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Technical Requirements Manual
	ML23345A084
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Site:	Susquehanna
Issue date:	11/28/2023
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To:	; Document Control Desk, Office of Nuclear Reactor Regulation
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MANUAL HARD COPY DISTRIBUTION DOCUMENT TRANSMITTAL 2023-14451 USER INFORMATION:

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of 10

SSES MANUAL Manual Name:

TRM2 nual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 Table Of Contents Issue Date:

11/27/.2023 Procedure Name Issue Date Change ID Change Nwnber TEXT LOES 99 01/03/2019

Title:

LIST OF EFFECTIVE SECTIONS

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TEXT TOC 29 11/27/2023

Title:

TABLE OF CONTENTS

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02/04/200.5 ~ ~/

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PLANT PROGRAMS AND SETPOINTS <N~~,UM~ TRIP SETPOINT TABLE

/1' ~,J 8/ /' *03/1'8./2021 TEXT 1.1 1

11/27/2023

Title:

USE AND APPLICATION DEFINITIONS TEXT 2.1

' 1 TEXT 3.0 r,._V'-,"'.

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Title:

APPLICABILITY TECHNICAL REQU~REMENT FOR OPERATION (TRO) APPLICABILITY

"~ '-./

TEXT 3.1.1

~-;:-~->11/09/2007

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Title:

REACTIVITY CONfRDL,SYSTEMS ANTICIPATED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS~ARI0 ~NSTRUMENTATION TEXT 3.1.2

(?~

0 11/19/2002

Title:

REACTIVITIY\\CON~R0L SYSTEMS CONTROL ROD DRIVE (CRD) HOUSING SUPPORT

'--" I

---.:._j TEXT 3.1. 3 5

12/18/2017

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD BLOCK INSTRUMENTATION TEXT 3.1.4 1

10/12/2020

Title:

REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VALVE TEXT 3.2.1 21 07/05/2023

Title:

CORE OPERATING LIMITS REPORT (COLR)

Page 1 of 15 Report Date: 11/27/23

SSES MANUAL Manual Name:

TRM2 Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.3.1 0

11/19/2002

Title:

INSTRUMENTATION RADIATION MONITORING INSTRUMENTATION TEXT 3.3.2 3

03/31/2011

Title:

INSTRUMENTATION SEISMIC MONITORING INSTRUMENTATION TEXT 3.3.3 2

11/09/2007

Title:

INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION TEXT 3.3.4 11 07/21/2017

Title:

INSTRUMENTATION TRM POST-ACCIDENT MONITORING INSTRUMENTATION TEXT 3.3.5 0

11/19/2002

Title:

INSTRUMENTATION THIS PAGE INTENTIONALLY LEFT BLANK TEXT 3.3.6 6

06/29/2023

Title:

INSTRUMENTATION TRM ISOLATION ACTUATION INSTRUMENTATION TEXT 3.3.7 5

08/08/2023

Title:

INSTRUMENTATION MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT 3.3.8 1

10/22/2003

Title:

INTENTIONALLY LEFT BLANK TEXT 3.3.9 3

05/14/2009

Title:

INSTRUMENTATION LPRM UPSCALE ALARM INSTRUMENTATION TEXT 3.3.10 1

12/14/2004

Title:

INSTRUMENTATION REACTOR RECIRCULATION PUMP MG SET STOPS TEXT 3.3.11 1

10/22/2003

Title:

INSTRUMENTATION MVP ISOLATION INSTRUMENTATION TEXT 3.3.12 2

04/02/2019

Title:

WATER MONITORING INSTRUMENTATION Page 2 of 15 Report Date: 11/27/23

SSES MANUAL Manual Name:

TRM2

.anual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.4.1 1

04/26/2006

Title:

REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM CHEMISTRY TEXT 3.4.2 1

04/16/2009

Title:

INTENTIONALLY LEFT BLANK TEXT 3.4.3 1

11/09/2007

Title:

REACTOR COOLANT SYSTEM REACTOR COOLANT SYSTEM (RCS)

TEXT 3.4.4 2

05/14/2009

Title:

REACTOR COOLANT SYSTEM REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT 3.4.5 1

04/26/2006

Title:

REACTOR COOLANT SYSTEM REACTOR VESSEL MATERIALS

.EXT 3.4.6 1

04/25/2013

Title:

REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION TEXT 3.5.1 2

03/05/2019

Title:

ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM ADS MANUAL INHIBIT TEXT 3.5.2 2

03/05/2019

Title:

ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM ECCS RPV WATER INVENTORY CONTROL AND RCIC MONITORING INSTRUMENTATION TEXT 3.5.3 1

03/05/2019

Title:

ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM LONG TERM NITROGEN SUPPLY TO ADS TEXT 3.6.1 1

11/27/2023

Title:

CONTAINMENT VENTING OR PURGING TEXT 3. 6.2

3 01/03/2019

Title:

SUPPRESSION CHAMBER TO DRYWELL VACUUM BREAKER POSITION INDICATION TEXT 3.6.3 0

11/19/2002

Title:

CONTAINMENT SUPPRESSION POOL ALARM INSTRUMENTATION Page 3 of 15 Report Date: 11/27/23

SSES MANUAL Manual Name:

TRM2 Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.6.4 1

11/27/2023

Title:

CONTAINMENT PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT 3.7.1 O

11/19/2002

Title:

PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM (ESW) SHUTDOWN TEXT 3.7.2 1

11/27/2023

Title:

PLANT SYSTEMS ULTIMATE HEAT SINK (UHS) AND GROUND WATER LEVEL TEXT 3.7.3.l 7

04/21/2022

Title:

PLANT SYSTEMS FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT 3.7.3.2 3

04/16/2009

Title:

PLANT SYSTEMS SPRAY AND SPRINKLER SYSTEMS TEXT 3.7.3.3 4

05/16/2016

Title:

PLANT SYSTEMS CO2 SYSTEMS TEXT 3.7.3.4 2

04/16/2009

Title:

PLANT SYSTEMS HALON SYSTEMS TEXT 3.7.3.5 2

04/16/2009

Title:

PLANT SYSTEMS FIRE HOSE STATIONS TEXT 3.7.3.6 2

04/16/2009

Title:

PLANT SYSTEMS YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT 3.7.3.7 1

04/26/2006

Title:

PLANT SYSTEMS FIRE RATED ASSEMBLIES TEXT 3.7.3.8 15 08/02/2021

Title:

PLANT SYSTEMS FIRE DETECTION INSTRUMENTATION TEXT 3.7.4 2

11/27/2023

Title:

PLANT SYSTEMS SOLID RADWASTE SYSTEM Page 4 of 15 Report Date: 11/27/23

SSES MANUAL Manual Name:

TRM2

.anual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.7.5.1 1

03/05/2015

Title:

PLANT SYSTEMS MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT 3.7.5.2 0

11/19/2002

Title:

PLANT SYSTEMS MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE TEXT 3.7.5.3 1

04/26/2006

Title:

PLANT SYSTEMS LIQUID HOLDUP TANKS TEXT 3.7.6 3

06/04/2012

Title:

PLANT SYSTEMS ESSW PUMPHOUSE VENTILATION TEXT 3.7.7 2

09/05/2008

Title:

PLANT SYSTEMS MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION EXT 3.7.8 9

03/05/2015

Title:

PLANT SYSTEMS SNUBBERS TEXT 3.7.9 2

03/05/2019

Title:

PLANT SYSTEMS CONTROL STRUCTURE HVAC TEXT 3.7.10 2

04/29/2014

Title:

PLANT SYSTEMS SPENT FUEL STORAGE POOLS (SFSPS)

TEXT 3.7.11 2

11/01/2018

Title:

PLANT SYSTEMS TEXT 3.8.1 4

08/02/2021

Title:

ELECTRICAL POWER PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTE~TIVE DEVICES TEXT 3.8.2.1 3

09/19/2023

Title:

ELECTRICAL POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -

CONTINUOUS TEXT 3. 8. 2. 2

Title:

ELECTRICAL AUTOMATIC Page 5 of 15 3

06/23/2021 POWER MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -

Report Date: 11/27/23

SSES MANUAL Manual Name:

TRM2 Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.8.3 4

01/28/2020

Title:

ELECTRICAL POWER DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT 3.8.4 2

11/27/2023

Title:

ELECTRICAL POWER 24 VDC ELECTRICAL SUBSYSTEM TEXT 3.8.5 l

11/14/2013

Title:

ELECTRICAL POWER DEGRADED VOLTAGE PROTECTION TEXT 3.8.6 3

03/05/2019

Title:

ELECTRICAL POWER EMERGENCY SWITCHGEAR ROOM COOLING TEXT 3.8.7 3

02/25/2021

Title:

BATTERY MAINTENANCE AND MONITORING PROGRAM TEXT 3.9.1 0

11/19/2002

Title:

REFUELING OPERATIONS DECAY TIME TEXT 3.9.2 0

11/19/2002

Title:

REFUELING OPERATIONS COMMUNICATIONS TEXT 3.9.3 1

03/12/2019

Title:

REFUELING OPERATIONS REFUELING PLATFORM TEXT 3.10.1 2

11/27/2023

Title:

MISCELLANEOUS SEALED SOURCE CONTAMINATION TEXT 3.10.2 l

04/09/2007

Title:

MISCELLANEOUS SHUTDOWN MARGIN TEST RPS INSTRUMENTATION TEXT 3.10.3 4

10/05/2022

Title:

MISCELLANEOUS INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

TEXT 3.10.4 2

04/17/2009

Title:

INTENTIONALLY LEFT BLANK 6

of 15 Report Date: 11/27/23

SSES MANUAL Manual Name:

TRM2

.anual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3. 11. 1. 1 2

11/27/2023

Title:

RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS CONCENTRATION TEXT 3. 11. 1. 2 2

11/27/2023

Title:

RADIOACTIVE EFFLUENTS LIQUID EFFLUENTS DOSE

'l'EXT 3. 11. 1. 3 2

11/27/2023

Title:

RADIOACTIVE EFFLUENTS LIQUID WASTE TREATMENT SYSTEM TEXT 3.11.1.4 3

11/27/2023

Title:

RADIOACTIVE EFFLUENTS LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT 3. 11. 1. 5 4

11/27/2023

Title:

RADIOACTIVE EFFLUENTS RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION

.EXT 3.11.2.l 5

11/27/2023

Title:

RADIOACTIVE EFFLUENTS DOSE RATE TEXT 3.11.2.2 2

11/27/2023

Title:

RADIOACTIVE EFFLUENTS DOSE -

NOBLE GASES TEXT 3.11.2.3 2

11/27/2023

Title:

RADIOACTIVE EFFLUENTS DOSE -

IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATE FORM TEXT 3.11.2.4 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS GASEOUS RADWASTE TREATMENT SYSTEM TEXT 3. 11. 2. 5 5

11/27/2023

Title:

RADIOACTIVE EFFLUENTS VENTILATION EXHAUST TREATMENT SYSTEM TEXT 3. 11. 2. 6 9

11/27/2023

Title:

RADIOACTIVE EFFLUENTS RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION TEXT 3.11.3 2

11/27/2023

Title:

RADIOACTIVE EFFLUENTS TOTAL DOSE Page 7 of 15 Report Date: 11/27/23

SSES MANUAL Manual Name:

TRM2 Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 3.11.4.1 6

11/27/2023

Title:

RADIOACTIVE EFFLUENTS MONITORING PROGRAM TEXT 3. 11. 4. 2 3

11/27/2023

Title:

RADIOACTIVE EFFLUENTS LAND USE CENSUS TEXT 3.11.4.3 2

11/27/2023

Title:

RADIOACTIVE EFFLUENTS INTERLABORATORY COMPARISON PROGRAM TEXT 3.12.1 0

11/19/2002

Title:

LOADS CONTROL PROGRAM CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT 3.12.2 4

04/17/2008

Title:

LOADS CONTROL PROGRAM HEAVY LOADS REQUIREMENTS TEXT 3.12.3 0

11/19/2002

Title:

LOADS CONTROL PROGRAM LIGHT LOADS REQUIREMENTS TEXT 4.1 0

09/27/2003

Title:

ADMINISTRATIVE CONTROLS ORGANIZATION TEXT 4.2 1

01/03/2019

Title:

ADMINISTRATIVE CONTROLS REPORTABLE EVENT ACTION TEXT 4.3 1

01/03/2019

Title:

ADMINISTRATIVE CONTROLS SAFETY LIMIT VIOLATION TEXT 4.4 1

12/18/2008

Title:

ADMINISTRATIVE CONTROLS PROCEDURES & PROGRAMS TEXT 4.5 2

11/27/2023

Title:

ADMINISTRATIVE CONTROLS REPORTING REQUIREMENTS TEXT 4.6 0

09/27/2003

Title:

ADMINISTRATIVE CONTROLS RADIATION PROTECTION PROGRAM Page 8 of 15 Report Date: 11/27/23

SSES MANUAL Manual Name:

TRM2

.anual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT 4.7 1

12/13/2022

Title:

ADMINISTRATIVE CONTROLS TRAINING TEXT B3.0 7

03/18/2021

Title:

APPLICABILITY BASES TECHNICAL REQUIREMENT FOR OPERATION (TRO) APPLICABILITY TEXT B3.l.l 2

04/29/2014

Title: REACTIVITY CONTROL SYSTEM BASES ANTICIP~TED TRANSIENT WITHOUT SCRAM ALTERNATE ROD INJECTION (ATWS-ARI) INSTRUMENTATION TEXT B3.l.2 0

11/19/2002

Title:

REACTIVITY CONTROL SYSTEM BASES CONTROL ROD DRIVE (CRD) HOUSING SUPPORT TEXT B3.l.3 4

12/18/2017

Title:

REACTIVITY CONTROL SYSTEM BASES CONTROL ROD BLOCK INSTRUMENTATION

.EXT B3.l.4 1

10/12/2020

Title:

REACTIVITY CONTROL SYSTEM BASES CONTROL ROD SCRAM ACCUMULATORS INSTRUMENTATION AND CHECK VA_LVE TEXT B3.2.l 0

11/19/2002

Title:

CORE OPERATING LIMITS BASES CORE OPERATING LIMITS REPORT (COLR)

TEXT B3.3.l 1

01/31/2014

Title:

INSTRUMENTATION BASES RADIATION MONITORING INSTRUMENTATION TEXT B3.3.2 2

03/31/2011

Title:

INSTRUMENTATION BASES SEISMIC MONITORING INSTRUMENTATION TEXT B3.3.3 2

11/09/2007

Title:

INSTRUMENTATION BASES METEOROLOGICAL MONITORING INSTRUMENTATION TEXT B3.3-.4 8

11/27/2023

Title:

INSTRUMENTATION BASES TRM POST ACCIDENT MONITORING (PAM) INSTRUMENTATION TEXT B3.3.5 2

11/09/2007

Title:

INSTRUMENTATION BASES THIS PAGE INTENTIONALLY LEFT BLANK Page 9 of 15 Report Date: 11/27/23

SSES MANUAL Manual Name:

TRM2 Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.3.6 7

06/29/2023

Title:

INSTRUMENTATION BASES TRM ISOLATION ACTUATION INSTRUMENTATION TEXT B3.3.7 5

08/08/2023

Title:

INSTRUMENTATION BASES MAIN TURBINE OVERSPEED PROTECTION SYSTEM TEXT B3.3.8 1

10/22/2003

Title:

INTENTIONALLY BLANK TEXT B3.3.9 4

01/03/2019

Title:

INSTRUMENTATION BASES LPRM UPSCALE ALARM INSTRUMENTATION TEXT B3.3.10 3

02/22/2012

Title:

INSTRUMENTATION BASES REACTOR RECIRCULATION PUMP MG SET STOPS TEXT B3.3.ll 1

10/22/2003

Title:

INSTRUMENTATION BASES MVP ISOLATION INSTRUMENTATION TEXT B3.3.12 1

04/02/2019

Title:

WATER MONITORING INSTRUMENTATION TEXT B3.4.1 0

11/19/2002

Title:

REACTOR COOLANT SYSTEM BASES REACTOR COOLANT SYSTEM CHEMISTRY TEXT B3.4.2 1

04/16/2009

Title:

REACTOR COOLANT SYSTEM BASES STRUCTURAL INTEGRITY TEXT B3.4.3 1

11/09/2007

Title:

REACTOR COOLANT SYSTEM BASES HIGH/LOW PRESSURE INTERFACE LEAKAGE MONITOR TEXT B3.4.4 1

01/03/2019

Title:

REACTOR COOLANT SYSTEM BASES REACTOR RECIRCULATION FLOW AND ROD LINE LIMIT TEXT B3.4.5 0

11/19/2002

Title:

REACTOR COOLANT SYSTEM BASES REACTOR VESSEL MATERIALS Page 10 of 15 Report Date: 11/27/23

SSES MANUAL Manual Name:

TRM2

.anual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.4.6 2

01/03/2019

Title:

REACTOR RECIRCULATION SINGLE LOOP OPERATION SLO FLOW RATE RESTRICTION TEXT B3.5.l 2

03/17/2020

Title:

ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM ADS MANUAL INHIBIT TEXT B3.5.2 2

03/05/2019

Title:

ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM ECCS RPV WATER INVENTORY CONTROL AND RCIC MONITORING INSTRUMENTATION TEXT B3.5.3 2

03/05/2019

Title:

ECCS RPV WATER INVENTORY CONTROL AND RCIC SYSTEM LONG 1ERM NITROGEN SUPPLY TO ADS TEXT B3.6.l 1

11/27/2023

Title:

CONTAINMENT BASES VENTING OR PURGING

.EXT B3.6.2 0

11/19/2002

Title:

CONTAINMENT BASES SUPPRESSION CHAMBER-TO-DRYWELL VACUUM BREAKER POSITION INDICATION TEXT B3.6.3 1

04/19/2007

Title:

CONTAINMENT BASES SUPPRESSION POOL ALARM INSTRUMENTATION TEXT B3.6.4 2

11/27/2023

Title:

CONTAINMENT BASES PRIMARY CONTAINMENT CLOSED SYSTEM BOUNDARIES TEXT B3.7.1 0

11/19/2002

Title:

PLANT SYSTEMS BASES EMERGENCY SERVICE WATER SYSTEM (SHUTDOWN)

TEXT B3.7.2 1

11/27/2023

Title:

PLANT SYSTEMS BASES ULTIMATE HEAT SINK (UHS) GROUND WATER LEVEL TEXT B3.7.3.1 4

02/16/2017

Title:

PLANT SYSTEMS BASES FIRE SUPPRESSION WATER SUPPLY SYSTEM TEXT B3.7.3.2 2

04/26/2006

Title:

PLANT SYSTEMS BASES SPRAY AND SPRINKLER SYSTEMS Page 11 of 15 Report Date: 11/27/23

SSES MANUAL Manual Name:

TRM2 Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.7.3.3 0

11/19/2002

Title:

PLANT SYSTEMS BASES CO2 SYSTEMS TEXT B3.7.3.4 3

06/19/2019

Title:

PLANT SYSTEMS BASES HALON SYSTEMS TEXT B3.7.3.5 1

0"4/26/2006

Title:

PLANT SYSTEMS BASES FIRE HOSE STATIONS TEXT B3.7.3.6 1

04/26/2006 Tide: PLANT SYSTEMS BASES YARD FIRE HYDRANTS AND HYDRANT HOSE HOUSES TEXT B3.7.3.7 0

11/19/2002

Title:

PLANT SYSTEMS BASES FIRE RATED ASSEMBLIES TEXT B3.7.3.8 3

09/27/2012

Title:

PLANT SYSTEMS BASES FIRE DETECTION INSTRUMENTATION TEXT B3.7.4 1

11/27/2023

Title:

PLANT SYSTEMS BASES SOLID RADWASTE SYSTEM TEXT B3.7.5.1 0

11/19/2002

Title:

PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS HYDROGEN MONITOR TEXT B3.7.5.2 0

11/19/2002

Title:

PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS EXPLOSIVE GAS MIXTURE TEXT B3.7.5.3 0

11/19/2002

Title:

PLANT SYSTEMS BASES LIQUID HOLDUP TANKS TEXT B3.7.6 4

06/04/2013

Title:

PLANT SYSTEMS BASES ESSW PUMPHOUSE VENTILATION TEXT B3.7.7 2

01/31/2008

Title:

PLANT SYSTEMS BASES MAIN CONDENSER OFFGAS PRETREATMENT LOGARITHMIC RADIATION MONITORING INSTRUMENTATION Page 12 of 15 Report Date: 11/27/23

SSES MANUAL Manual Name:

