ML033100098

From kanterella
Jump to navigation Jump to search
TRM2 - Technical Requirements Manual, Susquehanna, Unit 2
ML033100098
Person / Time
Site: Susquehanna Talen Energy icon.png
Issue date: 10/27/2003
From:
Susquehanna
To:
Document Control Desk, Office of Nuclear Security and Incident Response
References
28401
Download: ML033100098 (44)
v • d • e


Text

-7\ J.I Oct. 27, 2003 Page 1 of 2 MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2003-50300 USER TNF-RMA/ONt GE SE M EMPL#:28401 CA#: 0363 Address UCSA2 Phone# 254- 94 TRANSMITTAL INFORMATION:

TO: . - 10/27/2003 LOCATION: USNRC p'ROM: NUCLEAR RECORDS DOCUMENT CONTROL CENTER NUCSA-2)

K_4'HE FOLLOWING CHANGES HAVE OCCURRED TO THE HARDCOPY OR ELECTRONIC MANUAL ASSIGNED TO YOU:

TRM2 - TECHNICAL REQUIREMENTS MANUAL UNIT 2 REMOVE MANUAL TABLE OF CONTENTS DATE: 10/02/2003 ADD MANUAL TABLE OF CONTENTS DATE: 10/24/2003 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 2.2 REMOVE: REV:0 ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 3.3.11 REMOVE: REV:0 ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 3.3.6 REMOVE: REV:0 ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT 3.3.8 REMOVE: REV:0 DD: REV: 1 HES CATEGORY: DOCUMENTS TYPE: TRM2

Oct. 27, 2003 Page 2 of 2 ID: TEXT B3.3.11 REMOVE: REV:0 ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT B3.3.6 REMOVE: REV:0 ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT B3.3.8 REMOVE: REV:0 ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT LOES REMOVE: REV:O ADD: REV: 1 CATEGORY: DOCUMENTS TYPE: TRM2 ID: TEXT TOC REMOVE: REV:0

\-DD: 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 CONTENTS (TECHNICAL REQUIREMENTS MANUAL)

SECTION TITLE PAGE 1.0 USE AND APPLICATION .......................... 1.0-1 1.1 Definitions .TRM/1.0-2 2.0 PLANT PROGRAMS .......................... 2.0-1 2.1 Plant Programs .2.0-1 2.2 Instrument Trip Setpoint Table .......................... : TRM2.0-5 3.0 APPLICABILITY .TRM/3.0-1 3.0 (TRO) -TR for Operation (TRO) Applicability ...... TRM/3.0-1 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 ....................... 3.1-4 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 3.2 CORE OPERATING LIMITS REPORT......................................................... 3.2-1 3.2.1 Core Operating Limits Report .3.2-1 3.3 INSTRUMENTATION ........ ;TRM/3.3-1 3.3.1 , Radiation Monitoring Instrumentation . ...........................

w..TRM13.3-1 3.3.2 Seismic Monitoring Instrumentation . ...............................TRMJ3.3-4 3.3.3 Meteorological Monitoring Instrumentation . .................................3.3-7 3.3.4 TRM Post-Accident Monitoring Instrumentation . . ..... TRM/3.3-9.

3.3.5 Section Not Used .. TRM/3.3-12

.3.3.6 TRM Containment Isolation Instrumentation;.:.. . .... T-RM3.3-13 3.3.7 Turbine OverspeedProtection System .. TRM/3.3-17 3.3.83.3.8 ~~Section Seto Not Used .....................................................;R/.S1 osd......TRMI3.3-19 3.3.9 LPRM Upscale Alarm Instrumentation . ............................. 3.3-21 3.3.10 Reactor Recirculation Pump MG Set Electrical and Mechanical Stops .. TRM/3.3-22 3.3.11 MVP Isolation Instrumentation . .TRM/3.3-24 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 3A.4 Reactor Recirculation Flow and Rod Line Limit .3.4-12 3.4.5 Reactor Vessel Material Surveillances Program. 3.4-13 3.5 EMERGENCY CORE COOLING AND RCIC . .3.5-1 3.5.1 ADS Manual Inhibit....................................................................................3.-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 SUSQUEHANNA-UNIT 2 i EFFECTIVE DATE 10/2212003

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

SECTION TITLE PAGE 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 .............................. 3.6-3 3.6.3 Suppression Pool Alarm Instrumentation ............................ 3.6-4 3.6.4 Primary Containment Closed System Boundaries .......................... TRM/3.6-7 3.7 PLANT SYSTEMS ..................................... TRM/3.7-1 3.7.1 Emergency Service Water System (Shutdown) .............................. TRM3.7-1 3.7.2 Ultimate Heat Sink and Ground Water Level .............................. 3.7-3 3.7.3.1 Fire Suppression Water Supply System . TRM13.7-4 3.7.3.2 Spray and Sprinkler Systems . TRM13.7-8 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 ...........  ;- TRM3.7-18 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........... TRM/3.7-40 3.7.6 ESSW Pumphouse Ventilation ., ...... ..... 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 (SFSPs) ............................. .  ::TRM/3.7-51 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 -

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

Automatic ...... .............................TRM3.8-1 3.8.3 Diesel Generator (DG) Maintanence 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 Plafform ................... 3.9-3 ii EFFECTIVE DATE 10/22/2003 SUSQUEHANNA-SUSQUEHANNA-UNIT2 urr 2

  • ii EFFECTIVE DATE 10/22/2003

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

SECTION TITLE PAGE 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 Installition (ISFSI) . TRM3.10-7 3.10.4 Leading Edge Flow Meter (LEFM)...................................................TRM/3.10-8 3.11 RADIOACTIVE EFFLUENTS .3.11-1 3.11.1 Liquid Effluents ............................ 3.11-1 3.11.1.1 Liquid Effluents Concentration. 3.11-1 3.11.1.2 Liquid Effluents Dose .3.114 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 Gaseous Effluents.....: ...... 3.11-17 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 3.11.2A Gaseous Radwaste Treatment System . TRM13.11-22

