2.2 TABLE 2.2-1 (Page 1 of 7)

INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO [TRO] TRIP FUNCTION TRIP SETPOINT 2.2.1 Reactor Protection 2.2.1.1 3.3.1.1 Intermediate Range Monitor, Neutron Flux- 120/125 divisions of full High scale 2.2.1.2 .-- 3.3.1.1 Average Power Range Monitor, Neutron Flux S 15% of RATED THERMAL POWER

- High Setdown 2.2.1.3 3.3.1.1 Average Power Range Monitor, Flow Biased See COLR - TRO 3.2 Simulated Thermal Power - High Two Loop Operation 2.2.1 A 3.3.1.1 Average Power Range Monitor, Flow Biased See COLR - TRO 3.2 Simulated Thermal Power - High Single Loop Operation 2.2.1.5 3.3.1.1 Average Power Range Monitor, Flow Biased < 113.5% of RATED THERMAL Simulated Thermal Power- High Flow POWER Clamped 2.2.1.6 3.3.1.1 Average Power Range Monitor, Fixed Neutron S 118% of RATED THERMAL POWER Flux- High 2.2.1.7 3.3.1.1 Reactor Vessel Steam Dome Pressure - High S 1087 psig 2.2.1.8 3.3.1.1 Reactor Vessel Water Level - Low, Level 3 2 13.0 inches ° 2.2.1.9 3.3.1.1 Main Steam Isolation Valve - Closure . 10% closed 2.2.1.10 This Section Not Used 2.2.1.11 3.3.1.1 Drywell Pressure - High . 1.72 psig 2.2.1.12 3.3.1.1 . Scram Dischargeyolume Water Level - High * . 65 gallons

- Level Transmitter 2.2.1.13 3.3.1.1 Scram Discharge Volume Water Level - High

  • 61 gallons

- Float Switch 2.2.1.14 3.3.1.1 Turbine Stop Valve - Closure * . £ 5.5% closed 2.2.1.15 3:3.1.1 Turbine Control Valve Fast Closure; Trip . - -- . -* 500 psig Oil Pressure - Low 2.2.2 Isolation Actuation Instrumentation 2.2.2.1 Primary Containment Isolation 2.2.2.1.1 3.3.6.1 Reactor Vessel Water Level Low, Level 3 2 13.0 inches '

2.2.2.1.2 3.3.6.1 Reactor Vessel Water Level Low Low, Level a -38.0 inches(a) 2 2.2.2.1.3 3.3.6.1 Reactor Vessel Water Level Low Low low, 2 -129 inches (a)

Level 1 2.2.2.1.4 3.3.6.1 Drywell Pressure - High £ 1.72 psig 2.2.2.1.5 3.3.6.1/13.3.6] SGTS Exhaust Radiation - High £ 23.0 mRthr 2.2.2.1.6 (3.3.6] Main Steam Line Radiation - High High £ 15 x full power background without hydrogen injection (continued)

  • (a) See Figure 2.2-1 SUSQUEHANNA - UNIT 1 TRM / 2.0-6 EFFECTIVE DATE 1012212003

Instrument Trip Setpoint Program PPL Rev. 1-  ;: 2.2 TABLE 2.2-1 (Page 2 of 7)

INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO

[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.2.2 Secondary Containment Isolation 2.2.2.2.1 3.3.6.2 Reactor Vessel Water Level - Low Low, 2 -38.0 inches '

Level 2 2.2.2.2.2 3.3.6.2 Drywell Pressure - High

  • 1.72 psig 2.2.2.2.3 3.3.6.2 Refuel Floor High Exhaust Duct Radiation- 518 mRihr High 2.2.2.2.4 3.3.6.2 Railroad Access Shaft Exhaust Duct 5 5 mR/hr Radiation - High 22.2.2.5 3.3.6.2 Refuel Floor Wall Exhaust Duct Radiation - . 21 mRihr High 2.2.2.3 Main Steam Line Isolation 2.2.2.3.1 3.3.6.1 Reactor Vessel Water Level - Low Low Low, 2 -129 inchest(

Level 1 2.2.2.3.2 3.3.6.1 Main Steam Line Pressure - Low 2 861 psig 2.2.2.3.3 3.3.6.1 Main Steam Line Flow- High - * *113 psid 2.2.2.3.4 3.3.6.1 . Condenser Vacuum - Low 2 9.0 inches Hg vacuum 2.2.2.3.5 3.3.6.1 Reactor Building Main Steam Line Tunnel