TRM2

.anual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.7.8 4

01/31/2014

Title:

PLANT SYSTEMS BASES SNUBBE~S TEXT B3.7.9 3

03/05/2019

Title:

PLANT SYSTEMS BASES CONTROL STRUCTURE HVAC TEXT B3.7.10 1

12/14/2004

Title:

PLANT SYSTEMS BASES SPENT FUEL STORAGE POOLS TEXT B3.7.ll 3

11/01/2018

Title:

STRUCTURAL INTEGRITY TEXT B3.8.l 2

03/10/2010

Title:

ELECTRICAL POWER BASES PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES

.EXT B3.8.2.l 1

09/19/2023

Title:

ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -

CONTINUOUS TEXT B3.8.2.2 2

06/23/2021

Title:

ELECTRICAL POWER BASES MOTOR OPERATED VALVES (MOV) THERMAL OVERLOAD PROTECTION -

AUTOMATIC TEXT B3.8.3 0

11/19/2002

Title:

ELECTRICAL POWER BASES DIESEL GENERATOR (DG) MAINTENANCE ACTIVITIES TEXT B3.8.4 1

11/27/2023

Title:

ELECTRICAL POWER BASES 24 VDC ELECTRICAL POWER SUBSYSTEM TEXT B3.8.5 1

11/14/2013

Title:

ELECTRICAL POWER BASES DEGRADED VOLTAGE PROTECTION TEXT B3.8.6 4

03/05/2019

Title:

ELECTRICAL POWER BASES EMERGENCY SWITCHGEAR ROOM COOLING TEXT B3 8 7 3

02/25/2021 Titl~:.BATTERY MAINTENANCE AND MONITORING PROGRAM Page 13 of 15 Report Date: 11/27/23

SSES MANUAL Manual Name:

TRM2 Manual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.9.l 0

11/19/2002

Title:

REFUELING OPERATIONS BASES DECAY TIME TEXT B3.*9. 2 0

11/19/2002

Title:

REFUELING OPERATIONS BASES COMMUNICATIONS TEXT B3.9.3 1

03/12/2019

Title:

REFUELING OPERATIONS BASES REFUELING PLATFORM TEXT B3.10.l 1

11/27/2023

Title:

MISCELLANEOUS BASES SEALED SOURCE CONTAMINATION TEXT B3.10.2 1

04/10/2007

Title:

MISCELLANEOUS BASES SHUTDOWN MARGIN TEST RP.S INSTRUMENTATION TEXT B3.10.3 3

10/05/2022

Title:

MISCELLANEOUS BASES INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)

TEXT B3.11. 1. 1 2

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS CONCENTRATION TEXT B3.11.1. 2 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES LIQUID EFFLUENTS DOSE TEXT B3. 11. 1. 3 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES LIQUID WASTE TREATMENT SYSTEM TEXT B3.11.1.4 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION TEXT B3.11.1. 5 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION TEXT B3.11.2.1 2

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES DOSE RATE Page 14 of 15 Date: 11/27 /23

SSES MANUAL Manual Name:

TRM2

.anual

Title:

TECHNICAL REQUIREMENTS MANUAL UNIT 2 TEXT B3.ll.2.2 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES DOSE -

NOBLE GASES TEXT B3.ll.2.3 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES DOSE -

IODINE, TRITIUM, AND RADIONUCLIDES IN PARTICULATES FORM TEXT B3.11. 2. 4 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES GASEOUS RADWASTE TREATMENT SYSTEM TEXT B 3. 11. 2. 5 6

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES VENTILATION EXHAUST TREATMENT SYSTEM TEXT B3.11. 2. 6 3

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

.EXT B3.ll.3 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES TOTAL DOSE TEXT B 3. 11. 4. 1 7

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES MONITORING PROGRAM TEXT B3.ll.4.2 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES LAND USE CENSUS TEXT B3.ll.4.3 1

11/27/2023

Title:

RADIOACTIVE EFFLUENTS BASES INTERLABORATORY COMPARISON PROGRAM TEXT B3.12.l 1

10/04/2007

Title:

LOADS CONTROL PROGRAM BASES CRANE TRAVEL-SPENT FUEL STORAGE POOL TEXT B3.12.2 1

12/03/2oio

Title:

LOADS CONTROL PROGRAM BASES HEAVY LOADS REQUIREMENTS TEXT B3.12.3 0

11/19/2002

Title:

LOADS CONTROL PROGRAM BASES LIGHT LOADS REQUIREMENTS Page 15 of 15 Report Date: 11/27)23

Rev. 1 1.0 USE AND APPLICATION*

1.1 Definitions Definitions 1.1

NOTE----------------------------------------------------------

The defined terms of this section appear in capitalized type and are applicable throughout these Technical Requirements and Bases.

Term ACTIONS CHANNEL CALIBRATION CHANNEL CHECK CHANNEL FUNCTIONAL TEST SUSQUEHANNA - UNIT 2 Definition ACTIONS shall be that part of a Technical Requirement that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.

A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, display, and trip functions, and shall include the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an in place qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel.

The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is calibrated.

A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.

A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify FUNCTIONALITY, including required alarm, interlock, display, and trip functions, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire* channel is tested.

(continued)

TRM / 1.0-1

Rev. 1 1.1 Definitions (continued)

FUNCTIONAL/

FUNCTIONALITY GASEOUS RADWASTE TREATMENT SYSTEM Definitions 1.1 A system, structure, or component (SSC) is FUNCTIONAL or has FUNCTIONALITY when it is capable of performing its function(s) as described in the design and licensing basis.

FUNCTIONALITY includes the ability of required support systems to perform their related support function(s) for equipment required to be OPERABLE by the Technical Specifications.

A GASEOUS RADWASTE TREATMENT SYSTEM shall be any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system offgases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

MEMBER(S) OF THE PUBLIC MEMBER(S) OF THE PUBLIC shall include all persons who are not occupationally associated with the plant. This category does not include employees of the utility, its contractors or vendors. Also excluded from this category are persons who enter the site to service equipment or to make deliveries. This category does include persons who use portions of the site for recreational, occupational or other purposes not associated with the plant.

MODE PROCESS CONTROL PROGRAM PURGE - PURGING SUSQUEHANNA - UNIT 2 A MODE shall correspond to any one inclusive combination of mode switch position, average reactor coolant temperature, and reactor vessel head closure bolt tensioning specified in Table 1.1-1 of the Technical Specifications with fuel in the reactor vessel.

The PROCESS CONTROL PROGRAM (PCP) shall contain the sampling, analysis, and formulation determination by which SOLIDIFICATION of radioactive wastes from liquid systems is assured.

PURGE or PURGING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is required to purify the confinement.

(continued)

TRM / 1.0-2

Rev. 1 1.1 Definitions (continued)

OPERABLE - OPERABILITY SITE BOUNDARY SOLIDIFICATION SOURCE CHECK THERMAL POWER UNRESTRICTED AREA VENTILATION EXHAUST TREATMENT SYSTEM SUSQUEHANNA - UNIT 2 Definitions 1.1 A system, subsystem, division, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified safety function(s) and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication, and other auxiliary equipment that are required for the system, subsystem, division, component, or device to perform its specified safety function(s) are also capable of performing their related support function(s).

The SITE BOUNDARY shall be that line beyond which the land is not owned, leased, or otherwise controlled by the licensee. See FSAR Section 2.1.1.2.

SOLIDIFICATION shall be the conversion of radioactive wastes from liquid systems to a homogeneous (uniformly distributed), monolithic, immobilized solid with definite volume and shape, bounded by a stable surface of distinct outline on all sides (free-standing).

A SOURCE CHECK shall be the qualitative assessment of channel response when the channel sensor is exposed to a radioactive source.

THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

An UNRESTRICTED AREA shall be any area at or beyond the SITE BOUNDARY access to which is not controlled by the licensee for purposes of protection of individuals from exposure to_ radiation and radioactive materials, or any area within the site boundary used for residential quarters or for industrial, commercial, institutional, and/or recreational purposes. See FSAR Section 2.1.1.3.

A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine or radioactive material in particulate form in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

(continued)

TRM / 1.0-3 I.

Rev. 1 1.1 Definitions (continued)

VENTING SUSQUEHANNA - UNIT 2 Definitions 1.1 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration or other operating condition, in such a manner that replacement air or gas is not provided or required during venting. Vent, used in system names, does not imply a VENTING process.

TRM / 1.0-4

Rev. 2 3.10 MISCELLANEOUS Sealed Source Contamination 3.10.1 3.10.1 Sealed Source Contamination TRO 3.10.1 Each sealed source containing radioactive material in excess of the following activities shall be free of greater than or equal to 0.005 microCurie of removable contamination.

APPLICABILITY:

ACTIONS ALPHA BETA GAMMA At all times SEALED SOURCE MINIMUM ACTIVITY 5

100 100

µCi

NOTE---------------------------------------------------------

The provisions of TRO 3.0.4 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A.

A sealed source has A.1 Withdraw the sealed Immediately removable source from use.

contamination in excess of the limit.

AND A.2.1 Initiate actions to Immediately decontaminate and repair the sealed source.

OR A.2.2 Initiate actions to dispose Immediately

of the 'sealed source in accordance with Federal Regulations.

SUSQUEHANNA - UNIT 2 TRM / 3.10-1

Rev. 2 Sealed Source Contamination 3.10.1 A_CT_I_O_N_S ______ -----,----------------.--------

CONDITION AND A.3 REQUIRED ACTION Initiate a condition report.

TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE COMPLETION TIME In accordance with the Corrective Action Program FREQUENCY TRS 3.10.1.1

NOTE-------------------------------

TRS 3.10.1.2 Test shall include all sealed sources in use with a half-life greater than 30 days, excluding the following sources:

sources containing hydrogen-3 (tritium),

sources in the form of a gas, startup sources, and fission detectors previously subjected to core flux.

Determine the level of leakage and contamination, as required, for each of the in use sources.

Determine the level of leakage and contamination, as required, of all sealed sources and fission detectors not in use.

SUSQUEHANNA - UNIT 2 TRM / 3.10-2 6 months

NOTE--------

N ot required to be performed if performed in the previous 6 months Prior to being placed into use or transferred to another licensee

Rev. 2 Sealed Source Contamination 3.10.1 TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE TRS 3.10.1.3 TRS 3.10.1.4 Determine the level of leakage and contamination, as required, of all sealed sources and fission

_detectors transferred without a certificate indicating the last test date.

Determine the level of leakage and contamination, as required, of each sealed startup source and fission detector.

SUSQUEHANNA - UNIT 2 TRM / 3.10-3 FREQUENCY Prior to being placed into use Within 31 days prior to being subjected to core flux or installed in the core AND Following repair or maintenance to the source

Rev. 2 3.11 RADIOACTIVE EFFLUENTS 3.11.1 Liquid Effluents 3.11.1.1 Liquid Effluents Concentration Liquid Effluents Concentration 3.11.1.1 TRO 3.11.1.1 The concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS (See FSAR Section 2.1.1.3) shall be limited to 10 times the concentrations specified in Appendix B, Table 2, Column 2 to 1 0CFR 20.1001 -20.2402 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 µCi/ml total activity.

APPLICABILITY:

At all times.

ACTIONS

NOTE--------------------------------------------------

The provisions of TRO 3.0.4 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A

Concentration of A 1.

Restore the concentration to Immediately radioactive material within the above limits.

released in liquid effluents to UNRESTRICTED AREAS (See FSAR Section 2.1.1.3) exceeds the limits specified in TRO 3.11. 1. 1.

SUSQUEHANNA - UNIT 2 TRM / 3.11-1

Rev.2 Liquid Effluents Concentration 3.11.1.1 TECHNICAL REQUIREMENT SURVEILLANCE TRS 3.11.1.1.1 TRS 3.11.1.1.2 SURVEILLANCE The radioactivity content of each batch of radioactive liquid waste shall be determined by sampling and analysis in accordance with Table 3.11.1.1-1. The results of pre-release analyses shall be used with the calculational methods and parameters in the ODCM to assure that the concentration at the point of release is maintained within the limits of TRO 3.11.1.1.

Post release analyses of samples composited from batch releases shall be performed in accordance with Table 3.11.1.1-1. The results of the previous post-release analyses shall be used with the calculational methods and parameters in the ODCM to assure that the concentrations at the point of release were maintained within the limits of TRO 3.11.1.1.

. SUSQUEHANNA - UNIT 2 TRM / 3.11-2 FREQUENCY Prior to each release According to the ODCM

Rev.2 TABLE 3.11.1.1-1 Liquid Effluents Concentration 3.11.1.1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM Lower Limit Minimum of Detection Liquid Release Sampling Analysis Type of Activity (LLD)

Type Frequency Frequency Analysis

(µCi/ml)

Batch Waste Prior to Prior to Principal Gamma 5E-7 Release Tanks Release Release Emitters Each Batch Each Batch 1-131 1E-6 Prior to 31 days Dissolved and 1E-5 Release Entrained Gases One Batch (Gamma Emitters)

Per Month Prior to 31 day H-3 1E-5 Release Composite(a)

Each Batch Gross Alpha 1E-7 Prior to 92 days SR-89. Sr-90 5E-8 Release Composite(a)

Each Batch Fe-55 IE-6 (a)

Minimum frequency for initiation of required analysis.

SUSQUEHANNA - UNIT 2 TRM / 3.11-3

Rev. 2 3.11 RADIOACTIVE EFFLUENTS 3.11.1 Liquid Effluents 3.11.1.2 Liquid Effluents Dose Liquid Effluents Dose 3.11.1.2 TRO 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each reactor unit UNRESTRICTED AREAS shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ.

b. During any calendar year to less than or equal to 3.0 mrems to the total body and to less than or equal to 10 mrems to any organ.

APPLICABILITY:

At all times.

ACTIONS

-*-----------------------------------------------------NOTE---------------------------------------------------------

The provisions of TRO 3.0.4 are not applicable.

CONDITION A.

Calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits.

SUSQUEHANNA - UNIT 2 REQUIRED ACTION A 1.

Initiate a condition report.

TRM / 3.11-4 COMPLETION TIME In accordance with the Corrective Action Program

Rev.2 TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE TRS 3.11.1.2.1 Determine cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year in accordance with methodology and parameters in the ODCM.

SUSQUEHANNA - UNIT 2 TRM / 3.11-5 Liquid Effluents Dose 3.11.1.2 FREQUENCY 31 days

Rev. 2 3.11 RADIOACTIVE EFFLUENTS 3.11.1 Liquid Effluents 3.11.1.3 Liquid Radwaste Treatment System Liquid Radwaste Treatment System 3.11.1.3 TRO 3.11.1.3 The appropriate portions of the Liquid Radwaste (LRW) Treatment System, as described in the ODCM, shall be FUNCTIONAL. Appropriate portions of the LRW Treatment System shall be used to reduce the radioactive materials in liquid effluent, prior to their discharge, when projected doses due to liquid effluent releases from each reactor unit to UNRESTRICTED AREAS would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in a 31 day period.

APPLICABILITY:

At all times.

ACTIONS

NOTE---------------------------------------------------------

The provisions of TRO 3.0.4 are not applicable.

CONDITION REQUIRED ACTION A

Liquid effluent releases A 1.

Initiate a condition report.

being discharged without treatment and in excess of the TRO limit.

SUSQUEHANNA - UNIT 2 TRM /3.11-6 COMPLETION TIME In accordance with the Corrective Action Program

Rev.2 Liquid Radwaste Treatment System 3.11.1.3 TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE TRS 3.11.1.3.1 Project doses due to liquid releases from each reactor unit to the UNRESTRICTED AREAS in accordance with the methodology and parameters in the ODCM.

TRS 3.11.1.3.2

NOTE-------------------------------

Not required to be performed if the LRW Treatment System has been utilized to process radioactive liquid during the previous 92 days.

FREQUENCY 31 days Demonstrate the LRW Treatment System is 92 days FUNCTIONAL by operating LRW Treatment System equipment for at least 10 minutes.

SUSQUEHANNA - UNIT 2 TRM/3.11-7

Rev. 3 Liquid Radwaste Effluent Monitoring Instrumentation 3.11.1.4 3.11 RADIOACTIVE EFFLUENTS 3.11.1 Liquid Effluents 3.11.1.4 Liquid Radwaste Effluent Monitoring Instrumentation TRO 3.11.1.4 The Radioactive Liquid Radwaste Effluent Monitoring Instrumentation channels shown in Table 3.11.1.4-1 shall be FUNCTIONAL with their setpoints established in accordance with the ODCM to ensure that the alarm/trip will occur prior to exceeding the limits of TRO 3.11.1.1.

APPLICABILITY:

At all times.

ACTIONS

NOTES-------------------------------------*-----

1. Separate condition entry is allowed for each channel.

2. The provisions of TRO 3.0.4 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more radioactive A.1 Suspend the release of Immediately liquid effluent monitoring radioactive liquid effluents instrumentation monitored by the affected alarm/trip channels channel.

setpoint less conservative than the OR limits allowed by TRO 3.11.1.1.

A.2 Declare the channel Immediately nonfunctional.

SUSQUEHANNA - UNIT 2 TRM / 3.11-8

Rev. 3 ACTIONS CONDITION B.

Liquid Radwaste B.1 releases are necessary and Effluent Line Gross Radioactivity Monitoring Instrumentation nonfunctional.

AND B.2 AND B.3 AND B.4 C.

Liquid Radw~ste C.1 releases are not in progress and the Gross Radioactivity Monitoring instrumentation is nonfunctional because the nonfunctional channel is caused by a discharge valve interlock in an off-normal condition or not functioning.

D.

Liquid Radwaste D. 1 releases are necessary and Effluent Line or Cooling Tower AND Slowdown Flow Monitoring D.2 Instrumentation nonfunctional.

SUSQUEHANNA - UNIT 2 Liquid Radwaste Effluent Monitoring Instrumentation 3.11.1.4 REQUIRED ACTION

.COMPLETION TIME Analyze at least two Prior to initiating each independent samples in release.

accordance with TRO 3.11.1.1.

\\

Independently determine Prior to initiating each release rates for samples release.

analyzed per Action B.1.

Perform and independently Prior to initiating each verify discharge valve lineup.

release.

Restore monitoring 30 days instrumentation.

Maintain at least one isoiation Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of valve closed between each securing from release source of release and the or discovery of liquid radwaste discharge nonfunctional valve.

instrument.

Estimate Flow Rate.

Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during releases.

Restore Monitoring 30 days Instrumentation.

TRM / 3.11-9

Liquid Radwaste Effluent Monitoring Instrumentation Rev. 3 3.11.1.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME E.

Liquid Radwaste E.1 Maintain at least one isolation Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of releases are not in valve closed between each securing release or progress and cooling source of release and the discovery of tower blowdown flow liquid radwaste discharge nonfunctional monitoring valve.

instrument instrumentation is nonfunctional because the nonfunctional channel is a discharge valve interlock in an off-normal condition or not functioning.

F.

Required Action and F.1

NOTE-------------

Associated Completion Only applicable to Time of Conditions B, C, Conditions B and D.

D, or E not met.

Effluent releases via this Immediately pathway may continue (up to 45 days from initial TRO entry) provided that Required Actions B.1, 8.2, 8.3 and D.1 are performed as applicable (within associated Completion Times). Otherwise, suspend release of radioactive effluents via this pathway.

AND F.2 Initiate a condition report.

In accordance with the Corrective Action Program SUSQUEHANNA - UNIT 2 TRM / 3.11-10

Rev. 3 Liquid Radwaste Effluent Monitoring Instrumentation 3.11.1.4 TECHNICAL REQUIREMENT SURVEILLANCE

NOTE---------------------

Refer to Table 3.11.1.4-1 to determine which TRSs apply for each Monitoring Function.

SURVEILLANCE TRS 3.11.1.4.1 Perform CHANNEL CHECK.

TRS 3.11.1.4.2 Perform CHANNEL CHECK including a SOURCE CHECK.

TRS 3.11.1.4.3 Perform CHANNEL FUNCTIONAL TEST.

TRS 3.11.1.4.4 Perform CHANNEL CALIBRATION.

SUSQUEHANNA - UNIT 2 TRM / 3.11-11 FREQUENCY 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Prior to commencing release 92 days 24 months

Rev. 3 Liquid Radwaste Effluent Monitoring Instrumentation 3.11.1.4 TABLE 3.11.1.4-1 LIQUID RADWASTE EFFLUENT MONITORING INSTRUMENTATION REQUIRED SURVEILLANCE FUNCTION CHANNELS REQUIREMENTS

1. GROSS RADIOACTIVITY MONITORS PROVIDING AUTOMATIC TERMINATION OF RELEASE

a. Liquid Radwaste Effluent Line

2. FLOW RA TE MEASUREMENT DEVICES

a. Liquid Radwaste Effluent Line

b. Cooling Tower Slowdown (a) Only required when performing batch releases.