  • 31.2.5 Ventilation Exhaust Treatment System .TRM13.11-23 3.11.2.6 Radioactive Gaseous Effluent Monitoring Instrumentation..................3........................................t..............................3.11-26 3.11.3 Total Dose ......................... 3.11-33 3.11.4 Radiological Environmental Monitoring .........................  : ; 3.11-35 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 3.12' LOADS CONTROL PROGRAM..........................................................TRM/3.12-1 3.12.1 Crane Travel'- Spent Fuel Storage Pool .TRM13.12-1 3.12.2 Heavy Loads Requirements ......................  ;... TRM/3.12.3 3.12.3 Light Loads Requirements .TRM3.12-5 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 4

iii EFFECTIVE DATE 10122/2003 SUSQUEHANNA - UNIT 2 SUSQUEHANNA-UNI'172 fi EFFECTIVE DATE 10122/2003

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

SECTION TITLE PAGE B 3.0 (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 Altemate Rod Injection . TRMIB 3.1-1 B 3.1.2 CRD Housing Support .B 3.1-4 B 3.1.3 Control Rod Block Instrumentation .TRM/B 3.1-5 B 3.1.4 Control Rod Scram Accumulators Instrumentation and Check Valve ........ TRMIB 3.1-8 B 3.2.1 Core Operating Limits Report (COLR) ... B 3.2-1 B 3.3.1 Radiation Monitoring Instrumentation . ....... TRMlB 3.3-1 B 3.3.2 Seismic Monitoring Instrumentation . ....... B 3.3-2 B 3.3.3 Meteorological Monitoring Instrumentation . ....... TRMIB 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 .. TRMIB 3.3-14 B 3.3.8 Section Not Used .. TRMIB 3.3-15 B 3.3.9 LPRM Upscale Alarm Instrumentation . .B 3.3-18 B 3.3.10 Reactor Recirculation Pump MG Set Electrical and Mechanical Stops .......................... TRM/B 3.3-20 B 3.3.11 MVP Isolation Instrumentation . ..........................

. TRMlB 3.3-22 B 3.4.1 Reactor Coolant System Cheimisty,....................,.............................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 34-4 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 .............................. .1 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 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 . .................................... 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 ............................... : TRMIB 3.7-3 B 3.7.3.2 Spray and Sprinkler Systems .............................. TRM/B 3.7-5 B 3.7.3.3 C02 systems ............................. TRMlB 3.7-7 B 3.7.3.4 Halon Systems ............................. TRMlB 3.7-8 B 3.7.3.5 Fire Hose Stations ............................. TRMlB 3.7-10 SUSQUEHANNA-UNIT2 iv EFFECTIVE DATE 10/22/2003

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

SECTION TITLE PAGE B 3.7.3.6 Yard Fire Hydrants and Hydrant Hose Houses ............................... TRMlB 3.7-11 B 3.7.3.7 Fire Rated Assemblies .TRMB 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 ................ TRMlB 3.7-33 B 3.8.1 Primary Containment Penetration Conductor Overcurrent Protective Devices .. - TRMlB 3.8-1 B 3.8.2.1 Motor Operated Valves Thermal Overload Protection -

Continuous . . .TRM/B 3.8-3 B 3.8.2.2 Motor Operated Valves Thermal Overload Protection -

Automatic ... ..TRMB 3.8-4 B 3.8.3 Diesel Generator (DG) Maintanence Activities ... ..... TRMIB 3.8-5 B 3.8.4 24VDC Electrical Power Subsystem . . . ..... TRMIB 3.8-6 B 3.8.5 Degraded Voltage Protection . . ...... TRMlB 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 B 3.9.3 Refueling Platform ........ .............. B 3.9-3 B 3.10.1 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) .................... ;.TRMIB 3.10-4 B 3.10.4 Leading Edge Flow Meter (LEFM) ................... TRMIB 3.10-6 B 3.11.1.1 Liquid Effluents Concentration ................... B 3.11-1 B3.11.1.2 Liquid Effluents Dose ................... B 3.11-4 B3.11.1.3 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 B3.11.2.1 Dose Rate ....................  : TRMIB 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 .......................... TRMIB 3.11-20 B3.11.2.5 Ventilation Exhaust Treatment System .......................... TRM/B 3.11-21 V EFFECTIVE DATE 1012212003 SUSQUEHANNA-SUSQUEHANNA-UNITUNIT 22 v EFFECTIVE DATE 10/22/2003

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

SECTION TITLE PAGE B 3.11.2.6 Radioactive Gaseous Effluent Monitoring Instrumentation ........................ B 3.11-24 B 3.11.3 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 LOADS CONTROL PROGRAM ............................ TRB 3.12-1 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 TM2 Tet TOC vi EFFECTIVE DATE 10122/2003 SUSQUEHANNA SUSQUEHANNA-UNIT - UNIT 2 2 vi EFFECTIVE DATE 10122/2003

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

Section Title Effective Date TOC TABLE OF CONTENTS 10/22/2003 1.0 USE AND APPLICATION Page TRM / 1.0-1 08/31/1998 Page TRM I 1.0-2 10/04/2002 Page TRM / 1.0-3 08/31/1998 2.0 PLANT PROGRAMS Page 2.0-1 08/31/1998 Pages TRM / 2.0-2 through TRM / 2.0-4 ,, 06/25/2002 Page TRM / 2.0-5 04/12/1999 Page TRM / 2.0-6 10/22/2003 Page TRM / 2.0-7 10/22/2003 Page TRM / 2.0-8 08/30/2001 Page TRM / 2.0-9 09/06/2002 Pages TRM / 2.0-10 and TRM 2.0-11 04/12/1999 Page TRM / 2.0-12 10/22/2003 Page TRM / 2.0-13 06/16/2000 3.0 APPLICABILITY Pages TRM / 3.0-1 and TRM 04/08/1999 Page TRM /3.0-3 03/15/2002 Page TRM / 3.0-4 ) 04/08/1999 3.1 REACTIVITY CONTROL SYSTEMS Pages 3.1-1 thrbugh"3.1-6\" ' 08/31/1998 Pages TRMI3>S1-7'and TRM / 3.1-8 06/05/2002 Pages TRM3.A-9 ard TRM / 3.1-9a 02/18/1999 Page TRM/&1-10,> 02/18/1999 3.2 CORE OPERATING LIMITS REPORT IPage 32-1 08/31/1998 Pages TRM / 3.2-2 through TRM / 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 12117/1998 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 12/14/1998 Page TRM / 3.3-15 10/22/2003 Page TRM /3.3-16 06/27/2001 Pages TRM / 3.3-17 and TRM / 3.3-18 06/14/2002 TRM / LOES-1 EFFECTIVE DATE 10122/2003 SUSQUEHANNA - UNIT SUSQUEHANNA -