  • 1770 F Temperature - High 2.2.2.3.6 This Section Not Used 22.2.3.7 [3.3.6] Reactor Building Main Steam Line Tunnel .. 990 F

^ Temperature - High 2.2.2.3.8 [3.3.6.1] Turbine Building Main Steam Tunnel *1 97 0F Temperature - High 2.2.2.4 Reactor Water Cleanup System Isolation 2.2.2.4.1 3.3.6.1 Reactor Vessel Water Level - Low Low, 2 -38 inches (a)

Level 2 2.2.2.4.2 3.3.6.1 RWCU A Flow - High

  • 59 gpm 2.2.2.4.3 3.3.6.1 RWCU Flow- High

-High 0

2.22.4.6 3.3.6.1 RWCU Pump Area Temperature - High :147 F 0

2.22.4.7 [3.3.6] RWCU Pump Room Area ATemperature - S 69 F High 2.2.2A.8 3.3.6.1 RWCU Heat Exchanger Area Temperature - - S 1470F High 2.2.2.4.9 [3.3.6] RWCU Heat Exchanger Room Area

  • 690 F A Temperature - High (continued)

(') See Figure 2.2-1 SUSQUEHANNA - UNIT TRM / 2.0-7 EFFECTIVE DATE 10/22/2003

Instrument Trip Setpoint Program PPL Rev. 1.-  ;: 2.2 TABLE 2.2-1 (Page 3 of 7)

INSTRUMENTATION SETPOINTS SYSTEMIREFERENCE LCO

[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.2.5 Reactor Core Isolation Cooling System Isolation 22.2.5.1 3.3.6.1 RCIC Steam Line A Pressure - High S 188 inches H20 2.2.2.52 3.3.6.1 RCIC Steam Supply Line Pressure - Low 2 60 psig 22.2.5.3 3.3.6.1 RCIC Turbine Exhaust Diaphragm Pressure < 10.0 psig

- High 22.2.5.4 3.3.6.1 RCIC Equipment Room Temperature - High

  • 1670 F 22.2.5.5 3.3.6.1 RCIC Pipe Routing Area Temperature - High S 1670 F 22.2.5.6 3.3.6.1 RCIC Emergency Area Cooler Temperature - , 1670 F

. High 2.2.2.5.7 3.3.6.1 Drywell Pressure - High < 1.72 psig 2.2.2.5.8 13.3.6] RCIC Equipment Room A Temperature -High 890 F 2.22.5.9 13.3.6] RCIC Pipe Routing AreaATemperature- S890 F High 2.2.2.6 High Pressure Coolant Injection System Isolation 2.2.2.6.1 3.3.6.1 HPCI Steam LineA Pressure - High S 370 inches H20 2.2.2.6.2 3.3.6.1 HPCI Steam Supply Line Pressure - Low 2 104 psig 2.2.2.6.3 3.3.6.1 HPCI Turbine Exhaust Diaphragm Pressure -

  • 10 psig High 2.2.2.6.4 3.3.6.1 HPCI Equipment Room Temperature - High S 1670F 22.2.6.5 3.3.6.1
  • HPCI EmergencyArea Cooler Temperature - .- S 1670F High 22.2.6.6 3.3.6.1 . HPCI Pipe Routing Area Temperature - High ' 1670F 2.2.2.6.7 3.3.6.1 Drywell Pressure - High - 1.7Z psig 2.2.2.6.8 [3.3.6] HPCI Equipment Room A Temperature - High
  • S 89SF 2.2.2.6.9 13.3.6] HPCI Pipe Routing Area A Temperature - -- -
  • 89F High 2.2.2.7 Shutdown Cooling/System Isolation 2.2.2.7.1 3.3.6.1 Reactor Vessel Water Level - Low, Level 3 2 13.0 inches (a 2.22.72 3.3.6.1 Reactor Vessel Steam Dome Pressure - High - S 98 psig 2.22.7.3 [3.3.6] RHR Flow - High < 25,000 gpm 2.2.3 ECCS Actuation 2.2.3.1 Core Spray System 22.3.1.1 . 3.3.5.1 Reactor Vessel Water Level - Low Low Low, 2 -129 inches ()

Level 1 22.3.12 3.3.5.1 Drywell Pressure - High . S 1.72 psig 22.3.1.3 3.3.5.1 Reactor Vessel Steam Dome Pressure - Low 2 413, S 427 psig injection permissive (continued)

(a)See Figure 2.2-1

.SUSQUEHANNA - UNIT TRM / 2.0-8 EFFECTIVE DATE 09/04/2002

Instrument Tip Setpoint Program PPL Rev. 1.- i:;