SUSQUEHANNA - UNIT 2 TRM / 3.11-12 1

1 1

TRS 3.11.1.4.2 TRS 3.11.1.4.3 TRS 3.11.1.4.4 TRS 3.11.1.4.1 <a>

TRS 3.11.1.4.3 TRS 3.11.1.4.4 TRS 3. 11. 1.4. 1 <a>

TRS 3.11.1.4.3 TRS 3.11.1.4.4

Rev.4 Radioactive Liquid Process Monitoring Instrumentation 3.11.1.5 3.11 RADIOACTIVE EFFLUENTS 3.11.1 Liquid Effluents 3.11.1.5 Radioactive Liquid Process Monitoring Instrumentation TRO 3.11.1.5 The Radioactive Liquid Process Monitoring Instrumentation channels shown in Table 3.11.1.5-1 shall be FUNCTIONAL with their setpoints established in accordance with the ODCM to ensure the alarm will occur prior to exceeding the limits of TRO 3.11.1.1.

APPLICABILITY:

As specified in Table 3.11.1.5-1.

ACTIONS

._NOTES-------------------------------------------------------

1. Separate condition entry is allowed for each channel.

2. TRO 3.0.4.c is applicable.

3. The provisions of TRO 3.0.6 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A

One or more A.1 Suspend the release of Immediately Radioactive Liquid liquid effluents monitored Process Monitoring by the affected channel.

Instrumentation alarm/trip channels OR setpoint less conservative than the A.2 Declare the channel Immediately limits allowed by nonfunctional.

TRO 3.11.1.1.

SUSQUEHANNA - UNIT 2 TRM / 3.11-13

Rev.4 ACTIONS CONDITION B.

Radioactive Liquid Process Monitoring Instrumentation otherwise nonfunctional.

C.

Required Actions and Associated Completion Times of Condition B not met.

D.

RHR Heat Exchanger to be drained to the spray pond.

SUSQUEHANNA - UNIT 2 B.1.1 B.1.2 AND 8.2 C.1 D.1 Radioactive Liquid Process Monitoring Instrumentation 3.11.1.5 REQUIRED ACTION COMPLETION TIME Suspend the release of liquid Immediately effluents monitored by the affected channel.

OR Analyze grab samples for Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months isotopic activity to the when the associated required LLDs for liquid pathway is in service effluents (Table 3.11.1.1-1).

Restore monitoring 30 days instrumentation.

Initiate a condition report.

In accordance with the Corrective Action Program Analyze grab samples from Prior to draining RHR the RHR Heat Exchanger for Heat Exchanger to the isotopic activity to the spray pond required LLDs for liquid effluents (Table 3.11.1.1-1 ).

TRM / 3.11-14

Rev. 4 Radioactive Liquid Process Monitoring Instrumentation 3.11.1.5 TECHNICAL REQUIREMENT SURVEILLANCE

NOTE----------------------------------------------------------

Refer to Table 3.11.1.5-1 to determine which TRSs apply for each Monitoring Function.

SURVEILLANCE FREQUENCY TRS 3.11.1.5.1 Perform CHANNEL CHECK.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TRS 3.11.1.5.2 Perform a SOURCE CHECK.

31 days TRS 3.11.1.5.3 Perform CHANNEL FUNCTIONAL TEST.

92 days TRS 3.11.1.5.4 Perform CHANNEL CALIBRATION.

24 months SUSQUEHANNA - UNIT 2 TRM/3.11-15

Rev.4 Radioactive Liquid Process Monitoring Instrumentation 3.11.1.5 TABLE 3.11.1.5-1 RADIOACTIVE LIQUID PROCESS MONITORING INSTRUMENTATION REQUIRED FUNCTION CHANNELS APPLICABILITY SURVEILLANCE REQUIREMENTS GROSS RADIOACTIVITY MONITORS NOT PROVIDING AUTOMATIC TERMINATION OF RELEASE

1.

Service Water System 1

(a)

TRS 3.11.1.5.1 Effluent Line TRS 3.11.1.5.2

. TRS 3.11.1.5.3 TRS 3.11.1.5.4

2.

Supplemental Decay Heat 1

(a)

TRS 3.11.1.5.1 Removal Service Water TRS 3.11.1.5.2 TRS 3.11.1.5.3 TRS 3.11.1.5.4

3.

RHR Service Water 1/Loop (b)

TRS 3.11.1.5.1 System Effluent Line TRS 3.11.1.5.2 TRS 3.11.1.5.3 TRS 3.11.1.5.4 (a) System aligned through Fuel Pool Cooling Heat Exchanger. Alignment change between Service Water System Effluent Line and Supplemental Decay Heat Removal Service Water is not considered to be a change in the applicable condition.

(bl At all times.

SUSQUEHANNA - UNIT 2 TRM / 3.11-16

Rev. 5 Dose Rate 3.11.2.1 3.11 RADIOACTIVE EFFLUENTS 3.11.2 Gaseous Effluents 3.11.2.1 Dose Rate TRO 3.11.2.1 The dose rate due to radioactive materials released in gaseous effluents to areas at and beyond the SITE BOUNDARY (See FSAR APPLICABILITY:

ACTIONS Section 2.1.1.3) shall be limited to the following:

I.

For Noble Gases:

A Less than or equal to 500 mrems/yr to the total body, and B. Less than or equal to 3000 mrems/yr to the skin.

II. For iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half lives greater than 8 days.

A Less than or equal to 1500 mrem/yr to any organ (Inhalation pathways only).

At all times.

NOTE---------------------------------------------------

The provisions of.TRO 3.0.4 are not applicable.

CONDITION A

Dose rate( s) exceed the above limits.

SUSQUEHANNA - UNIT 2 REQUIRED ACTION A.1 Restore the release rate to within the above limits.

TRM/3.11-17 COMPLETION TIME Immediately

Rev. 5 TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE Dose Rate 3.11.2.1 FREQUENCY TRS 3.11.2.1.1 Determine the dose rate due to noble gases in See ODCM gaseous effluents..

TRS 3.11.2.1.2 The dose rate due to iodine-131, iodine-133, tritium, See and all radionuclides in particulate form with half-lives Table 3.11.2.1-1 greater than 8 days in gaseous effluents shall be determined to be within the limits in accordance with the methodology and parameters of the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 3.11.2.1-1.

SUSQUEHANNA - UNIT 2 TRM / 3.11-18

Rev. 5 Dose Rate 3.11.2.1 TABLE 3.11.2.1-1 RADIOACTIVE GASEOUS EFFLUENT SAMPLING AND ANALYSIS Sampling Lower Limit of Method and Minimum Analysis Type of Activity Detection (LLD)

Gaseous Release Type Frequency Frequency Analysis

(µCi/ml)

A. Containment Purge Prior to each purge Prior to each Principal Noble 1E-4 Grab Sample purge Gas Gamma Emitters H-3(e) 1E-6 B. Reactor Building 31 days (a) 31 days(a)

Principal Noble 1E-4 Vents, Turbine Grab Sample Gas Gamma Emitters Building Vents, and SGTS H-3 1E-6 Continuous(b) Iodine 7 days(c) 1-131 1E-12 Cartridge Sample 1-133 1E-10 Continuous(b) 7 days(cJ Principal 1 E-11 Particulate sample Particulate Gamma Emitters 1-131 Continuous(bl 92 days Gross Alpha 1 E-11 Particulate Sample Composite(d)

Continuous(b) 92 days Sr-89, Sr-90 1 E-11 Particulate sample Composite(d)

Continuous(b)

Noble Gas Noble Gases, Gross 1E-6 Monitor Beta or Gamma (Xe-133 equivalent)

(a)

Noble gas analyses shall be performed following shutdown, startup, or a THERMAL POWER change exceeding 15% of the RATED THERMAL POWER within a 1-hour period.

(b)

The ratio of the sample flow rate to the sampled stream flow rate shall be known for the time period covered by each dose or dose rate calculation made in accordance with TROs 3.11.2.1, 3.11.2.2, and 3.11.2.3.

(c)

Samples shall be changed at least:

1.

Once per 7 days; and

2.

Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for at least 7 days following each shutdown, startup, or thermal power change exceeding 15% of rated thermal power in 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if the noble gas monitor or grab samples show that effluent activity is

>1 E-6 µCi/cc and has increased by more than a factor of 3 when compared with effluent activity prior to the power change.

Analyses shall be completed within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months after change-outs. When samples collected for::s;24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months are analyzed, the corresponding LLD may be increased by a factor of 10.

(d)

Minimum frequency for initiation of required analysis.

(e)

Tritium analysis shall not be required prior to purging if the containment sample noble gas concentration does not

exceed the limiting containment noble gas concentration. However, the Tritium analysis shall be completed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after sampling.

SUSQUEHANNA - UNIT 2 TRM/3.11-19

Rev. 2 3.11 RADIOACTIVE EFFLUENTS 3.11.2 3.11.2.2 Gaseous Effluents Dose - Noble Gases Dose - Noble Gases 3.11.2.2 TRO 3.11.2.2

The air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY (See FSAR Section 2.1.1.3) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 5 mrads for gamma radiation and less than or equal to 10 mrads for beta radiation, and

b. During any calendar year: Less than or equal to 1 O mrads for gamma radiation and less than or equal to 20 mrads for beta radiation.

APPLICABILITY:

At all times.

ACTIONS

* --- NOTE ------------------------------------------------------------

The provisions of TRO 3.0.4 are not applicable.

CONDITION REQUIRED ACTION A

The calculated air dose A.1 Initiate a condition report.

exceeds the limits.

TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE COMPLETION TIME In accordance with the Corrective Action Program FREQUENCY TRS 3.11.2.2.1 Determine the cumulative dose contributions for the 31 days current calendar quarter and current calendar year for these sources in accordance with the methodology and parameters in the ODCM.

SUSQUEHANNA - UNIT 2 TRM / 3.11-20

Rev. 2 Dose - Iodine, Tritium, and Radionuclides in Particulate Form 3.11.2.3 3.11 RADIOACTIVE EFFLUENTS 3.11.2 Gaseous Effluents 3.11.2.3 Dose - Iodine, Tritium, and Radionuclides in Particulate Form TRO 3.11.2.3 The dose to a MEMBER OF THE PUBLIC from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, to areas at and beyond the SITE BOUNDARY shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any organ and,

b. During any calendar year: Less than or equal to 15 mrems to any organ.

APPLICABILITY:

At all times.

ACTIONS

NOTE-----------------------------------------------------

The provisions of TRO 3.0.4 are not applicable.

CONDITION A

The calculated dose from the release exceeds the limits.

REQUIRED ACTION A.1 Initiate a condition report.

TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE COMPLETION TIME In accordance with the Corrective Action Program FREQUENCY TRS 3.11.2.3.1 Determine the cumulative dose contributions for the 31 days current calendar quarter and current calendar year for these sources in accordance with the methodology and parameters in the ODCM.

SUSQUEHANNA - UNIT 2 TRM / 3.11-21

Rev. 1 GASEOUS RADWASTE TREATMENT SYSTEM 3.11.2.4 3.11 RADIOACTIVE EFFLUENTS 3.11.2 Gaseous Effluents 3.11.2.4 Gaseous Radwaste Treatment System TRO 3.11.2.4 The.GASEOUS RADWASTE TREATMENT SYSTEM shall be FUNCTIONAL and in operation.

APPLICABILITY:

When the main condenser air ejector (evacuation) system is in operation.

ACTIONS CONDITION REQUIRED ACTION A.

GASEOUS RADWASTE A.1 Restore GASEOUS TREATMENT SYSTEM RADWASTETREATMENT nonfunctional.

SYSTEM to FUNCTIONAL status.

B.

Required Action and B.1 Initiate a condition report.

associated Completion Time not met.

TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE TRS 3.11.2.4.1 Verify GASEOUS RADWASTE TREATMENT SYSTEM to be in operation.

SUSQUEHANNA - UNIT 2 TRM / 3.11-22 COMPLETION TIME 7 days In accordance with the Corrective Action Program FREQUENCY 92 days

Rev. 5 Ventilation Exhaust Treatment System 3.11.2.5 3.11 RADIOACTIVE EFFLUENTS 3.11.2 Gaseous Effluents 3.11.2.5 Ventilation Exhaust Treatment System TRO 3.11.2.5 The appropriate subsystems of the VENTILATION EXHAUST TREATMENT SYSTEM, as described in the Offsite Dose Calculation Manual (ODCM), shall be FUNCTIONAL.

NOTE---

Appropriate subsystems of the VENTILATION EXHAUST TREATMENT SYSTEM shall be used to reduce radioactive materials in gaseous waste prior to their discharge when projected doses due to gaseous effluent releases from either reactor unit to areas at and beyond the SITE BOUNDARY would exceed 0.3 mrem to any organ in a 31-day period.

APPLICABILITY:

At all times.

ACTIONS

------ NOTES --------------------------

1. Separate Condition entry is allowed for each subsystem.

2. The provisions of TRO 3.0.4 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A.

A subsystem of the A.1 Restore subsystem to 31 days VENTILATION FUNCTIONAL status.

EXHAUST TREATMENT SYSTEM nonfunctional.

SUSQUEHANNA - UNIT 2 TRM / 3. 11-23

Rev. 5 Ventilation Exhaust Treatment System 3.11.2.5 A_C_T_I_O_N_S ______ ~-----------....---------

CONDITION REQUIRED ACTION B.

Required Action and 8.1 Initiate a condition report.

Associated Completion Time of Condition A not met.

Gaseous waste from either reactor unit being discharged without appropriate treatment and in excess of 0.3 mrem to any organ in a 31-day period.

TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE TRS 3.11.2.5.1 Perform dose projection due to gaseous releases from each reactor unit to areas at and beyond the SITE BOUNDARY in accordance with the methodology and parameters in the ODCM.

COMPLETION TIME In accordance with the Corrective Action Program FREQUENCY 31 days TRS 3.11.2.5.2 ---------------------NOTE-------------------------

Not required if the appropriate subsystem has been utilized to process radioactive gaseous effluents during the previous 92 days.

Verify each subsystem of the VENTILATION 92 days EXHAUST TREATMENT SYSTEM is FUNCTIONAL by operating the subsystem ;:;,: 10 minutes.

TRS 3.11.2.5.3 Perform required HVAC filter testing in accordance with the Filter Testing Program.

SUSQUEHANNA - UNIT 2 TRM / 3.11-24 In accordance with the Filter Testing Program

Rev. 9 Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 3.11 RADIOACTIVE EFFLUENTS 3.11.2 Gaseous Effluents 3.11.2.6 Radioactive Gaseous Effluent Monitoring Instrumentation TRO 3.11.2.6 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.11.2.6-1 shall be FUNCTIONAL with their setpoints established in accordance with the ODCM to ensure that the limits of TRO 3.11.2.1 are not exceeded.

APPLICABILITY:

According to Table 3.11.2.6-1 ACTIONS

NOTES--------

1. Separate condition entry is allowed for each channel.

2. The provisions of TRO 3.0.6 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A.

Radioactive gaseous A.1 Suspend the release of Immediately effluent monitoring radioactive gaseous effluents instrumentation channel monitored by the affected alarm/trip setpoint less channel.

conservative than required to ensure that OR the limits of TRO 3.11.2.1 are not A.2 Declare the channel Immediately exceeded.

nonfunctional.

SUSQUEHANNA - UNIT 2 "TRM / 3.11-25

Rev. 9 ACTIONS CONDITION B.

Reactor Building 8.1 Ventilation System Noble Gas Activity Monitor low range channel nonfunctional.

AND 8.2 AND 8.3 C. Deleted.

D.

Reactor Building D. 1 Ventilation Monitoriryg System: Effluent Flow Rate Monitor or Sample (Bypass or Low Range)

AND Flow Rate Monitor nonfunctional.

D.2 SUSQUEHANNA - UNIT 2 Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 REQUIRED ACTION COMPLETION TIME Take grab samples.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months while release is in progress Analyze grab samples for Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of isotopic activity to the grab sample required LLDs for principal noble gas gamma emitters (Table 3.11.2.1-1).

Restore monitoring 30 days instrumentation.

Estimate flow rate.

Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months while rel~ase is in progress Restore monitoring 30 days instrumentation.

TRM / 3.11-26

Rev. 9 ACTIONS CONDITION E.

Turbine Building E.1 Ventilation System Noble Gas Activity Monitor low range AND channel nonfunctional.

E.2 AND E.3 AND E.4 F.

Deleted.

G. Turbine Building G.1 Ventilation Monitoring System: Effluent Flow Rate Monitor or Sample (Bypass or Low Range)

AND Flow Rate Monitor nonfunctional.

G.2 SUSQUEHANNA - UNIT 2 Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 REQUIRED ACTION COMPLETION TIME Verify mechanical vacuum Immediately pump is not in operation.

Take grab samples.

Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months while release is in progress Analyze grab samples for Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after isotopic activity to the required sample LLDs for principal noble gas gamma emitters (Table 3.11.2.1-1).

Restore monitoring 30 days instrumentation.

Estimate flow rate.

Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months while release is in progress Restore monitoring 30 days instrumentation.

TRM / 3.11-27

Rev. 9 ACTIONS CONDITION H.

Standby Gas Treatment H.1 System Noble Gas Activity Monitor low range channel nonfunctional.

AND H.2 AND H.3 I.

Deleted.

J.

SGTS Ventilation J.1 Monitoring System:

Effluent flow rate monitor or sample (Bypass or Low Range) flow rate AND monitor nonfunctional.

J.2 K.

Required Actions and K.1 Completion Times not met for Conditions B through J.

SUSQUEHANNA - UNIT 2 Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 REQUIRED ACTION COMPLETION TIME Take grab samples.

Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during operation of SGTS Analyze grab samples for Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of isotopic activity to the required grab sample being LLDs for principal noble gas taken gamma emitter~

(Table 3.11.2.1-1).

Restore monitoring 30 days instrumentation.

Estimate flow rate.

Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months during operation of SGTS Restore monitoring 30 days Instrumentation.

Initiate a condition report.

In accordance with the Corrective Action Program TRM / 3. 11-28

Rev. 9 Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 TECHNICAL REQUIREMENT SURVEILLANCE

NOTE---------------------------------------

Refer to Table 3.11.2.6-1 to determine which TRSs apply for each Monitoring Function.

SURVEILLANCE FREQUENCY TRS 3.11.2.6.1 Perform CHANNEL CHECK.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months TRS 3.11.2.6.2 Deleted.

TRS 3.11.2.6.3 Perform SOURCE CHECK.

31 days TRS 3.11.2.6.4 Perform CHANNEL FUNCTIONAL TEST.

92 days TRS 3.11.2.6.5 Perform CHANNEL CALIBRATION.

24 months SUSQUEHANNA - UNIT 2 TRM / 3.11-29

Rev. 9 Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 TABLE 3.11.2.6-1 (Page 1 of 3)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION REQUIRED SURVEILLANCE FUNCTION APPLICABILITY CHANNELS REQUIREMENTS

1. REACTOR BUILDING VENTILATION MONITORING SYSTEM

a. Noble Gas Activity Monitor At all Times 1

TRS 3.11.2.6.1

{Low Range)

TRS 3.11.2.6.3 TRS 3.11.2.6.4 TRS 3.11.2.6.5

b. Deleted C. Deleted d

Effluent System Flow Rate At all Times 1

TRS 3.11.2.6.1 Monitor TRS 3.11.2.6.4 TRS 3.11.2.6.5

e. Sample Flow Rate Monitor At all Times 1

TRS 3.11.2.6.1 (Bypass)

TRS 3.11.2.6.4 TRS 3.11.2.6.5

f.

Sample Flow Rate Monitor At all Times 1

TRS 3.11.2.6.1 (Low Range)

TRS 3.11.2.6.4 TRS 3.11.2.6.5 SUSQUEHANNA - UNIT 2 TRM / 3.11-30

Rev. 9 Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 TABLE 3.11.2.6-1 (Page 2 of 3)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION REQUIRED SURVEILLANCE FUNCTION APPLICABILITY CHANNELS REQUIREMENTS

2. TURBINE BUILDING VENTILATION MONITORING SYSTEM

a. Noble Gas Activity Monitor (Low Range)

b. Deleted

c. Deleted

d. Effluent System Flow Rate Monitor

e. Sample Flow Rate Monitor (Bypass)

f.