UNIT 2 2 TRM / LOES-1 EFFECTIVE DATE 10/22/2003

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

Section Title Effective Date Pages TRM / 3.3-19 and TRM 3.3-20 10/22/2003 Page 3.3-21 08/31/1998 Pages TRM / 3.3-22 through TRM / 3.3-24 05/16/2003 Page TRM / 3.3-25 10/22/2003 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 3.6-4 08/31/1998 Page TRM / 3.6-5 01/07/2002 Page 3.6-6 08/31/1998 Pages TRM / 3.6-7 through TRM / 3.6-9 12131/2002 3.7 PLANT SYSTEMS Pages TRM / 3.7-1 and TRM / 3.7-2 07/29/1999 Page 3.7-3 08/31/1998 Pages TRM / 3.7-4 through TRM / 3.7-10

  • 08/02/1999 Page TRM / 3.7-11 01/21/2000 Pages TRM / 3.7-12 through TRM /3.7-27 08/02/1999 Pages TRM / 3.7-28 through TRM / 3.7-32 11/16/2001 Page TRM / 3.7-33 10/05/2002 Pages TRM / 3.7-34 through TRM / 3.7-36 02/01/1999 Pages 3.7-37.through 3.7-39 08/31/1998 Pages TRM / 3.7-40 and TRM / 3.7-40a 08/11/2000 Pages 3.7-41 and 3.7-42 08/31/1998 Pages 3.7-43 through 3.7-47 10/13/1998 Page TRM / 3.7-48 03/08/2003 Pages TRM / 3.7-49 and TRM / 3.7-50 03/09/2001 Pages TRM / 3.7-51 and TRM / 3.7-52 04/15/2003 Page TRM / 3.7-53 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 / 3.8-6 04/02/2002 Pages TRM / 3.8-7 through TRM 3.8-8 08/31/1998 Page TRM / 3.8-9 08/24/2001 Page 3.8-10 08/31/1998 TRM / LOES-2 EFFECTIVE DATE 10/22/2003 UNIT 2 SUSQUEHANNA - UNrr 2 TRM I LOES-2 EFFECTIVE DATE 10/22/2003

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

Section Title Effective Date Page TRM 13.8-11 0410212002 Page TRM / 3.8-11 a 04/02/2002 Pages 3.8-12 through 3.8-14 08/31/1998 Pages-TRM / 3.8-15 through TRM 1 3.8-17 04/02/2002 Page 3.8-18 02/01/1999 Page TRM / 3.8-19 04/02/2002 Page TRM /3.8-20 02/01/1999 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 08/30/1998 Page TRM 13.10-5 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 through 3.11-21 . . 08131/1998 Pages TRM / 3.11-22 through TRM / 3.11-24  : 04/02/2002 Pages 3.11-25 through 3.11-32 a9/01/1 998 Pages 3.11-33 through 3.11-47 08/31/1998 3.12 LOADS CONTROL PROGRAM Pages TRM / 3.12-1 through TRM / 3.12-5 ... 02/05/1 999 4.0 ADMINISTRATIVE CONTROLS Pages 4.0-1 through 4.0-8 08/31/1998 TRM / LOES-3 EFFECTIVE DATE 10/22/2003 SUSQUEHANNA-UNIT2 SUSQUEHANNA - UNIT 2 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 I B 3.1-3 07/13/1999 Page B 3.1-4 08/31/1998 Pages TRM / B 3.1-5 through TRM I 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 08/31/1998 Pages TRM / B 3.3-3 and TRM / B 3.3-3A 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 I B 3.3-9 03/30/2001 Pages B 3.3-10 through B 3.3-12 08/31/1998 Page TRM / B3.3-13 10/2212003 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 Page TRM / B 3.3-15 10/22/2003 Page TRM / B 3.3-16 10/2212003 Page TRM / B 3.3-17 10/22/2003 Pages TRM / B 3.3-20 and TRM I B 3.3-21 05/16/2003 Page TRM I B3.3-22 10/22/2003 Page TRM / B3.3-23 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 B3.5

  • ECCS AND RCIC BASES Pages B 3.5-1 through B 3.5-5 08/31/1998 B3.6 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 ML E - F E TV A E 1 / 22 0 SU Q E -A N NT2T SUSQUEHANNA - UNIT 2 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 08131/1998 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 I B 3.7-8 through TRM / B 3.7-10 08/02/1999 Page TRM / B 3.7-1Oa 08/02/1999 Pages TRM / B 3.7-11 through TRM / B 3.7-14 08/02/1999 Page TRM / B 3.7-14a 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 Pages TRM / B 3.7-21 through TRM/B 3.7-21a 05/11/2001.

Pages TRM/B 3.7-22 and TRM/B 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 I B 3.7-33 04/15/2003 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 I B 3.8-2 04/02/2002 Page TRM / B 3.8-2a 04/02/2002 Page TRM I 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 I B 3.8-4a 04/02/2002 Page TRM I 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 and B 3.9-2 08/31/1998 Pages B 3.9-3 through B 3.9-7 10/23/1998 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 /3.10-7 04/1712002 B 3.11 RADIOACTIVE EFFLUENTS BASES Pages B 3.11-1 through B 3.11-9 08/31/1998 Pages TRM I B 3.11-10 02/01/1999 Pages TRMIB 3.11-11 and TRMIB 3.11-1 Ia 04/07/2000 Pages TRM/B 3.11-12 and TRMIB 3.11-13 02/01/1999 Page TRM / B 3.11-14 11/01/1999 Page TRM / B 3.11-15 02/01/1999 TRM / LOES-5 EFFECTIVE DATE 10/22/2003 UNIT 2 SUSQUEHANNA-- UNIT SUSQUEHANNA 2 TRM / LOES-5 EFFECTIVE DATE 10/22/2003

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

Section Title Effective Date Pages B 3.11-16 through B 3.11-19 08/31/1998 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 Page TRM / B 3.11-22 09/26/2003 Page TRM / B 3.11.23 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 B3.11-35 08/31/1998 Page TRM / B 3.11-36 02112/1999 B.3.12 LOADS CONTROL PROGRAM BASES Pages TRM I B 3.12-1 through TRM / B 3.12-3 02/05/1999 NFKMTRM2 texd LOES.doc TRM/LOES-6 EFFECTIVE DATE I 0/22/2003 SUSQUEHANNA - UNIT -

UNIT 22 TRM / LOES-6 EFFECTIVE DATE 10/22/2003

Instrument Trip Sefpoint Program PPL Rev. 1 .2.2 2.0 PLANT PROGRAMS AND SETPOINTS 2.2 Instrument Trip Setpoint Table The Instrument Trip Setpoint Limits in Table 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.