  • 2.2 TABLE 2.2-1 (Page 4 of 7)

INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO TRO] TRIP FUNCTION TRIP SETPOINT 2.2.3.2 LPCI Mode of RHR System 2.2.3.2.1 3.3.5.1 Reactor Vessel Water Level - Low Low Low, 2 -129 inches (a)

Level 2.2.3.2.2

  • 3.3.5.1 Drywell Pressure - High S 1.72 psig 2.2.3.2.3 3.3.5.1 Reactor Vessel Steam Dome Pressure - Low, 2 413, S 427 psig injection permissive 2.2.3.2.4 3.3.5.1 Reactor Vessel Steam Dome Pressure - Low. 2 236 psig, decreasing Recirculation Discharge Valve permissive 2.2.3.3 HPCI System 2.2.3.3.1 3.3.5.1 Reactor Vessel Water Level - Low Low, ._ 2 -38 inches (a)

Level 2 2.2.3.3.2 3.3.5.1 Drywell Pressure - High S 1.72 psig 2.2.3.3.3 3.3.5.1 Condensate Storage Tank Level - Low

22.3.5.1.1 3.3.8.1 Bus Undervoltage 2823.2, S 856.8 Volts 22.3.5.1.2 3.3.8.1 Time delay 2 0.4, S 0.6 seconds (continued)

(a)See Figure 2.2-1 SUSQUEHANNA - UNIT TRM / 2.0-9 EFFECTIVE DATE 09/04/2002

Instrument Trip Setpoint Program PPL Rev. I- 2.2 TABLE 2.2-1 (Page 5 of 7)

INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO TRO] TRIP FUNCTION TRIP SETPOINT 2.2.3.5.2 4.16kV ESS Bus Undervoltage (Degraded Voltage < 65%)

2.2.3.5.2.1 3.3.8.1 Bus Undervoltage 2641.1; S 2748.9 Volts 2.2.3.5.2.2 3.3.8.1 - Time delay 2 2.7, S 3.3 seconds 2.2.3.5.3 4.16kV ESS Bus Undervoltage (Degraded Voltage, < 93%)

2.2.3.5.3.1 3.3.8.1 Bus Undervoltage 23829.3, 3906.7 Volts 2.2.3.5.3.2 3.3.8.1 Time Delay (Non-LOCA) 2 4 minute, 30 seconds 5 5 minute, 30 seconds 2.2.3.5.3.4 3.3.8.1 Time Delay (LOCA) 29, S 11 seconds 2.2.3.5.4 480V ESS Bus OB565 Undervoltage (Degraded Voltage, < 65%)

2.2.3.5.4.1 [3.8.5] 480V Basis - 308.9. S 315.1 Volts 2.2.3.5.4.2 13.8.5] Time Delay 24.5.5 5.5 seconds 2.2.3.5.5 480V ESS Bus OB565 Undervoltage (Degraded Voltage, < 92%)

2.2.3.5.5.1 [3.8.5]

  • 480V Basis . 2437.6, 5 446.4 Volts 2.2.3.5.5.2 [3.8.5] Time Delay . 9. 5 11 seconds 2.2.4 ATWS Altemate Rod injection and Recirculati6n Pump Trip 2.2.4.1 3.3.4.2/[3.1.1] . Reactor Vessel, Water Level - Low Low, 2 -38 inches(a

-Level 2 2.2.4.1 3.3.4.24[3.1.1] Reactor Vessel Steam Dome Pressure - High 5 1135 psig 2.2.5 End of Cycle Recirculation Pump Trip 2.2.5.1 3.3.4.1 Turbine Stop Valve-Closure 55.5% closed 2.2.5.2 3.3.4.1 Turbine Control Valve - Fast Closure 2 500 psig 2.2.6 Reactor Core Isolation Cooling System Actuation 22.6.1 3.3.5.2 Reactor Vessel Water Level - Low Low. 2 -38 inches (a)

Level 2 22.62 3.3.5.2 Reactor Vessel Water Level - High, Level S 54 inches (a) 8 2.2.6.3 3.3.5.2 Condensate Storage Tank Level - Low Ž36.0 inches above tank bottom (continued)

(') See Figure 2.2-1 SUSQUEHANNA - UNIT TRM / 2.0-1 0 EFFECTIVE DATE 04/02/1999

Instrument Trip Setpoint Program PPL Rev. .- I: 2.2 TABLE 2.2-1 (Page 6 of 7)

INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO

[TRO] TRIP FUNCTION TRIP SETPOINT 2.2.7 Control Rod Block 2.2.7.1 Rod Block Monitor 2.2.7.1.1 3.3.2 , Low Power Range Upscale -Two Loop

  • 0.58W + 52%

Operation 2.2.7.1.2 3.3.2 Low Power Range Upscale - Single Loop

  • 0.58W +47%

Operation 2.2.7.1.3 Downscale 5%

2.2.7.2 APRM 2.2.7.2.1 [3.1.3] Flow Biased Simulated Thermal Power-High See COLR - TRO 32

- Two Loop Operation .