Sample Flow Rate Monitor (Low Range)

SUSQUEHANNA - UNIT 2 At all Times At all Times At all Times At all Times TRM /3.11-31 1

1 1

1 TRS 3.11.2.6.1 TRS 3.11.2.6.3 TRS 3.11.2.6.4 TRS 3.11.2.6.5 TRS 3.11.2.6.1 TRS 3.11.2.6.4 TRS 3.11.2.6.5 TRS 3.11.2.6.1 TRS 3.11.2.6.4 TRS 3.11.2.6.5 TRS 3.11.2.6.1 TRS 3.11.2.6.4 TRS 3.11.2.6.5

Rev.9 Radioactive Gaseous Effluent Monitoring Instrumentation 3.11.2.6 TABLE 3.11.2.6-1 {Page 3 of 3)

RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION REQUIRED SURVEILLANCE FUNCTION APPLICABILITY CHANNELS REQUIREMENTS

3. STANDBY GAS TREATMENT SYSTEM (SGTS) MONITOR

a. Noble Gas Activity Monitor (Low Range)

b. Deleted C. Deleted

d. Effluent System Flow Rate Monitor

e. Sample Flow Rate Monitor (Bypass)

f.

Sample Bypass Flow Rate Monitor (Low Range)

(a) TRO 3.0.4.c is applicable.

SUSQUEHANNA - UNIT 2 During operation of SGTSCa>

During operation of SGTSCa>

During operation of SGTSCa)

During operation of SGTSCa>

TRM / 3.11-32 1

TRS 3.11.2.6.1 TRS 3.11.2.6.3 TRS 3.11.2.6.4 TRS 3.11.2.6.5 1

TRS 3.11.2.6.1 TRS 3.11.2.6.4 TRS 3.11.2.6.5 1

TRS 3.11.2.6.1 TRS 3.11.2.6.4 TRS 3.11.2.6.5

Rev. 2 3.11 RADIOACTIVE EFFLUENTS 3.11.3 Total Dose Total Dose 3.11.3 TRO 3.11.3 The annual (calendar year) dose or dose commitment to any MEMBER OF THE PUBLIC, due to releases of radioactivity and radiation, from uranium fuel cycle sources shall be limited to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.

APPLICABILITY:

At all times ACTIONS

NOTE------------ ----------------

The provisions of TRO 3.0.4 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A.

Calculated doses from

. A.1 Initiate actions to calculate Immediately the release of whether the TRO limits have radioactive materials in been exceeded.

liquid or gaseous effluents exceed twice the limits of Requirements 3.11.1.2.a, 3.11.1.2.b, 3.11.2.2.a, 3.11.2.2.b, 3.11.2.3.a, or 3.11.2.3.b.

B.

TRO limits exceeded.

8.1 Initiate a condition report.

In accordance with the Corrective Action Program SUSQUEHANNA - UNIT 2 TRM / 3.11-33

Rev.2 TECHNICAL REQUIREMENT SURVEILLANCE TRS 3.11.3.1 TRS 3.11.3.2 SURVEILLANCE Determine the cumulative dose from liquid and gaseous effluents in accordance with the methodology and parameters in the ODCM.

Determine cumulative dose contributions from direct radiation from unit operation in accordance with the methodology and parameters in the ODCM.

SUSQUEHANNA - UNIT 2 TRM / 3.11-34 Total Dose 3.11.3 FREQUENCY 31 days 12 months

Rev.6 3.11 RADIOACTIVE EFFLUENTS 3.11.4 Radiological Environmental Monitoring 3.11.4.1 Monitoring Program Monitoring Program 3.11.4.1 TRO 3.11.4.1 The Radiological Environmental Monitoring Program shall be conducted as specified in Table 3.11.4.1-1.

APPLICABILITY:

At all times ACTIONS

*-------------------NOTE------------------------

The provisions of TRO 3.0.4 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A.

Radiological A.1 Initiate a condition report.

In accordance with the Environmental Corrective Action Monitoring Program not Program being conducted as specified in Table 3.11.4.1-1.

B.

The average level of B.1 Initiate a condition report.

In accordance with the radioactivity over any Corrective Action calendar quarter as the Program result of an individual radionuclide in plant effluents in a particular environmental exposure pathway in a particular environmental sampling medium, at a specified location exceeds the applicable reporting level of Table 3.11.4.1-2.

SUSQUEHANNA - UNIT 2 TRM / 3.11-35

Rev.6 ACTIONS CONDITION C.

More than one of the radionuclides in Table 3.11.4.1-2 are detected in a particular environmental exposure pathway at a specified monitoring location and are the result of plant effluents.

AND The sum of the ratios of the quarterly average activity levels to their corresponding reporting levels of each detected radionuclide, from Table 3.11.4.1-2, is

~ 1.0.

D.

One ormore Radionuclide(s) other than those in Table 3.11.4.1-2 are detected in a particular environmental exposure pathway at a specified location and are the result of plant effluents.

AND The potential annual dose to a MEMBER OF THE PUBLIC from all detected radionuclides that are the result of plant effluents is greater than or equal to the calendar year limits of TROs 3.11.1.2, 3.11.2.2 and 3.11.2.3.

SUSQUEHANNA - UNIT 2 REQUIRED ACTION C.1 Initiate a condition report.

D.1 Initiate a condition report.

TRM / 3.11-36 Monitoring Program 3.11.4.1 COMPLETION TIME In accordance with the Corrective Action Program In accordance with the Corrective Action Program

Rev.6 ACTIONS CONDITION E.

All requirements for a Special Report per either Condition B, C, or D are met except that the radionuclides detected are not the result of plant effluents.

F.

Milk or fresh leafy vegetable samples are unavailable from one or more of the sample locations required by Table 3.11.4.1-1.

SUSQUEHANNA - UNIT 2 REQUIRED ACTION E.1 Initiate a condition report.

NOTE --

The specific locations from which samples were unavailable may then be deleted from the monitoring program.

F.1 Initiate a condition report.

TRM / 3.11-37 Monitoring Program 3.11.4.1 COMPLETION TIME In accordance with the Corrective Action Program In accordance with the Corrective Action Program

Rev. 6 Monitoring Program 3.11.4.1 TECHNICAL REQUIREMENT SURVEILLANCE

-------------------------------- NOTE --------------------

The provisions of TRS 3.0.3 are not applicable to the below surveillances.

SURVEILLANCE TRS 3.11.4.1.1 Collect the radiological environmental monitoring samples pursuant to Table 3.11.4.1-1.

TRS 3.11.4.1.2 Analyze samples pursuant to.the requirements of Table 3.11.4.1-1 with equipment meeting the detection capabilities required by Table 3.11.4.1-3.

TRS 3.11.4.1.3 Determine annual cumulative potential dose contributions from radionuclides detected in environmental samples in accordance with the methodology and parameters in the ODCM.

SUSQUEHANNA - UNIT 2 TRM / 3.11-38 FREQUENCY As required by Table 3.11.4.1-1 As required by Table 3.11.4.1-1 Annually

Rev. 6 Monitoring Program 3.11.4.1 TABLE 3.11.4.1-1 (Page 1 of 3)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

1.

2.

EXPOSURE PATHWAY AND/OR SAMPLE DIRECT RADIATION AIRBORNE Radioiodine and Particulates NUMBER OF REPRESENTATIVE SAMPLES AND.

SAMPLE LOCATIONS 40 routine monitoring stations with two or more dosimeters or with one instrument for measuring and recording dose rate continuously placed as follows:

1.

An inner ring of stations, one in each meteorological sector, in the general area of the SITE BOUNDARY

2.

An outer ring of stations, one in each meteorological sector, in the 3 to 9 mile range from the site

3.

The balance of the stations placed in special interest areas such as population centers, nearby residences, schools, and in 1 or 2 areas to serve as control stations Samples from 5 locations

a. 1 sample from close to each of the 3 SITE BOUNDARY locations (in different sectors) with the highest calculated annual average ground level D/Q

b. 1 sample from the vicinity of the community having one of the highest calculated annual ground level O/Q C.

1 sample from a control location, between 15 and 30 km distant and in the least prevalent wind direction of wind blowing from the plant SAMPLING AND COLLECTION FREQUENCY Quarterly Continual sampler operation with sample collection weekly, or more frequently if required by dust loading TYPE AND FREQUENCY OF ANALYSIS Gamma dose quarterly Radioiodine Canister:

1-131 Analysis weekly Particulate Samgler:

Gross Beta radio activity analysis following filter change<al Gamma isotopic analysis of composite (by location) quarterly (al Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or more after sampling to allow for radon and thorn daughter decay. If gross beta activity in air particulate samples is greater than ten times the yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples.

SUSQUEHANNA - UNIT 2 TRM / 3.11-39

Rev. 6 Monitoring Program 3.11.4.1 TABLE 3.11.4.1-1 (Page 2 of 3)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE NUMBER OF SAMPLING AND PATHWAY AND/OR REPRESENTATIVE SAMPLES COLLECTION TYPE AND FREQUENCY SAMPLE AND SAMPLE LOCATIONS FREQUENCY OF ANALYSIS

3.

WATERBORNE

a. Surface 1 sample upstream Upstream Sample:

Gamma isotopic 1 sample downstream Composite analysis monthly.

sample over Composite for one-month tritium analyses quarterly period Downstream Sample:

weekly grab sample, composited monthly

b. Ground Samples from 1 or 2 sources Quarterly Gamma isotopic and only if likely to be affected tritium analyses quarterly C. Drinking 1 sample from each of 1 to 3 of Composite sample I-131 analysis on each the nearest water supplies that over 2-week period composite when the dose could be affected by its discharge when 1-131 analysis calculated for the is performed, monthly consumption of the water 1 sample from a control location composite otherwise is greater than 1 mrem per year. Composite for gross beta and gamma isotopic analyses monthly.

Composite for tritium analyses quarterly

d. Sediment from 1 sample from downstream area Semiannually Gamma isotopic analyses shoreline with existing or potential semiannually recreational value SUSQUEHANNA - UNIT 2 TRM / 3.11-40

Rev. 6 Monitoring Program 3.11.4.1 TABLE 3.11.4.1-1 (Page 3 of 3)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXPOSURE NUMBER OF REPRESENTATIVE SAMPLING AND TYPE AND PATHWAY SAMPLES AND SAMPLE COLLECTION FREQUENCY OF AND/OR SAMPLE LOCATIONS FREQUENCY ANALYSIS

4.

INGESTION

a. Milk

a.

Samples from milking animals in Semimonthly when Gamma isotopic and 3 locations within 5km from the animals are on 1-131 analysis plant having the highest dose pasture, monthly at semimonthly when potential. If there are none, other times.

animals are on then, 1 sample from milking pasture; monthly at animals in each of 3 areas other times.

between 5 and 8km distant where doses are calculated to be greater than 1 mrem per year.

1 sample from milking animals at a control location (between 15 and 30km from the plant preferably in the least prevalent direction for wind blowing from the plant).

b. Fish and/or

b.

1 sample of each of two Sample in season, or Gamma isotopic Invertebrates recreationally important species semiannually if they analysis on edible in vicinity of plant discharge are not seasonal.

portions.

area.

1 sample of same species in areas not influenced by plant discharge.

c. Food Products C.

1 sample of each principal class At time of harvest Gamma isotopic of food products from any area, analysis on edible which is irrigated by water in portions.

which liquid plant wastes have been discharged.

Samples of 3 different kinds of Monthly when Gamma isotopic and broad leaf vegetation grown available 1-131 analysis.

nearest each of two different offsite locations of highest predicted annual average ground level D/Q if milk sampling is not performed.

1 sample of each of the similar Monthly when Gamma isotopic and broad leaf vegetation grown available 1-131 analysis.

between 15 to 30km from the plant, preferably, in the least prevalent direction for wind blowing from the plant if milk sampling is not performed.

SUSQUEHANNA - UNIT 2 TRM /'3.11-41

Rev. 6 TABLE 3.11.4.1-2 Monitoring Program 3.11.4.1 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS IN ENVIRONMENTAL SAMPLES REPORTING LEVELS Water Airborne Particulate Fish Milk Food Products Analysis (pCi/I) or Gases (pCi/m3)

(pCi/kg, wet)

(pCi/I)

(pCi/kg, wet)

H-3 20,ooo<a)

Mn-54 1,000 30,000 Fe-59 400 10,000 Co-58 1,000 30,000 Co-60 300 10,000 Zn-65 300 20,000 Zr-Nb-95 400(b) 1-131 2

0.9 3

100 Cs-134 30 10 1,000 60 1,000 Cs-137 50 20 2,000 70 2,000 Ba-La-140 200(b) 300 (a) For drinking water samples. This is 40 CFR Part 141 value. If no drinking water pathway exists, a value of 30,000 pCi/I may be used.

(b) Total for parent and daughter.

SUSQUEHANNA - UNIT 2 TRM / 3. 11-42

Monitoring Program Rev.6 3.11.4.1 TABLE 3.11.4.1-3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD)

Airborne Food Water Particulate Or Fish Milk Products Sediments Analysis (pCi/1)

Gases (pCi/m3)

(pCi/kg, wet)

(pCi/I)

(pCi/kg, wet)

(pCi/kg,dry)

Gross Beta 4

0.01 H-3 2000 Mn-54 15 130 Fe-59 30 260 Co-58, 60 15 130 Zn-65 30 260 Zr-95 30 Nb-95 15 1-131 1 (a) 0.07 1

60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 60 La-140 15 15 (a) LLD for drinking water samples.

SUSQUEHANNA - UNIT 2 TRM / 3.11-43

Rev. 6 THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 2 TRM / 3.11-44 Monitoring Program 3.11.4.1

Rev. 3 3.11 RADIOACTIVE EFFLUENTS 3.11.4 Radiological Environmental Monitoring 3.11.4.2 Land Use Census TRO 3.11.4.2 A land use census shall be conducted.

APPLICABILITY:

At all times.

ACTIONS.

Land Use Census 3.11.4.2

NOTE----------------------------------------------------

The provisions of TRO 3.0.4 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A.

Land use census A.1 Identify the new location(s)

As defined by the identifies a location(s) in the next Radioactive Radioactive Effluent which yields a calculated Effluent Release Report.

Release Report dose or dqse commitment greater than the values currently being calculated in Requirement 3.11.2.3.

B.

Land use census 8.1 Add the new location(s) to the 30 days identifies a location(s) radiological environmental that yields a calculated monitoring program.

dose or dose commitment (via the AND same exposure pathway) 20 percent 8.2 Identify the new location(s)

As defined in greater than at a in the next Radioactive Radioactive Effluent location from which Effluent Release Report per Release Report samples are currently TS Section 5.6.

being obtained in accordance with Requirement 3.11.4.1.

SUSQUEHANNA - UNIT 2 TRM / 3.11-45

Rev. 3 TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE TRS 3.11.4.2.1 Conduct the land use census.

SUSQUEHANNA - UNIT 2 TRM / 3.11-46 Land Use Census 3.11.4.2 FREQUENCY 12 months

Rev. 2 lnterlaboratory Comparison Program 3.11.4.3 3.11 RADIOACTIVE EFFLUENTS 3.11.4 Radiological Environmental Monitoring 3.11.4.3 lnterlaboratory Comparison Program TRO 3.11.4.3 Analyses shall be performed on radioactive materials supplied as part of an lnterlaboratory Comparison Program.

APPLICABILITY:

At all times.

ACTIONS

NOTE-------------------------------------------------------------

The provisions of TRO 3.0.4 are not applicable.

CONDITION A.

Analyses not being performed.

REQUIRED ACTION A.1 Initiate a condition report.

TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE COMPLETION TIME In accordance with the Corrective Action Program FREQUENCY TRS 3.11.4.3.1 Include a summary of the results obtained as part of Annually the above required lnterlaboratory Comparison Program in the Annual Radiological Environmental Operating Report.

SUSQUEHANNA - UNIT 2 TRM / 3.11-47

Rev. 1 VENTING or PURGING 3.6.1 3.6 CONTAINMENT 3.6.1 VENTING or PURGING TRO 3.6.1 VENTING or PURGING of the primary containment shall be performed only with the following conditions established:

APPLICABILITY:

ACTIONS

1. Both Standby Gas Treatment Systems shall be OPERABLE in accordance with LCO 3.6.4.3 "Standby Gas Treatment (SGT) System" and whenever the purge system is in use during MODE 1, 2, or 3, only one of the SGT System trains may be used.

2. LCO 3.3.6.1 "Primary Containment Isolation Instrumentation" Function 2.e "SGTS Exhaust Radiation - High" shall be OPERABLE.

Whenever primary containment VENTING or PURGING is in progress.

CONDITION REQUIRED ACTION COMPLETION TIME A.

VENTING and A.1 PURGING requirements not met.

Suspend all VENTING and PURGING of the primary containment.

TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE Immediately FREQUENCY TRS 3.6.1.1 Verify that the requirements of TRO 3.6.1 "VENTING Within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and PURGING" are met.

prior to start SUSQUEHANNA - UNIT 2 TRM / 3.6-1 of VENTING or PURGING of the primary containment 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months

Rev.1 VENTING or PURGING 3.6.1 THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 2 TRM / 3.6-2

Rev. 1 3.6 CONTAINMENT Primary Containment Closed System Boundaries 3.6.4 3.6.4 Primary Containment Closed System Boundaries TRO 3.6.4 Primary Containment Closed System boundaries shall be OPERABLE.

APPLICABILITY:

When Primary Containment Isolation Valves (PCIVs) for lines in which the redundant isolation barrier is a closed system are required to be OPERABLE per LCO 3.6.1.3, "Primary Containment Isolation Valves

{PCIVs)."

NOTE--------------------------------------

Primary Containment Closed System boundaries may be unisolated intermittently under administrative controls.

ACTIONS

NOTES-----------------------------------------------------

1. Separate Condition entry is allowed for each Primary Containment Closed System.

2. Enter applicable Conditions and Required Actions for systems made inoperable by inoperable Primary Containment Closed System boundaries.

3. If Conditions and Required Actions for this TRO are not completed, LCO 3.0.3 shall be entered, not TRO 3.0.3.

4. Penetration flow paths may be unisolated intermittently under administrative controls.

5. Enter applicable Conditions and Required Actions of LCO 3.6.1.1, "Primary Containment,"

when Primary Containment Closed System boundary leakage results in exceeding overall containment leakage rate acceptance criteria in MODES 1, 2, and 3.

CONDITION A.

One or more penetration flow paths with its Primary Containment Closed System boundary inoperable and its corresponding PCIV(s) OPERABLE.

SUSQUEHANNA - UNIT 2 REQUIRED ACTION A.1.1 Isolate the affected portion of system piping from the rest of the closed system and primary containment by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

TRM / 3.6-7 COMPLETION TIME 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

Rev.1 ACTIONS (continued)

CONDITION A.

(continued)

A.1.2 OR A.2.1 A.2.2 B.

One or more 8.1 penetration flow paths with its Primary Containment Closed System boundary inoperable and its corresponding PCIV(s) inoperable.

OR B.2 C.

Required Action and C. 1 associated Completion Time of Condition A or B not met.

SUSQUEHANNA - UNIT 2 Primary Containment Clo*sed System Boundaries 3.6.4 REQUIRED ACTION COMPLETIOf)J TIME AND Verify the affected Once per 31 days portion of system piping is isolated from the rest of

'the closed system and primary containment.

Isolate the affected 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months penetration(s) by use of the closed and de-activated PCIV.

AND Verify the affected Once per 31 days penetration flow path is isolated.

Isolate the affected 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months penetration flow path by use of at least one closed and de-activated automatic valve, closed manual valve, or blind flange.

Immediately Enter the applicable Conditions and Required Actions of LCO 3.6.1.1 for a loss of Primary Containment.

Enter LCO 3.6.1.3 Immediately Condition G based on the unit MODE.

TRM / 3.6-8

Rev.1 Primary Containment Closed System Boundaries 3.6.4 TECHNICAL REQUIREMENT SURVEILLANCE i I.

I TRS 3.6.4.1 TRS 3.6.4.2 SURVEILLANCE FREQUENCY Verify Primary Containment Closed System boundary 92 days is intact.

Verify Primary Containment Closed System integrity.

In accordance with the Leakage Rate Test Program SUSQUEHANNA - UNIT 2 TRM /3.6-9

Rev. 1 Ultimate Heat Sink (UHS) and Ground Water Level 3.7.2 3.7 3.7.2 PLANT SYSTEMS Ultimate Heat Sink (UHS) and Ground Water Level TRO 3.7.2 The UHS shall be FUNCTIONAL and Ground Water shall be less than 663 feet Mean Sea Level (MSL)

NOTE--------------

The UHS requirement is applicable in all MODES except MODES 1, 2, and 3 (See LCO 3. 7.1, "RHRSW System and UHS"). The Ground Water requirement is applicable in all MODES as required by supported systems.