Alarm setpoints and other non-protection system trip settings as may be found in the Technical Specifications or in the Technical Requirements are.Dot included in this table.

Reference NDAP-QA-1 104 Setpoint Change Control SUSQUEHANNA - UNIT 2 TRM / 2.0-5 EFFECTIVE DATE 04/1211999

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

INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO TRJP FUNCTION TRIP SETPOINT

[TRO] '*

22.1 Reactor Protection 22.1.1 3.3.1.1 Intermediate Range Monitor, Neutron Flux - High S120t125 divisions of full scale 22.12 3.3.1.1 Average Power Range Monitor, Neutron Flux -High S 15% of RATED THERMAL Setdown POWER 22.1.3 3.3.1.1 Average Power Range Monitor, Flow Biased See COLR-TRO 32 Simulated Thermal Power - High Two Loop Operation 22.1.4 3.3.1.1 Average Power Range Monitor. Flow Biased See COLR -TRO 32 Simulated Thermal Power -High Single Loop Operation 22.1.5 3.3.1.1 Average Power Range Monitor, Flow Biased S113.5% of RATED THERMAL Simulated Thermal Power -High Flow Clamped POWER 22.1.6 3.3.1.1 Average Power Range Monitor, Fixed Neutron Flux - S 118% of RATED THERMAL High POWER 22.1.7 3.3.1.1 Reactor Vessel Steam Dome Pressure - High s 1087 psig 22.1.8 3.3.1.1 Reactor Vessel Water Level - Low. Level 3 2 13.0 inches 22.1.9 3.3.1.1 Main Steam Isolation Valve - Closure S10% dosed 22.1.10 This Section Not Used 22.1.11 3.3.1.1 Drywell Pressure - High, S 1.72 psig 22.1.12 3.3.1.1 Scram Discharge Volume Water Level -High - Level S65 gallons Transmitter 22.1.13 3.3.1.1 Scram Discharge Volume Water Level - High - Float S61 gallons Switch 22.1.14 3.3.1.1 Turbine Stop Valve -Closure . S5.5% dosed 22.1.15 3.3.1.1 Turbine Contro Valve Fast Closure, Trip Oil 2 500 psig Pressure - Low 222 Isolation Actuation Instrumentation .

222.1 Primary Containment Isolation 222.1.1 3.3.6.1 Reactor Vessel Water Level Low, Level 3 2 13.0 inches 222.12 3.3.6.1 Reactor Vessel Water Level Low Low. Level 2

  • 238.0
inches 22.2.1.3 3.3.6.1 - Reactor Vessel Water Level Low Low low, Level I * -- 2 inches) 22.2.1.4 3.3.6.1 Drywell Pressure -High < 1.72 psig 222.1.5 3.3.6.1/[3.3.6] SGTS Exhaust Radiation - High S23.0 mRftl 22.2.1.6 [3.3.6]. Main Stearn Une Radiation-High High - - S15 x full power background without hydrogen injection (continued)

U)See Figure 2.2-1 SUSQUEHANNA - UNIT 2 TRM 2.0-6 EFFECTIVE DATE 10/2212003

Instrument Trip Seipoint Table PPL Rev. I.I  ;: 2.2 TABLE 22-1 (Page 2 of 7)

INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE LCO TRIP FUNCTION TRIP SETPOINT

[TRO]

2.2.2.2 Secondary Containment Isolation 2.22.2.1 3.3.6.2 Reactor Vessel Water Level - Low Low, Level 2 2 -38.0 inches I 222.2.2 3.3.6.2 Drywell Pressure -High 5 1.72 psig 2222.3 3.3.6.2 Refuel Floor HIgh Exhaust Duct Radiation - High S 18 mRthr 2222.4 3.3.62 Railroad Access Shaft Exhaust Duct Radiation - S 5 mR/hr High 2222.5 3.3.62 . Refuel Floor Wall Exhaust Duct Radiation - High s 21 mR/hr 222.3 Main Steam Line Isolation 222.3.1 3.3.6.1 Reactor Vessel Water Level - Low Low Low, 2 -129 inches t' Level 1 222.3.2 3.3.6.1 Main Steam Une Pressure -Low 2 861 psig 22.2.3.3 3.3.6.1 Main Steam Line Flow- High S 113 psid 222.3.4 3.3.6.1 CondenserVacuum-Low a 9.0 Inches Hg vacuum 222.3.5 3.3.6.1 Reactor Building Main Steam Une Tunnel 5 177 0 F Temperature - High 222.3.6 This Section Not Used 222.3.7 13.3.6] Reactor Building Main Steam Une Tunnel A s 990 F Temperature - High 2.22.3.8 13.3.6.1] Turbine Building Main Steam Tunnel. S 197F Temperature - High 222.4 Reactor Water Cleanup System Isolation 2.22.4.1 3.3.6.1 Reactor Vessel Water Level - Low Low, Level 2 * -38 inches(')

222.4.2 3.3.6.1 . RWCU A Flow High * ..* 59 gpm 222.4.3 3.3.6.1 RWCU Flow - High .* 462 gpm 22.2.4.4 3.3.6.1 RWCU Penetration Area Temperature - High

  • 131OF 22.2.4.5 [3.3.6] RWCU Penetration Room Area A Temperature - s 690 F High 22.2.4.6 3.3.6.1 RWCU Pump Area Temperature - High.
  • s 147OF 22.2A.7 [3.3.6] RWCU Pump Room Area A Temperature - High - -- 69F 22.2.4.8 3.3.6.1 -RWCU Heat Exchanger Area Temperature - High S 1470 F 22.2.4.9 [3.3.6] RWCU Heat Exchanger Room Area ... 69F A Temperature :High (oonhnued)