2.2.7.2.2 13.1.3] Flow Biased Simulated Thermal Power High See COLR - TRO 3.2

- Single Loop Operation 2.2.7.2.3 13.1.31 Flow Biased Simulated Thermal Power High

  • 108% of RATED THERMAL POWER

- High Flow Clamped 2.2.7.2.4 13.1.31 Downscale 2 5% of RATED THERMAL POWER 2.2.7.2.5 [3.1.31 Neutron Flux - High Setdown

  • 12% of RATED THERMAL POWER 2.2.7.3 Source Range Monitors 2.2.7.3.1 [3.1.3] Upscale *. *2E5 cps 2.2.7.3.2 [3.1.3] ,Downscale . 0.7 cpse 2.2.7.4 Intermediate Range Monitors 2.2.7.4.1 [3.1.3] - Upscale 1081125 divisions of full scale 2.2.7A.2 [3.1.3] Downscale Ž 5125 divisions of full scale 2.2.7.5 Scram Discharge Volume 2.2.7.5.1 [3.1.3] Water Level - High

2.2.7.6.2 [3.1.3] Comparator

  • 10% flow deviation (continued)
0) Provided signal-to-nolse ratio is 2 2. Otherwise, 2 3 cps.

SUSQUEHANNA - UNIT 1 TRM / 2.0-1 1 EFFECTIVE DATE 04102/1999

Instrument Trip Setpoint Program PPL Rev. 1. -  :. 2.2 TABLE 2.2-1 (Page 7 of 7)

INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO TRO] TRIP FUNCTION TRIP SETPOINT 2.2.8 CREOASS 2.2.8.1 3.3.7.1 Main Control Room Outside Air Intake S 5 mR/hr Radiation Monitor 2.2.8.1.1 3.3.7.1 Reactor Vessel Water Level - Low Low, 2 -38.0 Inches (a)

Level 2 2.2.8.1.2 3.3.7.1 Drywell Pressure - High

  • 1.72 psig 2.2.8.1.3 3.3.7.1 Refuel Floor High Exhaust Duct Radiation - 18 mR/hr

-High 2.2.8.1.A 3.3.7.1 Railroad Access Shaft Exhaust Duct 5 5 mR/hr Radiation -.High 2.2.8.1.5 3.3.7.1 Refuel Floor Wall Exhaust Duct Radiation

  • 21 mR/hr

-High 2.2.9 Feedwater/Main Turbine Trip System Actuation 2.2.9.1 3.3.2.2 Reactor Vessel Level - High

  • 54.0 inches (a) 2.2.10 MVP.lsolation 2.2.10.1 [3.3.11] Main Steam Line Radiation -'High High
  • 15 x full power background without hydrogen injection

{a) See Figure 2.2-1 SUSQUEHANNA - UNIT TRM / 2.0 EFFECTIVE DATE 10/22/2003

Instrumenf Trip Setpoint Table PPL Rev. .-. 2.2

.900 ATER' LEVEL e cO.LS HEIGHT'ABOVE .

D. 'VESSEL ZERD READING io- I (IN.)

7) 566.5 +39

~~750-I ' 74_ VESS C4) 557.5 +30

' FLtE c:t 5) :S40.5 413

2) 489.5 -38
3) 39.5- -129.

-65.5--m MAIN 650- .- STEAM

. ' ' . , U"IDI

.oo- .F W .,..

581;5'S o) +60 -+60--60 +60

-56.5 *cn _ S() 4 7 )' 3 ? I IX.FRM SWO- -557.5 (4) nCn&C 4 ) 3 La Am

-540.S (3) . RIC 1f)Li BOTTOM CF. STEAi - -U

-I. ZERO DY5 ERSKIRT

  • RACTJ 484 .