APPLICABILITY:

As required by supported systems ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Groundwater level at A.1

Initiate a condition report.

In accordance with the any spray pond area Corrective Action observation well Program greater than or equal to 663 feet MSL.

B.

The UHS is otherwise 8.1.1 Evaluate OPERABILITY/

Immediately nonfunctional.

FUNCTIONALITY of supported systems.

AND 8.1.2 Declare supported systems Immediately inoperable/nonfunctional, as applicable.

SUSQUEHANNA - UNIT 2 TRM / 3.7-3

Rev. 1 Ultimate Heat Sink (UHS) and Ground Water Level 3.7.2 TECHNICAL REQUIREMENT SURVEILLANCE TRS 3.7.2.1 TRS 3.7.2.2 SURVEILLANCE Ensure TS Surveillance Requirements (SR) 3.7.1.1 and 3.7.1.2 are met.

Verify that the Ground Water Level at any spray pond area is less than 663 feet MSL.

SUSQUEHANNA - UNIT 2 TRM / 3.7-3a FREQUENCY As required by LCO 3.7.1 184 days

Rev.2 3.7 PLANT SYSTEMS 3.7.4 Solid Radwaste System Solid Radwaste System 3.7.4 TRO 3.7.4 A solid radwaste system shall be used in accordance with a PROCESS CONTROL PROGRAM, for the processing and packaging of radioactive wastes.

APPLICABILITY:

At all times ACTIONS

NO TE -------------------------------------------

The provisions of TRO 3.0.4 are not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A.

The requirements of A.1 Suspend shipments of Immediately 10 CFR 20.1301, and/or defectively processed or 10 CFR 71 are not met.

defectively packaged solid radwaste from the site.

B.

Solid radwaste system B.1 Restore solid radwaste 31 days nonfunctional.

system to FUNCTIONAL status.

C.

Required Action and C.1 Initiate a condition report.

In accordance with the associated Completion Corrective Action Time of Condition B not Program met.

SUSQUEHANNA - UNIT 2

TRM / 3.7-34

Rev.2 Solid Radwaste System 3.7.4

_A_CT_I_O_N_S __________________ ~-------

CONDITION REQUIRED ACTION COMPLETION TIME D.

Test specimen from a D.1 Suspend the Immediately batch of waste to be SOLIDIFICATION of the batch solidified fails to verify under test until such time as SOLIDIFICATION.

additional test specimens can be obtained, alternative SOLIDIFICATION parameters can be determined in accordance with the PROCESS CONTROL PROGRAM, and a subsequent test verifies SOLIDIFICATION.

Solidification of the batch may then be restored using the alternative SOLIDIFICATION parameters determined by the PROCESS CONTROL PROGRAM.

AND D.2 Collect and test representative 3 consecutive initial test specimens from each test specimens subsequent batch of the same demonstrate type of wet waste.

SOLIDIFICATION AND D.3 Modify the PROCESS As required CONTROL PROGRAM as required to assure SOLIDIFICATION of subsequent batches of waste.

SUSQUEHANNA - UNIT 2 TRM / 3.7-35

Rev. 2 TECHNICAL REQUIREMENT SURVEILLANCE TRS 3.7.4.1 TRS 3.7.4.2 SURVEILLANCE Demonstrate the solid radwaste system FUNCTIONAL.

OR Verify the existence *of a valid contract for processing to be performed by a contractor in accordance with a PROCESS CONTROL PROGRAM.

Verify the solidification of at least one representative test specimen.

SUSQUEHANNA - UNIT 2

TRM / 3.7-36 Solid Radwaste System 3.7.4 FREQUENCY 92 days Every tenth batch of each type of wet radwaste

Rev. 2 3.8 ELECTRICAL POWER 24 voe Electrical Power Subsystem 3.8.4 3.8.4 24 VDC Electrical Power Subsystem TRO 3.8.4 Two 24 VDC electrical power subsystems shall be FUNCTIONAL.

APPLICABILITY:

When supported systems are required to be OPERABLE or FUNCTIONAL, as applicable.

ACTIONS

__________, _____ NOTE--------------------------

Separate condition entry is allowed for each parameter and subsystem.

CONDITION REQUIRED ACTION COMPLETION TIME A

One or more batteries A.1 Verify pilot cell electrolyte 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months with one or more battery level and float voltage meet cell parameters not Table 3.8.4-1 Category C within Category A or B limits.

limits.

AND A.2 Verify battery cell parameters 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months meet Table 3.8.4-1 Category C limits.

AND Once Per 7 days thereafter AND A.3 Restore battery cell 31 days parameters to Table 3.8.4-1 Category A and B limits.

SUSQUEHANNA - UNIT 2 TRM / 3.8-15

Rev.2 ACTIONS CONDITION B.

Required Actions and associated Completion Times of Condition A not met.

OR One or more batteries with one or more battery cell parameters not within Category C limits.

OR One or more batteries with average electrolyte temperature of the representative cells not within limits.

C.

One or both 24 voe battery banks nonfunctional or deenergized for any reason.

SUSQUEHANNA - UNIT 2 8.1 C.1.1 C.1.2.

24 VDC Electrical Power Subsystem 3.8.4 REQUIRED ACTION COMPLETION TIME Declare associated battery Immediately nonfunctional.

Evaluate OPERABILITY/

Immediately FUNCTIONALITY of supported systems.

AND Declare supported systems Immediately inoperable / nonfunctional, as applicable.

TRM / 3.8-16

Rev. 2 24 VDC Electrical Power Subsystem 3.8.4 TECHNICAL REQUIREMENT SURVEILLANCE SURVEILLANCE FREQUENCY TRS 3.8.4.1 Verify battery terminal voltages when on float charge 7 days are 2 26V.

TRS 3.8.4.2 Verify battery cell parameters meet Table 3.8.4-1 7 days Category A limits.

TRS 3.8.4.3 Verify battery cell parameters meet Table 3.8.4-1 92 days Category B limits.

AND AND Once within 7 days Verify for each battery terminal and connector:

after battery discharge < 22V

a. No visible corrosion, or AND

b.

Battery terminal and connection resistance

< 150.0E-6 ohms.

Once within 7 days after battery overcharge > 30V TRS 3.8.4.4 Verify average electrolyte temperature of 92 days representative cells is 2 60°F for each Class 1 E 24V battery.

TRS 3.8.4.5 Verify battery cells, cell plates, and racks show no 18 months visual indication of physical damage or abnormal deterioration that could potentially degrade battery performance.

TRS 3.8.4.6 Remove visible corrosion and verify battery cell to 18 months cell and terminal connections are tight and coated with anti-corrosion material.

TRS 3.8.4.7 Verify each required battery charger supplies its 24 months

.associated battery for 2 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months at 2 25 amperes at 2 25.7 volts.

SUSQUEHANNA - UNIT 2 TRM / 3.8-17

Rev.2 24 VDC Electrical Power Subsystem 3.8.4 TECHNICAL REQUIREMENT SURVEI.LLANCE SURVEILLANCE FREQUENCY TRS 3.8.4.8 TRS 3.8.4.9

NOTE---------------

The performance discharge test in TRS 3.8.4.9 may be performed in lieu of the service test in TRS 3.8.4.8 once per 60 months.

Verify battery capacity is adequate to supply, and maintain in FUNCTIONAL status, the actual emergency loads for the design duty cycle when subjected to a battery service test.

24 months Verify battery capacity is ~ 80% of the manufacturer's 60 months rating when subjected to a performance discharge test or a modified performance discharge test.

AND 12 months when battery shows degradation or has reached 85% of expected service life with capacity

< 100% of manufacturer's rating AND 24 months when battery has reached 85% of expected service life with capacity

~ 100% of manufacturer's rating SUSQUEHANNA - UNIT 2 TRM / 3.8-18

24 VDC Electrical Power Subsystem Rev.2 3.8.4 TABLE 3.8.4-1 BATTERY CELL PARAMETER REQUIREMENTS CATEGORYC:

CATEGORY A:

CATEGORY B:

ALLOWABLE LIMITS LIMITS FOR EACH LIMITS FOR EACH FOR EACH PARAMETER DESIGNATED PILOT CELL CONNECTED CELL CONNECTED CELL Electrolyte Level

> Minimum level indication

> Minimum level Above top of plates mark, ::;; 1/4 inch above indication mark, and not overflowing maximum level indication and ::;; 1/4 inch above mark<a) maximum level indication mark<a)

Float Voltage

c: 2.13V

c:2.13V

> 2.07V Specific GravityCbJ(c)

c: 1.200

?:: 1.195 Not more than 0.020 AND below average of all connected cells Average of all AND connected cells

> 1.205 Average of all connected cells

c: 1.195 Cal It is acceptable for the electrolyte level to temporarily increase above the specified maximum level during and immediately following equalizing charges provided it is not overflowing.

(bl Corrected for electrolyte temperature. Level correction is not required.

(cl A battery charging current of less than 0.01 amp when on float change is acceptable for meeting specific gravity limits.

SUSQUEHANNA - UNIT 2

TRM / 3.8-19

I Rev. 2 24 VDC Electrical Power Subsystem 3.8.4 THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 2 TRM / 3.8-20

Rev. 2 4.0 ADMINISTRATIVE CONTROLS 4.5 Reporting Requirements 4.5.1 4.5.2 4.5.3 Not used Not used Not used SUSQUEHANNA - UNIT 2 TRM / 4.0-5 Reporting Requirements 4.5

Rev.2 Reporting Requirements 4.5 THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 2 TRM / 4.0-6

Rev. 1 Sealed Source Contamination B 3.10.1 B 3.10.1 Sealed Source Contamination BASES TRO ACTIONS TRS REFERENCES The limitations on removable contamination for sources required leak testing, including alpha emitters, is based on 10 CFR 70.39(c) limits for plutonium (Reference 1). This limitation will ensure that leakage from byproduct, source, and special nuclear material sources will not exceed allowable intake values. Sealed sources are classified into three groups according to their use, with surveillance requirements commensurate with the probability of damage to a source in that group (i.e., sources in use, sources not in use, and sources used for startup). Those sources frequently handled are required to be tested more often than those which are not. Sealed sources that are continuously enclosed within a shielded mechanism, i.e., sealed sources within radiation monitoring or boron measuring devices, are considered to be stored and need not be tested unless they are removed from the shielded mechanism.

The Actions are defined to ensure proper corrective measures are taken in response to the identified Condition.

For Required Action A.3, a condition report must be initiated and processed in accordance with station reporting and Corrective Action Program procedures (Reference 2).

The TRSs are defined to be performed at the specified Frequency to ensure that the requirements are maintained.

Tests for leakage and/or contamination shall be performed by:

a.

The licensee, or

b.

Other persons specifically authorized by the Commission or an Agreement State.

The test method shall have a detection sensitivity of at least 0.005 microcurie per test sample.

1.

1 O CFR 70.39.

2.

Technical Specification Section 5.6.2 - Annual Radiological Environmental Operating Report.

SUSQUEHANNA - UNIT 2 TRM / B 3.10-1

Rev. 2 Liquid Effluents Concentration B 3.11.1.1 B 3.11.1.1 Liquid Effluents Concentration BASES TRO ACTIONS TRS This requirement is provided to ensure that the concentration of radioactive materials released in liquid waste effluents to UNRESTRICTED AREAS will be less than 10 times the concentration levels specified in 1 O CFR Part 20.1001 to 20.2402, Appendix B, Table 2, Column 2. The requirement provides operational flexibility for releasing liquid effluents in concentrations to follow the Section II.A and I1.C design objectives of Appendix I to 1 O CFR part 50. This limitation provides reasonable assurance that the levels of radioactive materials in bodies of water in UNRESTRICTED AREAS will result in exposures within (1) the Section II.A design objectives of Appendix I, 10 CFR 50, to a Member of the Public and (2) restrictions authorized by 10 CFR 20.1301 (e). The concentration limit for dissolved or entrained noble gases is based upon the assumptions that Xe-135 is the controlling radionuclide and its effluent concentration in air (submersion) was converted to an equivalent concentration in water. This requirement does not affect the requirement to comply with the annual limitations of 10 CFR 20.1301 (a).. This requirement applies to the release of radioactive materials in liquid effluents from all units at the site. The required detection capabilities for radioactive materials in liquid waste samples are tabulated in terms of the lower limits of detection (LLDs). Detailed discussion of the LLD and the other detection limits can be found in Curie, L.A., "Lower Limit of Detection: Definition and Elaboration of a Proposed Position for Radiological Effluent and Environmental Measurements." (References*2, 3, and 4)

This section of the TRM is also part of the ODCM (Reference 2).

The Actions are defined to ensure proper corrective measures are taken in response to exceeding the TRO limits.

The TRSs are defined to be performed at the specified Frequency to ensure that the parameters are maintained within the TRO limits.

Table 3.11.1.1-1 defines Radioactive Liquid Waste Sampling and Analysis Program. The lower limit of detection (LLD) is defined, for purposes of these Requirements, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only 5%

SUSQUEHANNA - UNIT 2 TRM / B 3.11-1

Rev.2 BASES TRS (continued)

Liquid Effluents Concentration B 3.11.1.1 probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation:

LLD= ____

4_.6_6_s_b ___ _

E

V

2.22E6

Y

exp(-1.M)

Where:

LLD is the a priori lower limit of detection as defined above (as microcuries per unit mass or volume).

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency, as counts per disintegration, V is the sample size, in units of mass or volume, 2.22 E6 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable.

A is the radioactive decay constant for the particular radionuclide, and lit for plant effluents is the elapsed time between the midpoint of sample collection and time of counting.

Typical values of E, V, Y, and 1'J..t should be used in the calculation.

It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

A batch release is the discharge of liquid wastes of a discrete volume.

Prior to sampling for analyses, each batch shall be isolated, and then thoroughly mixed to assure representative sampling.

The principal gamma emitters for which the LLD specification applies include the following radionuclides: Mn-54; Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144. The dissolved and entrained gases (gamma emitters) for which the LLD specification applies include the following radionuclides: Kr-85, Kr-85m. Kr-87, Kr-88, Ar-41, Xe-133, Xe-133m, Xe-135, and Xe-135m. This list does not mean that only these nuclides are to be considered. Other gamma peaks that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in accordance with the ODCM.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-2

Rev.2 BASES TRS (continued)

REFERENCES Liquid Effluents Concentration B 3.11.1.1 A composite sample is one in which the quantity of liquid sampled is proportional to the quantity of liquid waste discharged and in which the method of sampling employed results in a specimen that is representative of the liquids releiased over a period no longer than the Minimum Analysis Frequency.

The Minimum Analysis Frequency as listed for the Composite Samples shall mean the minimum frequency for initiation of the required analyses, not completion of the analyses and evaluation of the results. Since the analysis involves sending the samples to an offsite laboratory and performance of involved sample preparation and wet chemical analyses, there will be a delay between initiation of the analysis and receipt of the results.

The analysis initiation shall normally be done on a calendar month for the 31-day frequency or calendar quarter for a 92-day frequency.

1. Technical Specification 5.5.4 - Radioactive Effluent Controls program.

2. Technical Specification 5.5.1 - Offsite Dose Calculation Manual.

3. NUREG/CR-4007, September, 1984.

4. 10 CFR Part 20.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-3

Rev. 1 Liquid Effluents Dose B 3.11.1.2 B 3.11.1.2 Liquid Effluents Dose BASES TRO.

ACTIONS TRS This requirement is provided to implement the requirements of Sections II.A, Ill.A and IV.A of Appendix I, 10 CFR 50. The Technical Requirement for Operation implements the guides set forth in Section II.A of Appendix I. Also, for fresh water sites with drinking water supplies which can be potentially affected by plant operations, there is reasonable assurance that the operation of the facility will not result in radionuclide concentrations in the finished drinking water that are in excess of the requirements of 40 CFR 141. The dose calculation methodology and parameters in the ODCM implement the requirements in Section Ill.A of Appendix I. The equations specified in the ODCM for calculating the doses due to the actual release rates of radioactive materials in liquid effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Dose*s to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977 (References 2, 3, 4, and 5).

This section of the TRM is also part of the ODCM (Reference 2).

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in liquid effluents will be kept "as low as is reasonably achievable."

If the calculated dose from the release of radioactive materials in liquid effluents exceeds any of the limits established in TRO 3.11.1.2, a condition report shall be initiated and processed in accordance with station reporting and Corrective Action Program procedures (Reference 6).

The TRSs are defined to be performed at the specified Frequency to ensure that the TRO limits are maintained.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-4

Rev. 1 BASES REFERENCES Liquid Effluents Dose B 3.11.1.2

1.

Technical Specification 5.5.4 - Radioactive Effluent Controls program.

2.

Technical Specification 5.5.1 - Offsite Dose Calculation Manual.

3.

10 CFR 20.

4.

Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977.

5.

Regulatory Guide 1.113, "Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementing Appendix I," April 1977.

6.

NUREG-1302, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors, Generic Letter 89-01, Supplement No. 1.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-5

Rev. 1 Liquid Radwaste Treatment System B 3.11.1.3 B 3.11.1.3 Liquid Radwaste Treatment System BASES TRO ACTIONS TRS REFERENCES The FUNCTIONALITY of the Liquid Radwaste (LRW) Treatment System ensures that this system will be available for use whenever liquid effluents require treatment prior to release to the environment. The requirement that the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept "as low as is reasonably achievable". This Requirement implements the requirements of 1 O CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR 50 and the design objective given in Section I1.D of Appendix I to 10 CFR 50. The specified limits governing the use of appropriate portions of the LRW Treatment System were specified as a suitable fraction of the dose design objectives set forth in Section II.A of Appendix I, 10 CFR 50, for liquid effluents (Reference 3).

This section of the TRM is also part of the ODCM (Reference 2).

The Actions are defined to ensure proper corrective measures are taken in response to the nonfunctional components.

If liquid effluent releases are being discharged without treatment and in excess of the TRO limit, a condition report shall be initiated and processed in accordance with station reporting and Corrective Action Program procedures (Reference 4).

The TRSs are defined to be performed at the specified Frequency to ensure that the system is maintained FUNCTIONAL. FUNCTIONALITY is demonstrated by operating the LRW Treatment System equipment for at least 10 minutes.

1. Technical Specification 5.5.4 - Radioactive Effluent Controls program.

2. Technical Specification 5.5.1 - ODCM.

3. 10 CFR 50, Appendix I.

4. NUREG-1302, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors, Generic Letter 89-01, Supplement No. 1.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-6

Rev. 1 Liquid Radwaste Effluent Monitoring Instrumentation B 3.11.1.4

B 3.11.1.4 Liquid Radwaste Effluent Monitoring Instrumentation BASES TRO The radioactive liquid effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM (Reference 2) to ensure that the alarm/trip will occur prior to exceeding the 1 O times the

concentration values specified in Appendix 8, Table 2, Column 2 of 10 CFR 20.1001 - 10 CFR 20.2401 (Reference 2). The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR 50 (Reference 4).

FUNCTIONALITY of the radiation monitoring instrumentation requires their alarm/trip setpoints set to ensure that the limits of TRO 3.11.1.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the methodology and parameters described in the ODCM.

FUNCTIONALITY of the Liquid Radwaste Effluent Line gross radioactivity monitor includes the proper functioning of the discharge valve interlocks (sample pump low flow, high radiation alarm*, and radiation monitor

failure).

FUNCTIONALITY of the Cooling Tower Slowdown flow rate measurement device includes the proper functioning of the Liquid Radwaste Effluent Line discharge valve interlock (i.e., cooling tower blowdown low flow).

The Required Channels for each function in Table 3.11.1.4-1 are as follows:

-a.

Liquid Radwaste Effluent rad monitor (Function 1.a) one instrument per station.

b.

Liquid Radwaste Effluent flow rate (Function 2.a) one instrument per station.

c.

Cooling Tower Slowdown flow rate (Function 2.b) one instrument per station.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-7

Rev. 1 BASES TRO (continued)

ACTIONS TRS Liquid Radwaste Effluent Monitoring Instrumentation B 3.11.1.4 It should be noted that the radioactive liquid waste stream is diluted in the Cooling Tower blowdown line prior to entering the Susquehanna River.

The setpoint for this dilution water flow is 5000 gpm from the combination of the Unit 1 blowdown, Unit 2 blowdown flow, and Spray Pond Discharge.