{" See Figure 2.2-1 SUSQUEHANNA - UNIT 2 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 SYSTEWNREFERENCE TRIP FUNCTION TRIP SETPOINT LCO [TRO]

22.2.5 Reactor Core Isolation Cooling System Isolation 2.2.2.5.1 3:3.6.1 RCIC Steam Une A Pressure - High £ 138 inches I+0 2.2.2.5.2 3.3.6.1 RCIC Steam Supply Line Pressure - Low a 60 psig 2.2.2.5.3 3.3.6.1 RCIC Turbine Exhaust Diaphragm Pressure - High - S 10.0 psig 2.2.2.5.4 3.3.6.1 RCIC Equipment Room Temperature - High s 167°F 222.5.5 3.3.6.1 RCIC Pipe Routing Area Temperature - High s 167°F 222.5.6 3.3.6.1 RCIC Emergency Area Cooler Temperature - High 5 167¶F 2.2.2.5.7

  • 3.3.6.1 Drywell Pressure - High 5 1.72 psig 222.5.8 [3.3.6] RCIC Equipment Room A Temperature - High  : 89°F 222.5.9 [33.6
  • RCIC Pipe Routing Area A Temperature - High £ 89OF 2.22.6 High Pressure Coolant Injection System Isolation 222.6.1 3.3.6.1 HPCI Steam Une A Pressure - High £ 370 inches 1+0 222.62 3.3.6.1 HPCI Steam Supply Une Pressure -Low 2 104 psig 222.6.3 3.3.6.1 HPCI Turbine Exhaust Diaphragm Pressure - High 10 psig 222.6.4 3.3.6.1 HPCI Equipment Room Temperature - High s1 67°F 222.6.5 3.3.6.1 HPCI Emergency Area Cooler Temperature - High S1 67°F 222.6.6 3.3.6.1 HPCI Pipe Routing Area Temperature - High s 167F 222.6.7 3.3.6.1 Drywell Pressure -High 5 1.72 psig 222.6.8 13.3.6] HPCI Equipment Room A Temperature - High £ 890F 222.6.9 13.3.6] HPCI Pipe Routing Area ATemperature -High 589¶F 222.7 Shutdown CoofingfSystem Isolation 222.7.1 3.3.6.1 Reactor Vessel Water Level - Low, Level 3 a 13.0 inches ° 222.72 3.3.6.1 Reactor Vessel Steam Dome Pressure - High £ 98 psig 222.7.3 13.3.6] RHR Flow- High . £ 25.000 gpm 22.3 ECCS Actuation 2.2.3.1 Core Spray System .

22.3.1.1 3.3.5.1 Reactor Vessel Water Level - LowLow Low, Level I * -129 inchesf')

2.2.3.12 3.3.5.1 Drywell Pressure - High * £1.72 psig 22.3.1.3 3.3.5.1 Reactor Vessel Steam Dome Pressure - Low injection 2 413. 5 427 psig permissive (continued)

" See Figure 22-1 SUSQUEHANNA - UNIT 2 TRM / 2.0-8 EFFECTIVE DATE 08130/2001

Instrument Trip Setpoint Program PPL Rev. 1- *: 2.2 TABLE 2.2-1 (Page 4 of 7)

INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE TRIP FUNCTION TRIP SETPOINT LCO [TRO]

22.3.2 LPCI Mode of RHR System 2.2.32.1 3.3.5.1 Reactor Vessel Water L.el - Low Low Low, Level1 2t -129 irches 2.2.3.22 3.3.5.1 Drywell Pressure - High . 1.72 psig 2.2.32.3 3.3.5.1 Reactor Vessel Steam Dome Pressure - Low. - 2413, S 427 psig hijection permissive 22.32.4 3.3.5.1 Reactor Vessel Steam Dome Pressure - Low, a 236 psig, decreasing Recirculation Discharge Valve permissive 22.3.3 HPCI System 2.2.3.3.1 3.3.5.1 Reactor Vessel Water Level - Low Low, Level 2 2 -38 inchesw 22.3.3.2 3.3.5.1 Drywell Pressure - High . 1.72 psig 2.2.3.3.3

  • 3.3.5.1 Condensate Storage Tank Level - Low . 36.0 kIches above tank bottom 2.2.3.3.4 3.3.5.1 Reactor Vessel Water Level - High, Level 8 S54 inches 22.3.4 Automatic Depressurzation System (ADS) 22.3.4.1 3.3.5.1 Reactor Vessel Water Level - Low Low Low, Level 1 - -129 inches 2.2.3.42 3.3.5.1 Drywell Pressure - High . 1.72 psig 22.3.4.3 3.3.5.1 ADS Timer 5102 seconds 2.2.3.4.4 3.3.5.1 Core Spray Pump Discharge Pressure- High 2135, 5155 psig 2.2.3.4.5 3.3.5.1
  • 13 Inches Confirmatory 2.2.3.4.7 3.3.5.1 ADS Drywell Pressure Bypass Timer .. 420 seconds 2.2.3.5 Loss of Power- ECCS Actuation 2.2.3.5.1 4.16kv ESS Bus Undervoltage (Loss of Votage < 20%)

22.3.5.1.1 3.3.8.1 Bus Undervoltage

  • 2 823.2. s 856.8 Volts 22.3.5.1.2 3.3.8.1 . Time delay -- -- 2 0.4r 0.6 seconds (continued)

" See Figure 22-1 SUSQU.EHANNA - UNIT 2 TRM 2.0-9 EFFECTIVE DATE 09/06/2002

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

INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE TRIP FUNCTION

  • TRIP SETFOINT LCO [TRO]

22.3.5.2 4.16kV ESS Bus Undervoltage (Degraded Voltage < 65%)

22.3.5.2.1 3.3.8.1 Bus Undervoltage 2 2641.1, 2748.9 Volts 22.3.5.22 3.3.8.1 Time delay 2 2.7, s 3.3 seconds 22.3.5.3 4.16kV ESS Bus Undervoltage (Degraded Voltage, < 93%)