=.. (2) COR , -38 - S 1ATER CON4TRI8UTE (2) INITIATE RCIC4 TO ADS 450- HPC1. ARI TRIP RECIRC PUMS 400- 39&5 (1) -12Y

'CO INITIATE RHR. Cs

368. 3-_ START DIESEL
  • CONTRIBUTE TO ADS 350- -0i- CLOWSE 3SIV-S 300-f- _ :3 250--J-200- .

ISl. 0 RECIRIC

. . . INLET CUTLET 150NOZL NOZZLE NOTE: SCALE.IN INCHES 1<~~o <1 ABV.ESLZR

. FIGURE 2.2-1 REACTOR VESSEL WATER LEVEL cum ID' .. 2.1 . . .

SUSQUEHANNA -UNIT1I TRM 2.0-13 EFFECTIVE DATE 06/16/2000

TRM Isolation Actuation Instrumentation PPL Rev. 1  ;:. 3.3.6 3.3 Instrumentation 3.3.6 TRM Isolation Actuation Instrumentation TRO 3.3.6 The TRM containment isolation instrumentation for each Function in Table 3.3.6-1 shall be OPERABLE.

APPLICABILITY: As specified in Table 3.3.6-1 ACTIONS NOTES Separate Condition entry is allowed for each channel.

CONDITION - REQUIRED ACTION COMPLETION TIME.

A One or more required Al Place channel in trip. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for channels inoperable Function l.a and 2.a

'ANil--

24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Functions other than Functions l.a and 2.a B. One or more Functions B.1 Restore isolation capability. 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with isolation capability not maintained.

SUSQUEHANNA - UNIT 1 TRM 3.3-1 3 EFFECTIVE DATE 12114/1998

TRM Isolation Actuation Instrumentation PPL Rev. 1 3.3.6 TECHNICAL REQUIREMENT SURVEILLANCE NOT I--S

1. Refer to Table 3.3.6-1 to determine which TRSs apply for each TRM Isolation Actuation Instrumentation Function.
2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated function maintains isolation capability.

SURVEILLANCE . FREQUENCY TRS 3.3.6.1 Perform CHANNEL CHECK 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> TRS 3.3.6.2 Perform CHANNEL FUNCTIONAL TEST 92 days TRS 3.3.6.3 Perform CHANNEL CALIBRATION 92 days TRS 3.3.6.4 Perform CHANNEL CALIBRATION 24 months TRS 3.3.6.5 Perform LOGIC SYSTEM FUNCTIONAL TEST 24 months TRS 3.3.6.6 Perform RESPONSE TIME TEST 24 months on a staggered test basis SUSQUEHANNA.- UNIT TRM / 3.3-14 EFFECTIVE DATE 12/14/1998

TRM Isolation Actuation Instrumentation PPL Rev. 1 -: 3.3.6 TABLE 3.3.6-1 (Page 1 of 2)

PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION APPLICABLE MODES OR OTHER REQUIRED SPECIFIED CHANNELS PER SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS TRIP SYSTEM REQUIREMENTS VALUE

1. Main Steam Line Isolation
a. Reactor Building 1,2,3 2 TRS 3.3.6.2
b. Turbine Building 1,2,3 2 TRS 3.3.62
2. Primary Containment Isolation
a. Main Steam Line 1,2,3 2 TRS 3.3.6.1
  • 21 x full power Radiation - High, High TRS 3.3.62.. -background TRS 3.3.6.4 without hydrogen TRS 3.3.6.5 injection TRS 3.3.6.6()
3. High Pressure Coolant Injection (HPCI) System Isolation
a. HPCI Pipe Routing 1,2.3 1 TRS 3.3.62
  • 980F Area A Temperature - TRS 3.3.6.3 High TRS 3.3.6.5
b. HPCI Equipment Room 1.2.3 1 TRS 3..6.2
  • 980 F A Temperature - High TRS 3.3.6.3 TRS 3.3.6.5 (continued)

SUSQUEHANNA - UNIT 1 TRM 13.315 EFFECTIVE DATE 10/22/2003

TRM Isolation Actuation Instrurnentation PPL Rev. 1 3.3.6 CaRadiation detectors are exempt from response time testing.