Options exist to ensure the requirement of one FUNCTIONAL Cooling Tower Slowdown flow Instrument per station is met as required by Table 3.11.1.4-1, Function 2.b. As long as any one of three instruments (Unit 1 Tower, Unit 2 Tower, Total Site Slowdown) are FUNCTIONAL and alignment of HS-06443A and HSS-01503 on panel 0C301 is such that the FUNCTIONAL instrument(s) are in the circuit, then the TRM Requirement is met.

This section of the TRM is also part of the ODCM (Reference 2).

The Actions are defined to ensure proper corrective measures are taken in response to the nonfunctional components.

Pump curves generated in situ may be used to estimate flow for Required Action 0.1.

For Required Action F.2, a condition report shall be initiated and processed in accordance with station reporting and Corrective Action Program procedures (Reference 5). -_

The TRSs are defined to be performed at the specified Frequency to ensure that the monitoring instrumentation is maintained FUNCTIONAL.

The TRSs shall be performed in accordance with the TRM definition for the test with the following additional requirements:

The Liquid Radwa~te Effluent Line radiation monitor CHANNEL FUNCTIONAL TEST shall also demonstrate that automatic isolation of this pathway and control room alarm annunciation occur if any of the following conditions exist:

1.

Instrument indicates measured levels above the alarm/trip setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-8

Rev. 1 BASES TRS (continued)

REFERENCES Liquid Radwaste Effluent Monitoring Instrumentation B 3.11.1.4 The liquid Radwaste Effluent Line radiation monitor initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration may be used in lieu of the reference standards associated with the initial calibration.

The Liquid Radwaste Effluent Line flow rate monitor and Cooling Tower Slowdown flow rate monitor CHANNEL CHECK shall consist of verifying indication of flow during periods of release. CHANNEL CHECK shall be made at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months on days on which continuous, periodic, or batch releases are made.

1.

Technical Specification 5.5.4 - Radioactive Effluent Controls program.

2.

Technical Specification 5.5.1 - Offsite Dose Calcul~tion Manual.

3.

10 CFR 20.

4.

10 CFR 50.

5.

Technical Specification 5.6.3 - Radioactive Effluent Release Report.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-9

Rev. 1 Radioactive Liquid Process Monitoring Instrumentation B 3.11.1.5 B 3.11.1.5 Radioactive Liquid Process Monitoring Instrumentation BASES TRO ACTIONS The radioactive liquid process instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in liquid effluents during actual or potential releases of liquid effluents. The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM (Reference 2) to ensure that the alarm/trip will occur prior to exceeding 10 times the concentration values specified in Appendix B, Table 2, Column 2 of 1 0 CFR 20.1001 -

20.2401 (Reference 3). The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR 50 (Reference 4).

This section of the TRM is also part of the ODCM (Reference 2).

The Actions are defined to ensure proper corrective measures are taken in response to the nonfunctional components.

C.1 If the Required Actions and associated Completion Times for Condition B are not met, a condition report shall be initiated and processed in accordance with station reporting and Corrective Action Program procedures (Reference 5).

D.1 If an RHR heat exchanger and its applicable RHRSW loop are in service there is a pathway from the heat exchanger to the spray pond. If the heat exchanger and RHRSW loop are not in service (i.e., valved-out, RHRSW pump not running, or piping drained) then a pathway does not exist.

If there is no pathway, the requirement to perform grab sampling is not applicable when the RHR Service Water System Effluent Line Radiation Monitor has been declared nonfunctional.

The function of pumping down the RHR heat exchanger and RHRSW system piping to the Spray Pond provides a pathway for a release of potentially radioactively contaminated water. The RHRSW system is considered an 80-10 system because a pathway to the environment from this system exists through the Spray Pond and because the system, although normally not radioactively contaminated, has the potential for becoming radioactively contaminated in the event that a leak develops across an RHR heat exchanger. Therefore, grab samples must be collected periodically when the RHRSW system radiation monitor for a SUSQUEHANNA - UNIT 2 TRM / B 3.11-10

Rev. 1 BASES ACTIONS (continued)

TRS D.1 (continued)

Radioactive Liquid Process Monitoring Instrumentation B 3.11.1.5 particular loop is nonfunctional (malfunctioning) and water from that loop of the system is being returned to the Spray Pond. Also, grab samples must be collected prior to operations in which water from the RHRSW system will be drained to the Spray Pond.

The TRSs are defined to be performed at the specified Frequency to ensure that the monitoring instrumentation is maintained FUNCTIONAL.

Performance of the CHANNEL CHECK ensures that a gross failure of the instrument has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel against a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious. A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrument continues to operate properly between each CHANNEL CALIBRATION.

Agreement criteria, which are developed by the plant staff based on an investigation of a combination of the channel instrument uncertainties, may be used to support this parameter comparison and include indication and readability. If a channel is outside the criteria, it may be an indication

~hat the instrument has drifted outside its limit and does not necessarily indicate the channel is nonfunctional.

The TRSs shall be performed in accordance with the Technical Specification definition for the test with the following additional requirements:

The CHANNEL FUNCTIONAL TEST shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1.

Instrument indicates measured levels above the alarm setpoint.

2.

Circuit failure.

3.

Instrument indicates a downscale failure, and

4.

Instrument controls not set in operate mode.

SUSQUEHANNA - UNIT 2 TRM/B3.11-11

Rev. 1 BASES TRS (continued)

REFERENCES Radioactive Liquid Process Monitoring Instrumentation B 3.11.1.5 The initial CHANNEL CALIBRATION shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and measurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration may be used in lieu of the reference standards associated with the initial calibration.

1.

Technical Specification 5.5.4 - Radioactive Effluent Controls program.

2.

Technical Specification 5.5.1 - Offsite Dose Calculation Manual.

3.

10 CFR 20.

4.

10 CFR 50.

5.

Technical Specification 5.6.3 - Radioactive Effluent Release Report.

SUSQUEHANNA - UNIT 2 TRM/B3.11-11a

. Rev. 2 Dose Rate B 3.11.2.1 B 3.11.2.1 Dose Rate BASES TRO ACTIONS TRS This requirement provides reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a Member of the Public either within or outside the Site Boundary, in excess of the design objectives of Appendix I to 1 0CFR50. It provides operational flexibility for releasing gaseous effluents while satisfying Section I1.B and I1.C design objectives of Appendix I. For individuals who may at times be within the Site Boundary, the occupancy of the individual will. usually be sufficiently low to compensate for any increase in atmospheric diffusion factor above that for the Site Boundary. The specified release rate limits restrict, at all times, the corresponding dose rates above background to a Member of the Public at or beyond the Site Boundary to less than or equal to 500 mrem/yr to the total body or to less than or equal to 3000 mrem/yr to the skin. These release rate limits also restrict, at all times, the corresponding thyroid dose rate above background to an individual via the inhalation pathway to less than or equal to 1500 mrem/yr. These limits provide reasonable assurance that radioactive material discharged in gaseous effluents will not result in the exposure of a MEMBER OF THE PUBLIC either within or outside the SITE BOUNDARY, to annual average concentrations exceeding the limits specified in Appendix B, Table II of 1 0 CFR Part 20. (Reference 3)

This Requirement applies to the release of gaseous effluents from all reactors at the site.

This section of the TRM is also part of the ODCM (Reference 2).

The Actions are defined to ensure proper corrective measures are taken in response to the limits being exceeded.

The TRSs are defined to be performed at the specified Frequency to ensure that the dose rates are maintained within limits. Dose rates are determined in accordance with the methodology and parameters of the ODCM.

SUSQUEHANNA - UNIT 2 TRM/B3.11-12

Rev.2 BASES TRS (continued)

Dose Rate B 3.11.2.1 Table 3.11.2.1-1 defines Radioactive Gaseous Waste Sampling and Analysis Program. The lower limit of detection {LLD) is defined, for purposes of these requirement, as the smallest concentration of radioactive material in a sample that will yield a net count, aqove system background, that will be detected with 95% probability with only 5%

probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system, which may include radiochemical separation:

LLD=

4.66Sb E

V

2.22E6

Y

exp(-A~t)

Where:

LLD is the a priori lower limit of detection as defined above (as microcuries per unit mass or volume),

Sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency, as counts per disintegration, V is the sample size, in units of mass or volume, 2.22 E6 is the number of disintegrations per minute per microcurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and M for plant effluents is the elapsed time between the midpoint of sample collection and time of counting (for plant effluents, not environmental samples).

The value of Sb used in the calculation of the LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance. Typical values of E, V, Y, and ~t shall be used in the calculation.

The principal gamma emitters for which the LLD specification applies include the following radionuclides: Kr-87, Kr-88, Xe-133, Xe-133m, Xe-135, Xe-135m and Xe-138 for gaseous emissions and Mn-54, Fe-59, Co-58, Co-60, Zn-65, Mo-99, Cs-134, Cs-137, Ce-141 and Ce-144 for particulate emissions. This list does not mean that only these nuclides are to be considered. Other gamma peaks which are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Radioactive Effluent Release Report.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-13

Rev. 2 BASES TRS (continued)

REFERENCES Dose Rate B 3.11.2.1 The design of the systems for the sampling of particulates and iodines uses constant flow rate sampling. Gaseous particulate and iodine samples are gathered continuously, with the sample size proportional to the stack emissions; a composite gaseous sample is a combination of all the particulate filters gathered in a sampling period.

Particulate or iodine sampling required to be in continuous service will be considered to remain and have been in continuous service when its service is interrupted for a time period not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per sampling period. For particulate and iodine sampling, this is a small fraction of the normal minimum analysis frequency.

The minimum Analysis Frequency as listed for the Composite Samples shall mean the minimum frequency for initiation of the required analyses, not completion of the analysis and evaluation of the results. Since the analysis involves sending the samples to an offsite laboratory and performance of involved sample preparation and wet chemical analyses, there will be a delay between initiation of the analysis and receipt of the results. The analysis initiation shall normally be done on a calendar quarter for a 92 day frequency.

1. Technical Specification 5.5.4 - Radioactive Effluent Controls Program.

2. Technical Specification 5.5.1 - Offsite Dose Calculation Manual.

3. 1 0CFR Part 20.

4. FSAR Section 11.5.2.1.

SUSQUEHANNA - UNIT 2 TRM/83.11-14

Rev.2 BASES THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 1 TRM / B 3.11-15 Dose Rate 8 3.11.2.1

Rev. 1 Dose - Noble Gases B 3.11.2.2 B 3.11.2.2 Dose - Noble Gases BASES TRO.

ACTIONS TRS This requirement is provided to implement the requirements of Sections I1.B, Ill.A and IV.A of Appendix I, 10 CFR 50 (Reference 5). The Technical Requirement for Operation implements the guides set forth in Section I1.B of Appendix I.

This section of the TRM is also part of the ODCM (Reference 2).

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive material in gaseous effluents will be kept "as low as is reasonably achievable".

A.1 If the calculated air dose exceeds the limits specified in TRO 3.11.2.2, a condition report shall be initiated and processed in accordance with station reporting and Corrective Action Program procedures (Reference 6).

The TRSs implement the requirements in Section Ill.A of Appendix I. The dose calculation established in the ODCM for calculating the doses due to the actual release rates of radioactive noble gases in gaseous effluents are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, " Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The ODCM equations provided for determining the air doses at and beyond the SITE BOUNDARY are based upon the historical average atmospheric conditions (References 2, 3 and 4).

SUSQUEHANNA - UNIT 2 TRM / B 3.11-16

Rev. 1 BASES REFERENCES Dose - Noble Gases 8 3.11.2.2

1.

Technical Specification 5.5.4 - Radioactive Effluent Controls program.

2.

Technical Specification 5.5.1 - Offsite Dose Calculation Manual.

3.

Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 1 O CFR Part 50, Appendix I", Revision 1, October 1977.

4.

Regulatory Guide 1.111, "Methods for estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977.

5.

10 CFR 50, Appendix I.

6.

NUREG-1302, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors, Generic Letter 89-01, Supplement No. 1.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-17

Rev. 1 Dose - Iodine, Tritium, and Radionuclides in Particulates Form B 3.11.2.3 B 3.11.2.3 Dose - Iodine, Tritium, and Radionuclides in Particulates Form BASES TRO ACTIONS TRS This requirement is provided to implement the requirements of Sections I1.C, Ill.A and IV.A of Appendix I, 10 CFR 50. The Technical Requirements for Operation are the guides set forth in Section I1.C of Appendix I (Reference 5).

This section of the TRM is also part of the ODCM (Reference 2).

The ACTION statements provide the required operating flexibility and at the same time implement the guides set forth in Section IV.A of Appendix I to assure that the releases of radioactive materials in gaseous effluents will be kept" as low as is reasonably achievable."

If the calculated dose from the release exceeds the limits specified in TRO 3.11.2.3, a condition report shall be initiated and processed in accordance with station reporting and Corrective Action Program procedures (Reference 6).

The TRSs are defined to be performed at the specified Frequency to ensure that the TRO limits are maintained.

The ODCM calculational methods specified in the TRSs implement the requirements in Section Ill.A of Appendix I that conformance with the guides of Appendix I be shown by calculational procedures based on models and data, such that the actual exposure of a MEMBER OF THE PUBLIC through appropriate pathways is unlikely to be substantially underestimated. The ODCM calculational methods for calculating the doses due to the actual release rates of the subject materials are consistent with the methodology provided in Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate Requirements for iodine-131, iodine-133, tritium, and radionuclides in particulate form with half lives greater than 8 days are dependent on the existing radionuclide pathways to man in areas at and beyond the SITE BOUNDARY. The pathways SUSQUEHANNA - UNIT 2 TRM / B 3.11-18

Rev. 1 BASES TRS (continued)

REFERENCES Dose - Iodine, Tritium, and Radionuclides in Particulates Form B 3.11.2.3 which were examined in the development of these calculations were: 1) individual inhalation of airborne radionuclides, 2) deposition of radionuclides onto green leafy vegetation with subsequent consumption by man, 3) deposition onto grassy areas where milk animals and meat producing animals graze with consumption of the milk and meat by man, and 4) deposition on the ground with subsequent exposure of man (References 2, 3 and 4).

1.

Technical Specification 5.5.4 - Radioactive Effluent Controls program.

2.

Technical Specification 5.5.1 - Offsite Dose Calculation Manual.

3.

Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977.

4.

Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.

5.

10 CFR 50, Appendix I.

6.

NUREG-1302, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors, Generic Letter 89-01, Supplemerit No. 1.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-19

Rev. 1 Gaseous Radwaste Treatment System B 3.11.2.4 B 3.11.2.4 Gaseous Radwaste Treatment System BASES TRO ACTIONS This TRO ensures that the GASEOUS RADWASTE TREATMENT SYSTEM is FUNCTIONAL and in operation to reduce radioactive materials in gaseous waste prior to discharge when the main condenser air ejector (evacuation) system is in operation. This requirement provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "a~ low as is reasonably achievable". This TRO implements the requirements of 10 CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR 50, and the design objectives given in Section I1.D of Appendix I to 10 CFR 50. The limits governing the use of the system were specified as a suitable fraction of the dose design objectives set forth in Sections I1.B and I1.C of Appendix I, 10 CFR 50, for gaseous effluents (Reference 1 ).

This section of the TRM is part of the ODCM (Reference 2) and implements the requirements of the Radiological Effluent Controls Program (Reference 3).

The ACTIONS are defined to ensure proper corrective measures are taken in response to the inoperable components.

A.1 With the GASEOUS RADWASTE TREATMENT SYSTEM nonfunctional, action must be taken to restore it to FUNCTIONAL status in order to maintain radioactive releases from the main condenser as low as reasonably achievable, and in compliance with regulatory requirements.

The 7-day Completion Time is reasonable to perform repairs and to maintain radioactive release objectives.

8.1 If the Required Action and Completion Time of Condition A are not met, a condition report shall be initiated and processed in accordance with station reporting and Corrective Action Program procedures (Reference 4).

SUSQUEHANNA - UNIT 2 TRM / B 3.11-20

Rev. 1 BASES TRS REFERENCES Gaseous Radwaste Treatment System B 3.11.2.4 The TRSs are performed at the specified Frequency to ensure that the GASEOUS RADWASTE TREATMENT SYSTEM is maintained FUNCTIONAL TRS 3.11.2.4.1 This surveillance, requires verification that the GASEOUS RADWASTE TREATMENT SYSTEM is in operation when the main condenser air ejector (evacuation) system is in operation. The Frequency of 92 days is appropriate considering the performance of monthly dose projections.

1.

10 CFR 50.

2.

Technical Specification 5.5.1 - Offsite Dose Calculation Manual.

3.

Technical Specification 5.5.4 - Radioactive Effluent Controls program.

4.

NUREG-1302, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors, Generic Letter 89-01, Supplement No. 1.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-20a

Rev.6 Ventilation Exhaust Treatment System B 3.11.2.5 B 3.11.2.5 Ventilation Exhaust Treatment System BASES TRO This TRO ensures that the appropriate subsystems of the VENTILATION EXHAUST TREATMENT SYSTEM, as described in the Offsite Dose Calculation Manual (ODCM) are FUNCTIONAL at all times. The TRO is modified by a Note which requires that the appropriate subsystems of the VENTILATION EXHAUST TREATMENT SYSTEM be used to reduce radioactive materials in gaseous waste prior to their discharge when projected doses due to gaseous effluent releases from either reactor unit to areas at and beyond the SITE BOUNDARY would exceed 0.3 mrem to any organ in a 31-day period. This requirement provides reasonable assurance that the releases of radioactive materials in gaseous effluents will be kept "as low as reasonably achievable." This TRO implements the requirements of 1 O CFR 50.36a, General Design Criterion 60 of Appendix A to 10 CFR 50, and the* design objectives given in Section I1.D of Appendix I to 10 CFR 50. The limits governing the use of appropriate subsystems of the systems were specified as a suitable fraction of the dose design objectives set forth in Sections I1.B and I1.C of Appendix I, 10 CFR 50, for gaseous effluents (Reference 1 ).

The VENTILATION EXHAUST TREATMENT SYSTEM is comprised of the following Unit 2 subsystems, as described in the ODCM:

The Unit 2 Zone 2 Reactor Building filtered exhaust subsystem, including the following filters:

2F255A, 2F255B, 2F257 A, 2F257B, 2F258A AND 2F258B.

The Unit 2 Zone 3 Reactor Building filtered exhaust subsystem, including the following filters:

2F216A, 2F216B, 2F217A, 2F217B, 2F218A, and 2F218B.

The Unit 2 Turbine Building filtered exhaust subsystem, including the following filters:

2F157 A, 2F157B, 2F158A, and 2F158B.

This section of the TRM is part of the ODCM (Reference 2) and impleme11ts the requirements of the Radiological Effluent Controls Program (Reference 3).

SUSQUEHANNA - UNIT 2 TRM / B 3.11-21

Rev. 6 BASES ACTIONS TRS Ventilation Exhaust Treatment System B 3.11.2.5 The ACTIONS have been modified by a Note that allows _separate Conditions entries for each subsystem. The ACTIONS are defined to ensure proper corrective measures are taken in response to the nonfunctional components.

A.1 The appropriate subsystem of the VENT! LA Tl ON EXHAUST TREATMENT SYSTEM will be declared nonfunctional if any of the following conditions exist:

1. Failure of,a surveillance test;

2. Broken or non-functional component which prevents the subsystem from being run (e.g., both 100% fans or one 50% fan in the subsystem); or

3. Bypass or degradation of subsystem filtration in which effluent flow continues without full treatment.

With a subsystem of the VENTILATION EXHAUST TREATMENT SYSTEM nonfunctional, action must be taken to restore it to FUNCTIONAL status. The 31-day Completion Time is a reasonable time frame to repair the nonfunctional components.

8.1 If the Required Action and Completion Time of Condition A are not met, or gaseous waste is being discharged without treatment and in excess of the TRO limit, a condition report shall be initiated and processed in accordance with station reporting and Corrective Action Program procedures (Reference 4).

The TRSs are performed at the specified Frequency to ensure that the VENTILATION EXHAUST TREATMENT SYSTEM is maintained FUNCTIONAL.