2.2.3.5.3.1 3.3.8.1 Bus Undervoltage 2 3829.3, 3906.7 Volts 2.2.3.5.3.2 3.3.8.1 Time Delay (Non-LOCA) 2 4 minute, 30 seconds 5 minute, 30 seconds 22.3.5.3.4 3.3.8.1 Time Delay (LOCA) 2 9, 11 seconds 2.2.3.5.4 480V ESS Bus OB565 Undervoltage (Degraded Voltage, < 65%)

2.2.3.5A.1 [3.8.5] 480V Basis 2 308.9, 315.1 Volts 2.2.3.5.42 [3.8.5] Tlime Delay a 4.5, s 5.5 seconds 22.3.5.5 48V ESS Bus OB565 Undervoltage (Degraded Voltage. <92%)

22.3.5.5.1 13.8.51 480V Basis 2 437.6, 5 446.4 Volts 2.2.3.5.52 [3.8.51 Time Delay 29. 11 seconds 22.4 ATWS Alternate Rod Injection and Recirculation Pump Trip 2.2.4.1 3.3A243.1.1] ReactorVessel, Water Level - Low Low. Level 2-38 inches 1 2

2.2.4.1 3.3.4.24[3.1.1] Reactor Vessel Steam Dome Pressure -High 5 1 135 psig 2.2.5 End of Cycle Recirculation Pump Trip 22.5.1 3.3.4.1 Turbine Stop Vaive.Closure s 5.5% closed 2.2.5.2 3.3.4.1 Turbine Control Valve - Fast Closure 2 500 psig 22.6 Reactor Core Isolation Cooling System Actuation 22.6.1 3.3.52 Reactor Vessel Water Level - Low Low, Level 2 -- -384nches 22.6.2 3.3.52 * -Reactor Vessel Water Level - High, Level 8 s54 inches 22.6.3 3.3.52 Condensate Storage Tank Level -Low 2 36.0 inches above tank bottom (continued)

(a)See Figure 2.2-1 SUSQUEHANNA - UNIT 2 TRM / 2.01 0 EFFECTIVE DATE 04/12/1999

Instrument Trip Setpoint Program.

PPL Rev. 1. 2.2 TABLE 2.2-1 (Page 6 of 7)

INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE TRIP FUNCTION TRIP SETPOINT LCO [TRO]

2.2.7 Control Rod Block 22.7.1 Rod Block Monitor 2.2.7.1.1 3.3.2 Low Power Range Upscale -Two Loop Operation - 5 0.58W +52%

2.2.7.12 3.32 Low Power Range Upscale -Single Loop S0.58W +47%

Operation 22.7.1.3 Downscale 5%

22.72 -- APRM 22.72.1 [3.1.3] Flow Biased Simulated Thermal Power-High - Two See COLR -TRO 32 Loop Operation 22 722 (3.1.3] Fow Biased Simulated Thermal Power High - See COLR -TRO 32 Single Loop Operation 22.72.3 [3.1.3] Flow Biased Simulated Thermal Power High - High s 108% of RATED Flow Clamped THERMAL POWER 22.72.4 (3.1.3] Downscale 2 5%of RATED THERMAL POWER 22.72.5 [3.1.3] Neutron Flux - High Setdown '- 12% of RATED THERMAL POWER 22.7.3 Source Range Monitors 22.7.3.1 [3.1.3] . Jpscale s 2E5 cps 22.7.32 [3-13] I)ownscale 2 0.7 cps#

22.7.4 Intermediate Range Monitors 22.7A.1 3.1.3] . Jpscale s 108/125 divisions of full

  • scale 22.7.42 [3.123] . IDownscale * .2 5125 d'ivsions of full

2.2.7.62 [3.1.3] Comparator s 10% owdeviation' (continued)

Ib) Provided signal-to-noise ratio is 2 2. Otherwise 2 3 cps SUSQUEHANNA - UNIT 2 TRM / 2.0-11 EFFECTIVE DATE 04/12/1999

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

INSTRUMENTATION SETPOINTS SYSTEM/REFERENCE TRIP FUNCION TRIP SETPOINT LCO [TRO]

2.2.8 CREOASS 22.8.1 -3.3.7.1 Main Control Roam Outside Air Intake Radiation :s5 mR/hr Monitor 22.8.1.1 3.3.7.1 Reactor Vessel Water Level - Low Low. Level 2 2!-38.0 ches'1 2.2.8.12 3.3.7.1 Drywefl Pressure - High  :!1.72 psig 2.2.8.1.3 3.3.7.1 Refuel Floor High Exhaust Duct Radiation - High :518 mRthr 2.2.8.1.4 3.3.7.1 Railroad Access Shaft Exhaust Duct Radiation - :55 mR/hr Hgh 2.2.8.1.5 3.3.7.1 Refuel Floor Wall Exhaust Duct Radiation - High :5 21 mR/hr 2 .9 Feedwater/Main Turbine Trip System Actuation 2.2.9.1 3.3.22 Reactor Vessel Level - High :5 54.0 inches a 2.2.10 MVP Isolalion Main Steam Line Radiation - High High 2.2.10.1 [3.3.11) :515 x full power background withu hyrqe nection See Figure 2.2-1 SUSQUEHANNA - UNIT 2 TRM I2.0-12 EFFECTIVE DATE 10/22/2003

Instrument Trip Sefjtoint Program PPL Re.v. 1 -: 2.2

- - ' - T ." -

,).

.eo-850-L'-T - - WATER LEVEL NOENLsuJ

..\ H :ABOVE

/ 00 I , _

(8)

VESSLR 5S1.

.)NO. RIN

+54 (7) .5.88. +3?

-745- VESS (4) 557.S +30

_L~ (3) 540.S +13 (2) 489.5 -31

) 398.5 -129.

70-

650-
WO-_ f m . -

-5Sa.5 C I EUtbU-PbUs

-566.5 (7)

-537.5 (4):.

-'6t) 4--- t, ,-- I cjI .. , ~. ~55O-4 rCi .~

lfe1c4 r1.

30L A

.so 54.5 (3),NST. M rnips Q)A-13' I EIOTCHF STEAM __. t. _

>Z 1. z _ :_M1 .nnX -- - ns D_

I fRERSKIRT.