SUSQUEHANNA- UNIT11 TRM 3.3-15 EFFECTIVE DATE 10/22/2003

  • TRM Isolation Actuation Instrumentation PPL Rev. I.- 3.3.6 TABLE 3.3.6-1 (Page 2 of 2)

PRIMARY CONTAINMENT ISOLATION INSTRUMENTATION APPLICABLE MODES OR OTHER REQUIRED SPECIFIED CHANNELS PER SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS - TRIP SYSTEM REQUIREMENTS VALUE

4. Reactor Core Isolation Cooling (RCIC) System Isolation
a. RCIC Pipe Routing 1.Z3 I TRS 3.3.6.2 S 98F Area A Temperature - TRS 3.3.6.3 High TRS 3.3.6.5
b. RCIC Equipment Room 1,2,3 1 TRS 3.3.6.2 S 98F ATemperature- High TRS 3.3.6.3 TRS 3.3.6.5
5. Reactor Water Cleanup (RWCU) System Isolation
a. RWCU Penetration 1,2.3 I TRS 3.3.6.2 . s 720 F Area ATemperature - TRS 3.3.6,3 High TRS 3.3.6.5
b. RWCU Pump Area A 1,2,3 1 TRS 3.3.6.2 s 720 F Temperature - High TRS 3.3.6.3 TRS 3.3.6.5
c. RWCU Heat Exchanger 1,2,3 1 TRS 3.3.6.2 S 72*F Area A Temperature - TRS 3.3.6.3 High TRS 3.3.6.5
6. Shutdown Cooling System Isolation (a)
a. . RHRFlow-High 3,4,5 1 TRS 3.3.6.1 S 26,000 gpm TRS 3.3.6.2 TRS 3.3.6.4 TRS 3.3.6.5, (a) Not required when the penetration is isolated from the reactor vessel via manual isolation valve, blind flange, or deactivated auto isolation valve.

SUSQUEHANNA - UNIT 1 TRM / 3.3-16 EFFECTIVE DATE 6/27/2001

PPL Rev. 1 3.3.8 3.3 Instrumentation 3.3.8 Section not used THIS PAGE INTENTIONALLY LEFT BLANK .

SUSQUEHANNA - UNIT 1 TRM / 3.3-19 EFFECTIVE DATE 10/22/2003

PPL Rev. I 3.3.8 THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA- UNI 1 TRM / 3.3-20 EFFECTIVE DATE 10/22/2003

PPL Rev. I 3.3.8 THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT TRW/3.3-21 EIEFFECTIVE DATE 10/22/2003

/

Mechanical Vacuum Pump (MVP) Isolation Instrumentation PPL Rev. I  ;:. . 3.3.11 3.3 Instrumentation 3.3.11 MVP Isolation Instrumentation TRO 3.3.11 The MVP Isolation Instrumentation for each Function in Table 3.3.11-1 shall be OPERABLE.

APPLICABILITY: MODE 1 or 2 with one or more Main Steam Isolation Valves open and mechanical vacuum pump in service.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A One or more required A.1 Place channel in trip. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> channel inoperable.

B. MVP isolation capability not B.1 Restore MVP Isolation 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> maintained. capability..

C. Required Action and C.1 Shut-down the MVP and . Immediately associated Completion close the MVP suction valve.

.{

Time of Condition A or B not met.

TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.3.11.1 Perform CHANNEL FUNCTIONAL TEST. 92 days TRS 3.3.11.2 Perform CHANNEL CALIBRATION. 24 months TRS 3.3.11.3 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months SUSQUEHANNA - UNIT 1 TRM / 3.3-25 EFFECTIVE DATE 05/16/2003

. Mechanical Vacuum Pump (MVP) Isolation Istrumentation PPL Rey 1 3.3.11 TABLE 3.3.1 1-1 MVP ISOLATION INSTRUMENTATION

- REQUIRED CHANNELS PER SURVEILLANCE FUNCTION TRIP SYSTEM REQUIREMENTS ALLOWABLE VALUE

1. Main Steam Line 2 TRS 3.3.11.1 521 xfull power background Radiation - High TRS 3.3.11.2 without hydrogen injection High TRS 3.3.11.3 SUSQUEHANNA - UNIT TRM / 3.3-26 QTEFFECTIVE DATE 10122/2003

TRM Isolation Actuation Instrumentation PPL Rev. 1 B 3.3.6 B 3.3.6 TRM Isolation Actuation Instrumentation BASES TRO The TRM Actuation instrumentation automatically initiates closure of appropriate primary containment isolation valves (PCIVs). The function of the PCIVs, in combination with other accident mitigation systems, is to limit fission product release during and following postulated Design Basis Accidents (DBAs) (Reference 1). The TRM Isolation Actuation Instrument has been relocated from the Technical Specifications because the identified Function is not credited in the plant design basis to mitigate any plant event, but does provide a diverse means to initiate an Isolation Actuation.