TRS 3.11.2.5.1 This surveillance requires that a dose projection be performed in accordance with the methodology and parameters in the ODCM. The dose projection is performed based on the most recently available effluent data. If it is known prior to performing the dose projection that a treatment subsystem will be out of service, and if data exists which indicates how the.lack of treatment will impact effluents, these factors will be considered when performing the dose projection. The 31-day Frequency is co*nsistent with Reference 3.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-22

Rev. 6 BASES TRS (continued)

REFERENCES TRS 3.11.2.5.2 Ventilation Exhaust Treatment System B 3.11.2.5 This surveillance verifies that each of the subsystems of the VENTILATION EXHAUST TREATMENT SYSTEM is FUNCTIONAL by operating the. system ~ 10 minutes. Operation of the subsystem for at least 10 minutes provides sufficient time to verify the appropriate parameters are within their normal operating range. The Frequency of 92 days is appropriate considering the performance of monthly dose projections.

This TRS is modified by a Note which states that the TRS is not required to be performed if the appropriate subsystem has been utilized to process radioactive gaseous effluents during the previous 92 days. This allowance is appropriate because actual processing of radioactive gaseous effluents demonstrates subsystem FUNCTIONALITY.

TRS 3.11.2.5.3 This SR verifies that the required filter testing is performed in accordance with the Filter Testing Program. The Filter Testing Program includes testing HEPA filter performance, charcoal adsorber efficiency, and the physical properties of the activated charcoal (general use and following specific operations). Specific test frequencies and additional information are discussed in detail in the Filter Testing Program. The following filters will be tested:

Unit 2 RB Zone 2 filtered exhaust: 2F255A, 2F2558, 2F257 A, 2F257B, 2F258A and 2F2588 Unit 2 RB Zone 3 filtered exhaust: 2F216A, 2F216B, 2F217A, 2F2178, 2F218A and 2F218B Unit 2 TB filtered exhaust: 2F157 A, 2F1578, 2F158A and 2F1588

1.

1 O CFR 50, Appendix I.

2.

Technical Specification 5.5.1 - Offsite Dose Calculation Manual.

3.

Technical Specification 5.5.4 - Radioactive Effluent Controls Program.

4.

NUREG-1302, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors, Generic Letter 89-01, Supplement No. 1.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-23

Rev. 3 Radioactive Gaseous Effluent Monitoring Instrumentation B 3.11.2.6 B 3.11.2.6 Radioactive Gaseous Effluent Monitoring Instrumentation BASES TRO The radioactive gaseous effluent instrumentation is provided to monitor and control, as applicable, the releases of radioactive materials in gaseous effluents during actual or potential releases of gaseous effluents.

The alarm/trip setpoints for these instruments shall be calculated in accordance with the procedures in the ODCM (Reference 2) to ensure that the alarm/trip will occur prior to exceeding the release rate limits corresponding to dose rates above background to a MEMBER OF THE PUBLIC at or beyond the site boundary to ~ 500 mrem/yr to the total body or to~ 3000 mrem/yr to the skin. The FUNCTIONALITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR 50 (References 3 and 4).

FUNCTIONALITY requires alarm/trip setpoints set to ensure that the

1 limits of TRO 3.11.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the methodology and parameters in the ODCM.

This section of the TRM is also part of the ODCM (Reference 2).

The vent effluent monitor for the Turbine Building and Standby Gas Treatment System (SGTS) is a wide range noble gas monitor. The Effluent channel #4 for each of the Turbine and SGTS displays the release rate in uCi/min using the best detector in range. Upscale and failure alarms originate from the Effluent channel. There are 3 detectors for each wide range gas monitor, low, mid and high range. During normal plant operations, the low range channel will be selected for Effluent channel calculation. The mid and high range detectors are in standby mode. The mid and high range detectors are activated and selected automatically based upon the monitored noble gas concentration. During high range noble gas releases, the mid and high range detectors are activated and the low range noble gas detector loop is selected in standby mode. Faults detected by the vent effluent monitor will be annunciated in the main control room overhead annunciator via the Effluent channel. These loops can be considered FUNCTIONAL if the Effluent release rate channel is not alarmed.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-24

Rev. 3 BASES TRO (continued)

ACTIONS TRS Radioactive Gaseous Effluent Monitoring Instrumentation B 3.11.2.6 The Turbine Building and SGTS vent sample flow system operates to support the detector selection requirements. Normally the low range sample flow is operating to support the low range detector. On detection of an upscale noble gas release, the mid/high range sample pump that is normally in standby mode is activated to draw a sample through the mid and high range noble gas detectors and low range sample flow system is in standby mode. The mid / high range sample is then selected and low range sample flow is activated automatically when noble gas concentrations return to normal levels. The bypass sample flow system is designed to make up the proper sample flow rate from the sampling probe array in the applicable exhaust vent. For the Turbine Building monitor, the bypass system is required to operate continuously. For the SGTS, the bypass system is in standby mode until high range noble gas is sensed and the bypass system is automatically activated and selected as required. These loops can be considered FUNCTIONAL if the Effluent release rate channel is not alarmed.

The Actions are defined to ensure proper corrective measures are taken in response to the nonfunctional components.

Low range Noble Gas channel readings from the local vent monitor may be used to meet the requirement for a Noble Gas grab sample *and grab sample analysis.

Noble Gas release grab samples are not required to be taken when there are no releases via that pathway. Effluent flow is to be determined by vent flow instrumentation or by a vent flow estimate every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Continuous sample collection shall be on the same basis as described in the Bases for TRO 3.11.2.1.

Monitoring may be interrupted for up to 30 minutes to perform particulate filter/iodine cartridge changeout required by TRM Table 3.11.2-1 without entering the TRO ACTIONS.

For Required Actions and Completion Times not met for Conditions B through J, a condition report shall be initiated and processed in accordance with station reporting and Corrective Action Program procedures (Reference 6).

The TRSs are defined to be performed at the specified Frequency to ensure that the monitoring instrumentation is maintained FUNCTIONAL.

The TRSs shall be performed in accordance with the Technical Specification definition for the test with the following additional requirements:

SUSQUEHANNA - UNIT 2 TRM / B 3.11-24a

Rev. 3 BASES TRS (continued)

REFERENCES Radioactive Gaseous Effluent Monitoring Instrumentation B 3.11.2.6 The CHANNEL FUNCTIONAL TEST for all noble gas activity monitors shall also demonstrate that control room alarm annunciation occurs if any of the following conditions exists:

1. Instrument indicates measured levels above the alarm/trip

setpoint,

2. Circuit failure, and

3. Instrument indicates a downscale failure..

The initial CHANNEL CALIBRATION for all noble gas activity monitors shall be performed using one or more of the reference standards certified by the National Institute of Standards and Technology (NIST) or using standards that have been obtained from suppliers that participate in measurement assurance activities with NIST. These standards shall permit calibrating the system over its intended range of energy and r:neasurement range. For subsequent CHANNEL CALIBRATION, sources that have been related to the initial calibration may be used in lieu of reference standards associated with the initial calibration..

Particulate or iodine sampling required to be in continuous service will be considered to remain and have been in continuous service when its service is interrupted for a period of time not to exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months per sampling period. For particulate and iodine sampling, this is a small fraction of the normal minimum analysis frequency.

1.

Technical Specification 5.5.4 - Radioactive Effluent Controls program.

2.

Technical Specification 5.5.1 - Offsite Dose Calculation Manual.

3.

10 CFR 20.

4.

10 CFR 50.

5.

FSAR Section 11.5.2.1.

6.

Technical Specification 5.6.3 - Radioactive Effluent Release Report.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-25

Rev. 1 B 3.11.3 Total Dose BASES TRO ACTIONS TRS Total Dose 8 3.11.3 This Requirement is provided to meet the dose limitations of 40 CFR 190 that were previoursly incorporated into 10 CFR 20 by 46 FR 18525.

10 CFR 20.2203 *requires, in part, the preparation and submittal of a report whenever levels of radiation or releases of radioactive material exceed the applicable environmental radiation standards in 40 CFR 190 or license conditions related to those 40 CFR 190 standards (References 3 and 4).

The Actions are defined to ensure proper corrective measures are taken when requirements are not met.

Calculations required by Action A.1 shall include direct radiation contributions from both reactor units and from outside storage tanks to determine whether the limits of this TRO have been exceeded.

If it is determined that the TRO 3.11.3 limits have been exceeded, a condition report shall be initiated and processed in accordance with station reporting and Corrective Action Program procedures (References 3, 4 and 5).

The TRSs are defined to be performed at the specified Frequency to ensure that requirements are implemented.

TRS 3.11.3.1 cumulative dose contributions from liquid and gaseous effluents shall be determined in accordance with TROs 3.11.1.2, 3.11.2.2, and 3.11.2.3, The direct radiation dose is determined from the results of radiation monitoring with TLDs that is conducted by the SSES REMP.

The REMP TLDs are processed quarterly. There is no requirement to show compliance with the 40 CFR 190 dose limits* more frequently than an annual basis. Demonstration of compliance with this dose limit considers the combined dose contributions from liquid and gaseous effluents and direct radiation.

SUSQUEHANNA - UNIT 2 TRM / 8 3. 11-26.

Rev. 1 BASES REFERENCES Total Dose B 3.11.3

1.

Technical Specification 5.5.4 - Radioactive Effluent Controls program.

2.

Technical Specification 5.5.1 - Offsite Dose Calculation Manual.

3.

40 CFR 190.

4.

10 CFR 20.2203.

5.

NUREG-1302, Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors, Generic Letter 89-01, Supplement No. 1.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-27

Rev. 7 Monitoring Program B 3.11.4.1 B 3.11.4.1 Monitoring Program BASES TRO

ACTIONS TRS The radiological environmental monitoring program required by this Requirement provides representative measurements of radiation and of radioactive materials in those environmental exposure pathways and for those radionuclides that lead to the highest potential radiation exposures ofMEMBERS OF THE PUBLIC resulting from the station operation. This monitoring program thereby supplements the radiological effluent monitoring program by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways. Changes to the radiological environmental monitoring program specified in Table 3.11.4.1-1 may be made based on expected SSES operation and the results of radiological environmental monitoring during SSES operation.

,The required detection capabilities for environmental sample analyses are tabulated in terms of the lower limits of detection (LLDs). The LLDs required by Table 3.11.4.1-3 are considered optimum for routine environmental measurements in industrial laboratories. It should be recognized that the LLD is defined as an a priori (before the fact) limit representing the capability of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement.

Detailed discussion of the LLD, and other detection limits, can be found in HASL Procedures Manual, HASL-300 (revised annually); Currie, L.A.,

"Limits for Qualitative Detection and Quantitative Determination -

Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968); and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975) (Reference 1).

This section of the TRM is also part of the ODCM (Reference 2).

The Required Action for each Condition is to generate a condition report.

Each condition report shall be,initiated and processed in accordance with station reporting and Corrective Action Program procedures (References 5, 6 and 7).

The TRSs are defined to be performed at the specified frequency to ensure that the requirements are implemented. Monitoring samples collected per TRS 3.11.4.1.1 shall be from the specific locations given in the table and figure in the ODCM (Reference 2).

SUSQUEHANNA - UNIT 2 TRM / B 3.11-28

Rev. 7 BASES TRS (continued)

Monitoring Program B 3.11.4.1 The TRSs are modified by a Note to take exception to TRS 3.0.3.

Table 3.11.4.1-1 Sample Locations Specific parameters of distance and direction sector from the centerline of one reactor, and additional description where pertinent, shall be provided for each and every sample loca.tion in this Table and in a table and figure(s) in the ODCM. Refer to NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979. (Reference 3) and NUREG-1302, Offsite Dose Calculation Manual Guidance: "Standard Radiological Effluent Controls for Boiling Water Reactors," April 1991 (Reference 5). Deviations are permitted from the required sampling schedule if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of automatic sampling equipment and other legitimate reasons. If specimens are unobtainable due to sampling equipment malfunction, every effort shall be made to complete corrective action prior to the end of the next sampling period. All deviations from the sampling schedule shall be documented in the Annual Radiological Environmental Operating Report. It is recognized that, at times, it may not be possible or practicable to continue to obtain samples of the media of choice at the most desired location or time.

In these instances, suitable alternative media and locations may be chosen for the particular pathway in question and appropriate substitutions made within 30 days in the radiological environmental monitoring program. Identify the cause of the unavailability of samples for that pathway and identify the new location(s) for obtaining replacement samples in the next Radioactive Effluent Release Report and also include in the report a revised figure(s) and table for the ODCM reflecting the new location(s).

Direct Radiation One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. Film badges shall not be used as dosimeters for measuring direct radiation.

Radioiodine and Particulates - Sampling and Collection Frequency The charcoal cartridges used in the airborne radioiodine sampling conducted as part of the radiological environmental monitoring program are designed and tested by the manufacturer to assure a high efficiency in the capture of radioiodine. Certificates from the manufacturer of the cartridges are provided with each batch of cartridges certifying the percent retention of the radioiodine for stated air flows.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-29

Rev. 7 BASES TRS (continued)

Monitoring Program B 3.11.4.1 Radioiodine and Particulates - Particulate Sample; Waterborne -Surface, Ground, Sediment; Food Products Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the facility.

Waterborne - Surface The "upstream sample" shall be taken at a distance beyond significant influence of the discharge. The "downstream" sample shall be taken just downstream of the discharge line near the mixing zone.

Waterborne - Drinking - Sampling and Collection Frequency A composite sample is one in which the quantity (aliquot) of liquid sampled is proportional to the quantity of flowing liquid and in which the method of sampling employed results in a specimen that is representative of the liquid flow. In this program composite samples shall be collected at time intervals that are very short (e.g., hourly) relative to the compositing period (e.g., monthly) in order to assure obtaining a representative sample.

Waterborne - Ground* - Samples and Sample Locations Groundwater samples shall be taken when this source is tapped for drinking or irrigation purposes in areas where the hydraulic gradient or recharge properties are suitable for contamination.

Drinking Water 131 Analyses Calculation of the dose projected from 1-131 in drinking water to determine if 1-131 analys.es of the water are required shall be performed for the maximum organ and age group using the methodology and parameters of the ODCM.

Food Products - Sampling and Collection Frequency If harvest occurs more than once a year, sampling shall be performed during each discrete harvest. If harvest occurs continuously, sampling shall be monthly.

Attention shall be paid to including samples of tuberous and root food products.

Table 3.11.4.1-3 This list does not mean that only these nuclides are to be considered.

Other peaks that are identifiable at 95% confidence level together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating report.

Required detection capabilities for dosimeters used.for environmental measurements are given in Regulatory Guide 4.13 (Reference 4).

SUSQUE~ANNA - UNIT 2 TRM / B 3.11-30

Rev. 7 BASES TRS (continued)

Table 3.11.4.1-3 (continued)

Monitoring Program B 3.11.4.1 The LLD is defined, for purpose of these Requirements, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

LLD = ____

4_.6_6_s_b ___ _

E* V

2.22

Y

exp(--1.M)

Where:

LLD is the a priori lower limit of detection as defined above (as picocuries per unit mass or volume),

sb is the standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute),

E is the counting efficiency, as counts per disintegration, V is the sample size, in units of mass or vol\\,lme,

2.22 is the number of disintegrations per minute per picocurie, Y is the fractional radiochemical yield, when applicable, A is the radioactive decay constant for the particular radionuclide, and Llt for environmental samples is the elapsed time between sample collection (or end of the sample collection period) and time of counting.

Typical values of E, V, Y, and Llt should be used in the calculation.

It should be recognized that the LLD is defined as a priori (before the fact) limit representing the capability 'of a measurement system and not as an a posteriori (after the fact) limit for a particular measurement. Analyses shall be performed in such a manner that the stated LLDs will be achieved under routine conditions. Occasionally background fluctuations, unavoidably small sample sizes, the presence of interfering nuclides, or other uncontrollable circumstances may render these LLDS unachievable. In such cases, the contributing factors shall be identified and described in the Annual Radiological Environmental Operating Report.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-31

Rev. 7 BASES REFERENCES Monitoring Program 8 3.11.4.1

1.

HASL Procedures Manual, HASL-300 (revised annually); Curie, L.A.,

"Limits for Qualitative Detection and Quantitative Determination -

Application to Radiochemistry" Anal. Chem. 40, 586-93 (1968); and Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975) Offsite Dose Calculation Manual.

2.

Technical Specification 5.5.1 - Offsite Dose Calculation Manual.

3.

NUREG-0133, "Preparation of Radiological* Effluent Technical Specifications for Nuclear Power Plants," October 1978, and to Radiological Assessment Branch Technical Position, Revision 1, November 1979.

4.

Regulatory Guide 4.13, "PerformaJ1ce, Testing, and Procedural Specifications for Thermoluminescence Dosimetry: Environmental Applications."

5.

NUREG-1302, Offsite Dose Calculation Manual Guidance: "Standard Radiological Effluent Controls for Boiling Water Reactors,"

April 1991.

6.

Technical Specification 5.6.2 - Annual Radiological Environmental Operating Report.

7.

Technical Specification 5.6.3-Radioactive Effluent Release Report.

SUSQUEHANNA - UNIT 2 TRM / 8 3.11-32

Rev. 7 BASES THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 2

TRM / 8 3.11-33 Monitoring Program B 3.11.4.1

Rev. 1 Land Use Census B 3.11.4.2 B 3.11.4.2 Land Use Census BASES TRO ACTIONS The Land Use Census shall identify within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden of greater than 50m2 (500ft2) producing broad leaf vegetation.

This Requirement is provided to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the results of this census. The best information from the door-to-door survey, aerial survey or consulting with local agricultural authorities or any combination of these methods shall be used. This census satisfies the requirements of Section IV.B.3 of.Appendix I to 10 CFR Part 50. Restricting the census to gardens of greater than 500 square feet provides assurance that significant exposure pathways* via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to produce the quantity (26 kg/year) of leafy vegetables assumed in Regulatory Guide 1.109 for consumption by a child. To determine this minimum garden size, the following assumptions were used: 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/square meter (Reference 1 and 2).

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the site bo1,.1ndary in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications for broad leaf vegetation sampling in Table 3.11.4.1-1 item 4c shall be followed, including analysis of control samples.

This section of the TRM is also part of the ODCM (Reference 3).

The Actions are defined to ensure proper corrective measures are taken in when requirements are not met.

The sampling location(s), excluding the control station location, having the lowest calculated dose, or dose commitment(s) (via the same exposure pathway) may be deleted from the monitoring program after October 31 of the year in which the land use census was conducted.

SUSQUEHANNA - UNIT2 TRM / B 3.11-34

Rev. 1 BASES TRS REFERENCES Land Use Census B 3.11.4.2 The TRSs are defined to be performed at the specified Frequency to ensure that the requirements are implemented.

The Land Use Census shall be conducted during the growing season at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report.

1. 10 CFR Part 50.

-2. Regulatory Guide 1.109, "Calculation of Ann\\,.lal Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977.

3. Technical Specification 5.5.1 - Offsite Dose Calculation Manual.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-35

Rev. 1 lnterlaboratory Comparison Program B 3.11.4.3 B 3.11.4.3 lnterlaboratory Comparison Program BASES TRO ACTIONS TRS REFERENCES The lnterlaboratory Comparison Program shall be accepted by the Commission. The requirement for participation in an lnterlaboratory Comparison Program is provided to ensure that independent checks on the precision and accuracy of the measurements of radioactive material in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring in order to demonstrate that the results are reasonably valid for the purpose of Section IV.B.2 of Appendix I to 10 CFR 50 (Reference 1).

This part of the TRM is also part of the ODCM (Reference 2).

For analyses not being performed, a condition report shall be initiated and processed in accordance with station reporting and Corrective Action Program procedures (Reference 3).

The TRSs are defined to be performed at the specified Frequency to ensure that the requirements are implemented.

1.

10 CFR 50.

2.

Technical Specification 5.5.1 - Offsite Dose Calculation Manual.

3.

Technical Specification 5.6.2 - Annual Radiological Environmental Operating Report.

SUSQUEHANNA - UNIT 2 TRM / B 3.11-36

Rev. 8 TRM Post Accident Monitoring Instrumentation B 3.3.4 B 3.3.4 TRM Post Accident Monitoring (PAM) Instrumentation BASES TRO The primary purpose of the TRM PAM instrumentation is to display plant variables that provide information required by the control room operators during accident situations. The OPERABILITY of the TRM PAM instrumentation ensures that the identified information is available on selected plant parameters to monitor and assess important variables following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97 Revision 2, "Instrumentation fo'r Light Water Cooled Nuclear Power Plants to Assess Plant Conditions During and following ali Accident," NUREG-0578, "TMl-2 Lessons Learned Task Force Status Report and Short-Term Recommendations" and NEDO-33160-A Revision 1, "Regulatory Relaxation For The Post Accident SRV Po,sition Indication System" (Reference 6). It should be noted that the Technical Specifications LCO 3.3.3.1 contains all Category 1, non-type A instruments and Regulatory Guide 1.97 Type A instrument (References 1 and 2). This TRO requires instruments outside of these criteria.