F 4N 5 -38 SCRA4

_- 1alTER 8:si(2) can . . CNRIBUE (2) INITIATE RCIC. TO ADS 450- -PCI. ARI TRIP RECM PUMS 400- 398.5 0) -129 (C).XTTATE RHR. CS 36.3- START. DIESEL, 350- COTRIfTE TO ADS

-150 C.S0EII

- 'S

.I 300- -

2504-

-216. 3-EL AMIvE

__200-1-- _. _.0-c R 18 . - --

-rdRC OUTLET I6-el.

sI

_ NOZZLE r NOZZ1 F 100-NOTE: SCLE NINCES so- - BOVE VESSEL ZERO FIGURE 2.2-1 REACTOR VESSEL WATER LEVEL eDi  : im.-L . . .11 SUSQUEHANNA - UN IT 2 TRM / 2.0-13 EFFECTIVE DATE 06/1612000

  • TRM Isolation Actuation Istrumentation 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 K .'1Z!

-1v, C - '-

1. Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A One or more required A1 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 AND

24 hours for

. _ . ~~~~Functions other than Functions 1.a

.__ ________ ______ _____ _ ______ __ _ _ _ _ _ _a nd 2 .a B. One or more Functions with 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 /> isolation capabilitylnot.

maintained.

SUSQUEHANNA - UNIT 2 TRM / 3.3-1 3 EFFECTIVE DATE 12/14/1998

TRM Isolation Actuation IrIstrumentation PPL Retv. 1  ;:. 3.3.6 TECHNICAL REQUIREMENT SURVEILLANCE I'd M.-

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 2 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 FUNCTION CONDITIONS TRIP SYSTEM REQUIREMENTS ALLOWABLE VALUE

1. Main Steam Line Isolation
a. Reactor Building 1,2,3 2 TRS 3.3.6.2 s 1080 F Main Steam Tunnel TRS 3.3.6.3 A Temperature - TRS 3.3.6.5 High
b. Turbine Building 1,2,3 2 TRS 3.3.6.2 S 2000 F Main Steam Line TRS 3.3.6.3 Tunnel Temperature TRS 3.3.6.5

- High

2. Primary Containment Isolation
a. Main Steam Line 1,2,3 2 TRS 3.3.6.1 521 xfull power Radiation - High TRS 3.3.6.2 background without High TRS 3.3.6.4 hydrogen injection
  • . * . TRS 3.3.6.5
  • * - ~~~~~~~TRS 3.3.6.6(";
3. High Pressure Coolant Injection (HPCI) System Isolation
a. HPCI Pipe Routing- 1,2,3 1 TRS 3.3.6:2 -S 98°F Area A Temperature TRS 3.3.6.3

- High TRS 3.3.6.5...

b. HPCI Equipment 1,2,3 1 TRS 3.3.6.2 5 98F Room TRS 3.3.6.3 A Temperature - TRS 3.3.6.5 High (continued)

(s)Radiation detectors are exempt from response time testing.

SUSQUEHANNA - UNIT 2 TRM / 3.3-15 EFFECTIVE DATE 10/2212003

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

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

4. Reactor Core Isolation Cooling (RCIC) System Isolation
a. RCIC Pipe 1.2.3 1 TRS 3.3.6.2 S 98F Routing Area TRS 3.3.6.3 ATemperature - TRS 3.3.6.5 High
b. RCIC Equipment 1.2.3 1 TRS 3.3.6.2 S 98 0F Room TRS 3.3.6.3 ATemperature- TRS 3.3.6.5 High
5. Reactor Water Cleanup (RWCU) System Isolation
a. RWCU . 1.2.3
b. RWCU Pump Area 1,2,3. 1 . TRS 3.3.6.2 720 F A Temperature- TRS 3.36.5 High S3..5
c. RWCU Heat 1.2,3 1 TRS 3.3.6.2 5720 F Exchanger Area TRS 3.3.6.3 A Temperature - TRS 3.3.6.5 High.
6. Shutdown Cooling System Isolation (a)

TRS 3.3.6.1 2,0 P

a. RHR Flow-High 3,4,5 1 TRS 3.3.6.2 S26,0gpm TRS 3.3.6.4 TRS 3.3.6.5 Not required when the penetration is isolated from the reactor vessel via manual Isolation valve, blind flange.

or deactivated auto isolation valve.

a..

SUSQUEHANNA-UNIT2 - TRM / 3.3-16 EFFECTIVE DATE 6/27/2001

TRM Isolation Actuation nstrumentation 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 lrT=Q.

Cod

-I-V

1. Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required A1 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 AND r

- < :24 hours for

. _ . ~~~~Functions other than Functions l.a and 2.a B. One or more Functions with 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 /> isolation capability'not maintained. _ _

SUSQUEHANNA- UNIT 2 TRM /3.3-1 3 EFFECTIVE DATE 12/14/1998

TRM Isolation Actuation ih:strumentation PPL Rev. 1 3.3.6 TECHNICAL REQUIREMENT SURVEILLANCE NOTES

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 2 TRM / 3.3-14 EFFECTIVE DATE 12114/1998

TRM Isolation Actuation Istrumentation PPL Re.v 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 FUNCTION CONDITIONS TRIP SYSTEM REQUIREMENTS ALLOWABLE VALUE

1. Main Steam Line Isolation
a. Reactor Building 1.2,3 2 TRS 3.3.6.2 S 108°F Main Steam Tunnel TRS 3.3.6.3 ATemperature - TRS 3.3.6.5 High
b. Turbine Building 1.2,3 2 TRS 3.3.6.2 S 2000 F Main Steam Line - - TRS 3.3.6.3 Tunnel Temperature TRS 3.3.6.5

-High

2. Primary Containment Isolation.. .
a. Main Steam Line 1.2,3 2 TRS 3.3.6.1 S 21 xfull power Radiation - High -. .TRS3.3.6.2-- background without High TRS 3.3.6.4 . hydrogen injection TRS 3.3.6.5 TRS 3.3.6.6
3. High Pressure Coolant Injecti6n(HPCI)Systein- - -- ----

Isolation

a. HPCI Pipe Routing 1.2,3 1 TRS 3.3.62 -- -* 98F Area A Temperature TRS 3.3.6.3

- High TRS 3.3.6.5 .. .

b. HPCI Equipment 1,2.3 1 TRS 3.3.6.2 s 980 F Room .TRS 3.3.6.3 ATemperature - TRS 3.3.6.5 High (continued)

(a)Radiation detectors are exempt from response time testing.