The isolation instrumentation includes the sensors, relays, and instruments that are necessary to cause initiation of primary containment and reactor coolant pressure boundary (RCPB) isolation. When the setpoint is reached, the sensor actuates, which then outputs an isolation signal to the isolation logic. Monitoring a wide range of independent parameters provides functional diversity. The input parameters to the isolation logic are:

(a) Main steam line radiation, (b) Reactor Building Main Steam Differential Temperature - High, (c) Turbine Building Main Steam Line Tunnel Temperature - High, (d) HPCI Pipe Routing Area Differential Temperature - High, (e) HPCI Equipment Room Differential Temperature - High, (f) RCIC Pipe Routing Area Differential Temperature - High, (g) RCIC Equipment'Room Differential Temperature'- High, (h) RWCU Penetration Area Differential Temperature - High, (i) RWCU Pump Area Differential Temperature - High,

0) RWCU Heat Exchanger Area Differential Temperature - High, and (k) RHR Flow- High.

The valves associated with these trip channels are identified in Table B 3.3.6-1.- Each of these valves is also associated with other trip channels as identified in LCO Bases B 3.6.1.3.

Functions (d) and (f) trips will occur only after a 15 minute time delay; the other trips occur after a one second delay. See Tech Spec Basis B 3.3.6-1.

(continued)

SUSQUEHANNA - UNIT 1 TRM I B 3.3-10 EFFECTIVE DATE 08/31/1998

TRM Isolation Actuation Instrumentation PPL Rev. 1 B 3.3.6 B 3.3.6 TRM Isolation Actuation Instrumentation BASES (continued)

ACTIONS The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components. The Actions are modified by Note 2, which identifies that if the degradation of any TRM Isolation Actuation Instrumentation impacts the OPERABILITY of any Technical Specification Isolation Instruments identified in LCO 3.3.6.1, Primary Containment Isolation Instrumentation", the appropriate Technical Specification Actions must be taken. This Note is necessary because the TRM Isolation Actuation Instrumentation can impact the capability of the Technical Specification Isolation Instrumentation. If this occurs, both the TRM and Technical Specification Required Actions must be taken to ensure proper compensatory actions are taken.

TRS The TRSs are defined to be performed at the specified Frequency to ensure that the TRM Isolation Actuation nstrumentation'Functions are maintained OPERABLE. TRM Isolation Actuation Instrumentation Surveillances are

. performed consistent with the Bases for LCO 3.3.6.1'"Isolation Activation Instrumentation."

TRS 3.3.6.5 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel. The system functional testing performed on PCIVs in LCO 3.6.1.3 overlaps this surveillance to provide complete testing of the assumed safety function. The 24 month Frequency is based on the need to perform portions of this surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the surveillance were performed with the reactor at power. Operating experience has shown these components usually pass the surveillance when performed at the 24 month Frequency.

TRS 3.3.6.6 Response time testing for the Function 1.a and Function 2.a

  • 10 second requirement per FSAR Table 7.3-29 is met by testing the channel for the 1 second channel response time requirement per FSAR Table 7.3-29 for Function 1.a.

(continued)

SUSQUEHANNA - UNIT 1 TRM / B 3.3-11 EFFECTIVE DATE 08131/1998

TRM Isolation Actuation Instrumentation

  • PPL Rev. 1 B 3.3.6 B 3.3.6 TRM Isolation Actuation Instrumentation BASES (continued)

REFERENCES 1. FSAR Section 7.3.1

2. NRC Inspection and Enforcement Manual, Part 9900: Technical

- Guidance, Standard Technical Specification Section 1.0 Definitions, Issue dated 12/8/96.

I .

SUSQUEHANNA - UNIT 1 TRM / B 3.3-12 EFFECTIVE DATE 08/31/1998

TRM Isolation Actuation Instrumentation PPL Rev. 1 - B 3.3.6 Table B 3.3.6-1 Primary Containment Isolation Valves Isolation Signal Plant systems Valve Number Valve Description Valve Description(Table Function No.

3.3.6-)

Nuclear HV-141F022A MSIV 1.a, 1.b Boiler HV-141F022B MSIV 1.a, 1.b HV-141F022C MSIV 1.a, 1.b HV-141F022D MSIV 1.a, 1.b HV-1 41 F028A MSIV 1.ap 1.b HV-141 F028B MSIV 1.a, 1.b HV-141F028C MSIV 1.a, 1.b HV-141F028D MSIV 1.a, 1.b HV-1 41 F01 6 MSL Drain Isolation Valve 1.a, 1.b HV-141F019 MSL Drain Isolation Valve 1.a, 1.b Reactor HV-143F019 Reactor Coolant'Sample Valve 2.a Recirculation HV-143FO20 Reactor Coolant Sample Valve . 2.a HPCI HV-155F002 HPCI Steam Supply Valve 3.a, 3.b HV-155F003 HPCI Steam Supply Valve 3.a, 3.b HV-155F100 HPCI Steam Supply Valve 3.a, 3.b HV-155F042 HPCI Suction Valve 3.a, 3.b RCIC HV-149F007 RCIC Steam Supply Valve 4.a, 4.b HV-149F008 RCIC Steam Supply Valve 4.a, 4.b HV-149F088 RCIC Steam Supply Valve 4.a,4.b RWCU HV-144F001 RWCU Suction Valve 5.a, 5.b, 5.c HV-144F004 RWCU Suction Valve 5.a, 5.b, 5.c RHR HV-151 F022 . RHR - Reactor Vessel Head Spray Valve. 6.a HV-151 F023 RHR - Reactor Vessel Head Spray Valve 6.a SUSQUEHANNA - UNIT . TRM / B 3.3-13. EFFECTIVE DATE 10/2212003

-. r-

. 'S.~

PPL Rev. 1 B 3.3.8 I-BASES B 3.3.8 Section not used THIS PAGE INTENTIONALLY LEFT BLANK

. . . .~~~~~~~~~~~~~~~~~~~~~~~~~~

SUSQUEHANNA - UNIT 1 TRM / B 3.3-15 EFFECTIVE DATE 10/22/2003

I U t

PPL Rev. 1 B 3.3.8

&f BASES (continued)

B.3.3.8 Section not used' THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT I TRM I B 3.3-16 EFFECTIVE E DATE 10/22/2003

MVP Isolation nstrumentation PPL Rev. I  :-, ' B 3.3.11 B 3.3.11 MVP Isolation Instrumentation BASES TRO The MVP Isolation instrumentation automatically shuts down the MVP and closes its suction valve. The purpose is to limit fission product release following a postulated Design Basis Control Rod Drop Accident with the MSIV's open and the MVP System in operation. The MVP draws gases from the main condenser and discharges to the Turbine Building vent stacks, providing an unfiltered release path for fission product activity to the environment. Automatic Isolation of the MVP System in response to a Main Steam Line-High High radiation signal is part of the design basis of the units as described in the FSAR.

The Isolation Instrumentation includes the sensors, relays, and devices that are necessary to initiate the above actions. The input parameter to the isolation logic is main steam line (MSL) radiation. When the MSL Radiation - High High setpoint is reached on eithe.MSL Radiation Monitor

'A" or B", the sensor actuates, which then generates a shutdown signal to the MVP System control logic. There is only one trip system for the MVP Isolation.

The components associated with this trip channel are identified in Table B 3.3.11-1.

ACTIONS This TRO is only applicable when the MVP System is in'service drawing or maintaining condenser vacuum with the reactor in Mode 1 or.2 and one or more MSIV's open. The time of exposure is relatively short, usually during startup from initial criticality up to a maximum of 5% reactor power. The Actions are defined to ensure that the capability to automatically isolate the MVP System is restored promptly if lost during MVP operation.

TRS The TRSs are defined to be performed at the specified Frequency to ensure that the MVP Isolation Function is OPERABLE prior to entering the applicable condition. The CHANNEL FUNCTIONAL TEST, CHANNEL CALIBRATION and LOGIC SYSTEM FUNCTIONAL TEST are performed at the same interval as the equivalent surveillance of the MSLRM channels for the Primary Containment Isolation functions.

REFERENCES 1. FSAR Section 7.3.1.1a.2.4.1.2.

2; FSAR Section 10.4.2.2.

3. FSAR Section 11.5.2.1.

SUSQU]EHANNA -UNIT TRM / B 3.3-20 EFFECTIVE DATE 10122/2003

MVP Isolation instrumentation PPL Rey.1 -  ;: B 3.3.11 Table B 3.3.11-1 MVP Isolation Components

. ~~~~~~Isolation Signal Plant Systems Component Component Description Function No.

Number PlantSystems .(Table 3.3.11-1)

Vacuum Hogging HV-10731 MVP Suction Isolation Valve 1.

1P05 Mechanical Vacuum Pump 1.

SUSQUEHANNA -UNIT 1 TRM / B 3.3-21 EFFECTIVE DATE 05/16/2003

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