SUSQUEHANNA - UNIT 2 TRM~ / 3.3-15 EFFECTIVE DATE 10/22/2003

A TRM Isolation Actuation Iistrumentation PPL Rev. I 3.3.6 K>-1 TABLE 3.3.6-1 (Page 2 of 2)

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

4. Reactor Core Isolation Cooling (RCIC) System Isolation
a. RCICPipe 12.3 1 TRS3.3.6.2 S980 F Routing Area TRS 3.3.6.3 A Temperature - TRS 3.3.65 High
b. RCIC Equipment 1,2,3 1 TRS 3.3.6.2 s 98F Room TRS 3.3.6.3 A Temperature - TRS 3.3.6.5 High
5. Reactor Water Cleanup (RWCU) System K1 Isolation
a. RWCU 1.2.3 '1 TRS 3.3.62 -. 72 0F Penetration Area .TRS 3.3.6.3 A Temperature - . TRS 3.3.6.5 High
b. RWCU Pump Area 1.2,3. I TRS 3.3.6.2*- 7201F A Temperature - - TRS 3.3.6.-3---

High - TRS 3.3.6.5

c. RWCU Heat 1,2.3 I TRS 3.3.6.2 S72F Exchanger Area
  • TRS 3.3.6.3 ATemperature- TRS 3.3.6.5 High
6. Shutdown Cooling- - - -.

System Isolation (a)

a. RHR Flow- High 3.4,5 1 TRS 3.3.6.2 TRS 3.3.6.1 ~ 26,000 gpm 2,0 p 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.

111 SUSQUEHANNA - UNIT 2 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 2 TRM 3.31 9 EFFECTIVE DATE 1012212003

PPL Rev. 1 . 3.3.8 THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 2 TRM / 3.3-20 EFFECTIVE DATE 10/22/2003

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, (j) 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 2 TRM / B 3.3-1 0 U2EFFECTIVE 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 Actioris 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, TPrimary 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 Instrumentation 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 *onthe 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 2 TRM / B 3.3-11 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)

'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.

SUSQUEHANNA - UNIT 2 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 (Page of 1)

Plant systems Valve Number Valve Description Isolation Signal Function No.

(Table 3.3.6-1)

Nuclear Boiler HV-241 F022A MSIV 1.a, 1.b HV-241 F022B MSIV 1.a,1.b HV-241 F022C MSIV 1.a, 1.b HV-241 F022D MSIV 1.a, 1.b HV-241 F028A MSIV 1.a, 1.b HV-241 F028B MSIV 1.a, 1.b HV-241 F028C MSIV 1.a, 1.b HV-241 F028D MSIV 1.a, 1.b HV-241 FO1 6 MSL Drain Isolation Valve 1.a, 1.b HV-241 F01 9 MSL Drain Isolation Valve 1.a, 1.b Reactor Recirculation HV-243F019 Reactor Coolant Sample Valve 2.a HV-243F020 Reactor Coolant Sample Valve 2.a HPCI HV-255F002 HPCI Steam Supply Valve 3.a, 3.b HV-255F003 HPCI Steam Supply Valve 3.a, 3.b HV-255F100 HPCI Steam Supply Valve 3.a, 3.b HV-255F042 HPCI Suction Valve 3.a, 3.b RCIC HV-249F007 RCIC Steam Supply Valve . 4.a, 4.b HV-249F008 RCIC Steam Supply Valve 4.a, 4.b HV-249F088 RCIC Steam Supply Valve 4.a, 4.b RWCU HV-244F001 RWCU Suction Valve . 5.a, 5.b, 5.c

_ HV-244F004 RWCU Suction Valve - 5.a, 5.b, 5.c RHR HV-251 F022 RHR - Reactor Vessel Head Spray Valve

  • 6.a HV-251 F023 RHR - Reactor Vessel Head Spray Valve 6.a SUSQUEHANNA - UNIT 2 TRM / B 33-13 EFFECTIVE DATE 10/22/2003.

Mechanical Vacuum Pump (MVP) Isolation Instrumentation PPL Rev. 1..- 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 a 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 /> channel inoperble.

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 close Immediately associated Completion 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 2 TRM / 3.3-24 EFFECTIVE DATE 05/16/2003

Mechanical Vacuum Pump (MVP) Isolation Istrumentation PPL Rev 1  ;:. 3.3.11 TABLE 3.3.1 1-1 MVP ISOLATION INSTRUMENTATION REQUIRED SURVEILLANCE FUNCTION CHANNELS REQUIREMENTS ALLOWABLE VALUE SYSTEM

1. Main Steam Line . 2 TRS 3.3.11.1 <21 xfull power background Radiation - High TRS 3.3.11.2 without hydrogen injection High TRS 3.3.11.3 SUSQUEHANNA - UNIT 2 TRM 3.3-25 EFFECTIVE DATE 10122/2003

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

SUSQUEHANNA -UNIT 2 TRM /B3.3-15 EFFECTIVE DATE 10I2003

PPL Rev. 1 .. B 3.3.8 BASES (continued)

B 3.3.8 Section not used THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 2 TRM / B 3.3-16 EFFECTIVE DATE 1012/2003

PPL Rev. I B 3.3.8 BASES (continued)

B 3.3.8 Section not used THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNiT 2 TRM B 3.3-17 EFFECTIVE DATE 10/2212003

Mechanical Vacuum Pump (MVP) Isolation Instrumentation PPL Rev. 1 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 stack, 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 either MSL Radiation Monitor Ar or UB",

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 fodauto6mitically isolate the MVP System is restored promptly if lost during MVP.opbration.

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.

SUSQUEHANNA - UNIT 2 TRM / B 3.3-22 EFFECTIVE DATE 10/22/2003

Mechanical Vacuum Pump (MVP) Isolation Instrumentation PPL Rev. 1 B 3.3.11 Table B 3.3.11-1 MVP Isolation Components Plant Systems Component Component Description Isolation Signal Number Function No.

_ _(Table 3.3.11-1)

Vacuum Hogging HV-20731 MVP Suction Isolation Valve 1.

. 2P105 Mechanical Vacuum Pump 1.

SUSQUEHANNA - UNIT 2 TRM / B 3.3-23 EFFECTIVE DATE 05/16/2003

Retrieved from "https://kanterella.com/w/index.php?title=ML033100098&oldid=2639211"