Table 3.3.4-1 identifies the following required Functions. Suppression Chamber Air Temperature provides a post accident indication of problems with the primary containment pressure suppression system. The Suppression Chamber Air Temperature loops are comprised of the following instruments for the purposes of this TRM. The recorders are the

primary method of indication used by operator during an accident; therefore, the PAM specification deals specifically with this portion of the instrument.

LOOPA LOOPS TE-25703 TE-25725 TT-25703 TT-25725 TR-25795A TR-257958 Main Steam Safety/Relief Valve Position Indicators (Acoustic Monitors}

provide indication when the valves are functioning. Alternate methods for monitoring SRV position include SRV Tailpipe Temperature and the following Functions from Technical Specific~tion Table 3.3.3.1-1:

Suppression Chamber Water Level (Function 3)

Suppression Chamber Water Temperature (Function 10)

Reactor Vessel Water Level (Function 2)

Reactor Steam Dome Pressure (Function 1)

SUSQUEHANNA - UNIT 2 TRM / B 3.3-4

Rev. 8 BASES TRO (continued)

TRM Post Accident Monitoring. Instrumentation B 3.3.4 The required channels for Standby Gas Treatment System Vent Noble Gas Monitor and Turbine Building Vent Noble Gas Monitor provide information regarding the release of radioactive materials to allow for early indication of the need to initiate action necessary to protect the public and for an estimate of the magnitude of any impending threat. For the Noble Gas Monitors the only required channels are the mid range and high range.

The drywell and suppression chamber hydrogen and oxygen concentrations gas analyzers monitor hydrogen and oxygen concentration to detect combustible gas levels in primary containment.

The analyzers are capable of determining hydrogen concentration in the range of O to 30% by volume and oxygen concentration in the range of 0 to 10% by volume, and each provide control room indication and output to a control.room recorder. Each gas analyzer must be capable of sampling either the drywe,II or the suppression chamber. The recorders are the primary method of indication available for use by the operator during an accident, therefore the PAM Specification deals specifically with this portion of the instrument channel. The gas analyzer piping is provided with heat tracing to reduce the buildup of condensation in the system.

H2O2 Analyzers can be considered OPERABLE for accident monitoring for up to 100 days with their heat tracing INOPERABLE.

The vent effluent monitor for the Turbine Building and Standby Gas Treatment System (SGTS) is a wide range noble gas monitor. The Effluent channel #4 for each of the Turbine and SGTS displays the release rate in uCi/min using the best detector in range. Upscale and failure alarms originate from the Effluent channel. There are 3 detectors for each wide range gas monitor, low, mid and high range. During normal plant operations, the low range channel will be selected for Effluent channel calculation. The mid and high range detectors are in standby mode. The mid and high range detectors are activated and selected automatically based upon the monitored noble gas concentration. During high range noble gas releases, the mid and high range detectors are activated and the low range noble gas detector loop is selected in standby mode. Faults detected by the vent effluent monitor will be annunciated in the main control room overhead annunciator via the Effluent channel. These loops can be considered Operable if the Effluent release rate channel is not alarmed.

SUSQUEHANNA - UNIT 2 TRM / B 3.3-5

Rev. 8 BASES TRO

( continued)

ACTIONS TRM Post Accident Monitoring Instrumentation B 3.3.4 The Turbine Building and SGTS vent sample flow system operates to support the detector selection requirements. Normally the low range sample flow is operating to support the low range detector. On detection of an upscale noble gas release, the mid/high range sample pump that is normally in standby mode is activated to draw a sample through the mid and high range noble gas detectors and low range sample flow system is in standby mode. The mid / high range sample is then selected and low range sample flow is activated automatically when noble gas concentrations return to normal levels. The bypass sample flow system is designed to make up the proper sample flow rate from the sample probe array in the applicable vent. For the Turbine Building monitor, the bypass system is required to operate c~ntinuously. For the SGTS, the bypass system is in standby mode until high range noble gas is sensed and the bypass system is automatically activated and selected as required.

These loops can be considered Operable if the Effluent release rate channel is not alarmed.

The Actions are defined to ensure proper corrective measures are taken in response to the inoperable components.

Action D requirements were determined by balancing the safety significance of the system with the impact of the actions on the operating unit. The loss of the acoustic monitors is not safety significant providing the diverse and redundant alternate methods of determining SRV position are available. System components in the control room are restorable within 30 days without unit operation impact. Components located in containment require a unit shutdown to gain access to individual components. The system channels shall be restored to operable condition at earliest opportunity.

Noble gas monitoring may be interrupted for up to 30 minutes to perform particulate filter/iodine cartridge changeout required by TRM Table 3.11.2-1 without entering the TRO ACTIONS.

Components of alternate SRV position systems may be taken inoperable for routine surveillances and periodic maintenance providing the appropriate LCO requirements are met during this action statement.

Tailpipe temperature is the direct process monitoring, alternate method and is not covered by Technical Specification LCO's as are the other alternative methods.

SUSQUEHANNA - UNIT 2 TRM / B 3.3-5a

Rev. 8 BASES TRS TRM Post Accident Monitoring Instrumentation 8 3.3.4 The Technical Requirement Surveillances (TRS) are modified by two Notes.

Note 1 states that the TRSs for each Post Accident Monitoring Instrumentation Function are located in the SR column of Table 3.3.4-1.

Note 2 modifies the Surveillances to indicate that 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided an alternate means of monitoring the parameter or associated Function are available. Upon completion of the Surveillance, or expiration of the 6-hour allowance, the channel must be returned to OPERABLE status or the applicable Condition entered and Required Actions taken.

The alternate means of monitoring the parameter or the associated function are:

Parameter Suppression Chamber Air Temperature Main Stearn Safety/Relief Valve Position Indicator Alternate Means/Associated Function One channel of Suppression Chamber Air Temperature Suppression Pool level Suppression Pool Temperature RPVlevel RPV pressure SRV Tailpipe Temperature Containment H2and 02Analyzer One channel of Containment H2 and 02 The TRSs are defined to be performed at the specified Frequency to ensure that the TRM PAM Function is maintained OPERABLE.

TRS 3.3.4.1 Performance of the CHANNEL CHECK once every 31 days ensures that a gross failure of instrumentation has not occurred. A CHANNEL CHECK is normally a comparison of the parameter indicated on one channel against a similar parameter on other channels. It is based on the assumption that instrument channels monitoring the same parameter should read approximately the same value. Significant deviations between instrument channels could be an indication of excessive instrument drift in one of the channels or something even more serious.

A CHANNEL CHECK will detect gross channel failure; thus, it is key to verifying the instrumentation continues to operate properly between each CHANNEL CALIBRATION.

SUSQUEHANNA - UNIT 2 TRM / B 3.3-6

Rev. 8 BASES TRS

( continued)

REFERENCES TRM Post Accident Monitoring Instrumentation B 3.3.4 TRS 3.3.4.1 (continued)

Agreement criteria, which are determined by the plant staff based on an investigation of a combination of the channel instrument uncertainties, may be used to support this parameter comparison and include indication and readability.* If a channel is outside the criteria, it may be an indication that the instrument has drifted outside its limit and does not necessarily indicate the channel is inoperable.

1. Regulatory Guide 1.97 Revision 2, "Instrumentation for Light Water Cooled Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident."

2.

3.

4.

5.

6.

7.

NUREG-0578, "TMl-2 Lessons Learned Task Force Status Report and Short-Term Recommendations."

Technical Specification Amendment No. 100 to License No. NPF-22 for failed Unit 2 "S" acoustic monitor.

Technical Specification Amendment No. 169 to License No. NPF-14 for failed Unit 1 "S" acoustic monitor.

Proposed amendment No. 183 to License No. NPF-22 failed Unit 2 "J" acoustic monitor.

NEDO-33160-A, Revision 1, "Regulatory Relaxation For The Post Accident SRV Position Indication System," dated October 2006.

NRC letter, "Final Safety Evaluation For Boiling Water Reactor Owners' Group (BWROG) Topical Report (TR) NEDO-33160, Regulatory Relaxation For The Post Accident SRV [Safety Relief Valve] Position Indication System (TAC No. MC5446)," dated September 26, 2006.

8. FSAR Section 11.5.2.1.

SUSQUEHANNA - UNIT 2 TRM / B 3.3-7

Rev. 8 BASES TRM Post Accident Monitoring Instrumentation B 3.3.4 THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 2 TRM / B 3.3-8

Rev. 1 Venting or Purging B 3.6.1 B 3.6.1 Venting or Purging BASES TRO ACTIONS This TRO establishes the requirements necessary to VENT or PURGE the Primary Containment to provide reasonable assurance that releases from the Primary Containment during purging operations will be maintained As Low As Reasonably Achievable for unrestricted areas. The following requirements are specified:

Flow must be maintained through Standby Gas Treatment System and when venting or purging both SGTS must be OPERABLE and only one can be aligned for purging. This requirement is established to ensure all flow is filtered through the SGTS System, to minimize the chance of an inadvertent release and to ensure, during purging, SGTS capability is maintained by ensuring the redundant system is available.

Ventilation evolutions to support habitability of the Drywell or the Suppression Chamber performed in Modes 4 and 5 shall be performed with the "SGTS Exhaust Radiation - High" Isolation Instrumentation OPERABLE. This is required to ensure all releases are monitored and any detection of excessive radiation results in the automatic termination of the evolution. In MODES 1, 2, or 3, this instrument Function is required to be OPERABLE per Technical Specification, so no redundant requirement is necessary in this TRO (Reference 2).

PURGING and VENTING as defined in the Technical Requirements Manual Definitions refer to the controlled process of discharging air or gas from a "confinement" in order to maintain various operating conditions, either with or without replacement air or gas.

The basis for this requirement is to provide a reasonable assurance that releases from the Primary Containment purging operations will not exceed the annual dose limits of 1 O CFR Part 20 for unrestricted areas.

Any ventilation evolutions performed during MODES 4, 5 or defueled, to support habitability of the Drywell or the Suppression Chamber, with any of the Containme.nt hatches removed or access doors open with interlocks defeated, do not constitute VENTING or PURGING as defined.

This is due to the fact that in such cases, the Drywell or the Suppression Chamber is not a "confinement". Therefore, the provisions of this TRO requiring two OPERABLE trains of the Standby Gas Treatment System

are not applicabl~.

The Actions are defined to ensure proper corrective measures are taken in response to the non-compliance with the TRO requirements.

SUSQUEHANNA - UNIT 2 TRM / B 3.6-1

Rev. 1 BASES TRS REFERENCES Venting or Purging B 3.6.1 The TRSs are defined to be performed at the specified Frequency to ensure compliance with the TRO requirements.

1. 10 CFR Part 20.

2. FSAR Section 6.5.1.1.

SUSQUEHANNA - UNIT 2 TRM / B 3.6-2

Rev. 2 Primary Containment Closed System Boundaries B 3.6.4 B 3.6.4 Primary Containment Closed System Boundaries BASES TRO A closed system used as a primary containment isolation boundary is defined as a piping system outside primary containment that does not communicate directly with the atmosphere outside primary containment, meets the design requirements of NUREG-75/087 (Reference 1), as described in FSAR Section 6.2.4 (Reference 2), and is considered an extension of primary containment. The design of several containment penetrations relies upon a single Primary Containment Isolation Valve (PCIV) and a closed piping system outside primary containment (Primary Containment Closed System) as the two isolation barrie(s, as identified in Technical Specification (TS) Bases, Table B 3.6.1.3-1. For a given containment penetration that relies upon a closed system as the redundant containment isolation barrier, the closed system boundary is essentially equivalent to the ASME Class 2 boundary for the system/loop which contains the penetration. The closed system boundaries are defined by the Leakage Rate Test Program.

As a special case, the containment penetrations for the H2O2 analyzer lines also rely upon a closed system as the redundant containment isolation barrier, even though two PC IVs are provided for each of these penetrations. The PCIVs associated with these penetrations are identified in TS Bases Table B 3.6.1.3-1. The PCIVs in each H2O2 analyzer penetration are redundant to each other with regard to mechanical operation, but are not redundant with regard to electrical operation. Both PC IVs in each of these penetrations are powered from the same electrical division in order to prevent a single electrical failure from resulting in a loss of both divisions of H2O2 analyzers. This results in the valves being susceptible to a single electrical failure which could result in both valves failing open or failing to remain closed. Because of this unique design consideration, the H2O2 penetrations are equivalent to penetrations having a single PCIV, with the closed system providing the redundant isolation barrier.

Each division of the H2O2 analyzer piping has multiple flowpaths (e.g.,

upper drywell, lower drywell, drywell return). These multiple flowpaths are interrelated and make up one closed system for each division. The tested closed system for each division is shown in the Leakage Rate Test Program.

For penetrations with a single PCIV, alteration of the corresponding closed system boundary during power operation is permitted provided that alteration does not impact the containment isolation function of the PCIV, [i.e., able to be closed (automatically or manually) or remain closed, and maintain leakage within that assumed in the design basis loss SUSQUEHANNA - UNIT 2 TRM / B 3.6-6

Rev. 2 BASES TRO

( continued)

ACTIONS Primary Containment Closed System Boundaries B 3.6.4 of coolant accident dose analysis.] Conversely, if a PCIV is in a configuration where it is not capable of performing its containment isolation function (e.g., stuck open), then closed system integrity must be maintained in order to have at least one containment isolation barrier operable. These requirements also apply to the H2O2 analyzer penetrations.

The APPLICABILITY is modified by a Note allowing Primary Containment Closed System boundaries to be unisolated intermittently under administrative controls. These controls consist of stationing a dedicated operator at the controls of the valve, who is in continuous communications with the control room. In this way, the Primary Containment Closed System can be rapidly isolated when a need for primary containment isolation is indicated.

Opening of closed system boundary valve periodically for specific activities that require the valve to be opened (e.g., testing, venting) is not considered a breach of a closed system, provided the valve is operated under administrative control. Examples include the opening of a high point vent in the Core Spray system to verify that the system is filled with water or the opening of a H2O2 analyzer boundary valve to perform a functional test of the Post Accident Sampling System. Similarly, stroking of a boundary valve as part of restoration from maintenance activities associated with that valve does not constitute a breach of the closed system. Examples of this would be the stroking of a valve where the work that was done was replacement of the motor actuator, or other work where the pressure boundary of the valve was not violated. Also, the opening of a valve as a result of normal system operation/testing does not constitute a breach of the closed system.

These ACTIONS *are provided to address Conditions where Primary Containment Closed System boundaries are inoperable. When the Primary Containment Closed System boundaries are OPERABLE, but the associated PCIV(s) is inoperable, LCO 3.6.1.3, "Primary Containment Isolation Valves (PCIVs)," Condition C or Condition D would apply.

Note 1 has been added to provide clarification that, for the purpose of the TRO, separate Condition entry is allowed for each closed system. This is acceptable, since the Required Actions for each Condition provide appropriate compensatory actions for each inoperable closed system.

Complying with Required Actions may allow for continued operation, and subsequent inoperable PCIVs or closed systems are governed by subsequent Condition entry and application of associated Required Actions.

SUSQUEHANNA - UNIT 2 TRM / B 3.6-7

Rev. 2 BASES ACTIONS (continued)

Primary Containment Closed System Boundaries B 3.6.4 The ACTIONS are modified by Notes 2 and 5. Note 2 ensures that appropriate remedial actions are taken, if necessary, if the affected system(s) are rendered inoperable by an inoperable closed system (e.g.,

an Emergency Core Cooling System subsystem is inoperable due to a failed open drain valve). Note 5 ensures appropriate remedial actions are taken when the primary containment leakage limits are exceeded.

Pursuant to TRO 3.0.6, these actions are not required even when the associated TRO is not met. Therefore, Notes 2 and 5 are added to require the proper actions be taken when Primary Containment Closed System boundaries are inoperable.

Note 3 has been added to provide clarification that failing to complete the Required Actions results in a condition that could compromise Primary Containment Integrity and thus, place the plant in an unanalyzed condition.

The ACTIONS are modified by Note 4 allowing penetration flow path(s) to be unisolated intermittently under administrative controls. This note applies to a condition where the closed system is inoperable. It does not apply to a situation where a penetration flowpath is normally open and the closed system is OPERABLE (such as the RHR and Core Spray minimum flow return lines), since that represents the normal design configuration. Administrative controls consist of stationing a dedicated operator at the controls of the valve, who is in continuous communication with the control room. In this way, the penetration can be rapidly isolated when a need for primary containment isolation is indicated.

A.1.1, A.1.2, A.2.1, and A.2.2 With one or more penetration flow paths with its Primary Containment Closed System boundary inoperable, the affected portion of the closed system piping must be isolated from the rest of the closed system and the primary containment. This Condition only applies when the associated PCIV for the penetration flow path is OPERABLE. For the penetration flow paths associated with the H2O2 analyzers, both.PCIVs must be

oPERABLE. The method of isolation must include the use of at least one isolation barrier that cannot be adversely affected by a single active failure. Isolation barriers that meet this criterion are a closed and de-activated automatic valve, a closed manual valve, and a blind flange.

Closing an intervening valve between the breach in the closed system and the open penetration is permitted when the penetration PCIV is OPERABLE. If no intervening valve exists between the closed system breach and the PCIV, then the PCIV must be closed and deactivated to ensure compliance with LCO 3.6.1.1, "Primary Containment." For the penetration flow paths associated with the H2O2 analyzers, one PCIV must be closed and deactivated. Deactivation of the H2O2 analyzer PCIVs is discussed in the TS Bases for LCO 3.6.1.3, Condition D.

SUSQUEHANNA - UNIT 2 TRM / B 3.6-8

Rev.2 BASES ACTION (continued)

Primary Containment Closed System Boundaries B 3.6.4 A.1.1, A.1.2, A.2.1, and A.2.2 (continued)

The Required Actions to isolate the closed system breach, or the penetration, must be completed within the 4-hour Completion Time. The Completion Time of 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months is consistent with LCO 3.6.1.3, Condition A, which applies to penetration flow paths with two PCIVs. The Primary Containment Closed System boundary is considered to be the functional equivalent to the ASME Class 2 boundary for the system/loop which contains the penetration. Because this boundary serves as the second barrier required by General Design Criteria 55 and 56 (Reference 3) in lieu of a second isolation valve, the same Required Actions and

. associated Completion Times are appropriate.

For inoperable closed system boundaries where the breach has been isolated from the rest of the closed system and primary containment (Required Action A.1.1), or where the penetration has been isolated by a closed and deactivated PCIV (Required Action A.1.2), the affected penetration flow path(s) must be verified to be isolated on a periodic basis. This is necessary to ensure that primary containment penetrations required to be isolated following an accident, and no longer capable of being automatically isolated, will be in the isolation position should an event occur. This Required Action does not require any testing or device manipulation. Rather, it involves verification that those devices outside containment and capable of potentially being mispositioned are in the correct position.

The Completion Time of "once per 31 days" is consistent with LCO 3.6.1.3, Condition A, and is appropriate because the devices are operated under administrative controls and the probability of their misalignment is low.

8.1 and 8.2 With one or more penetration flow paths with its Primary Containment Closed System boundary inoperable, the affected penetration flow path must be isolated within 1-hour when the corresponding PCIV for the penetration flow path is also inoperable. For the penetration flow paths associated with the H202 analyzers, this Condition applies when one or both PCIVs are inoperable. The method of isolation must include the use of at least one isolation barrier that cannot be adversely affected by a single active failure. Isolation barriers that meet this criterion are a closed and de-activated automatic valve, a closed manual valve, and a blind flange. The 1-hour Completion Time is consistent with the LCO 3.6.1.3, Condition B, which applies to penetration flow paths with two PCIVs, both of which are inoperable. Alternatively, immediate entry into the applicable Conditions and Required Actions of LCO 3.6.1.1 is permitted.

SUSQUEHANNA - UNIT 2 TRM / B 3.6-9

Rev. 2 BASES Primary Containment Closed System Boundaries B 3.6.4 ACTION C.1 (continued)

TRS If the Required Actions and associated Completion Times of Conditions A or B cannot be met, immediate entry into LCO 3.6.1.3, Condition G, is directed. The appropriate Condition to enter is determined by the operating MODE of the unit at the time of entry.

TRS 3.6.4.1 The boundaries for water filled closed systems are verified to be intact by direct observation, during operator rounds, of the lack of leakage from the system (which is under pressure from the keepfill system), or by observed integrity during functional testing as required by the applicable LCO; and by the system boundary administrative controls (i.e., by procedure and checkoff lists for evolutions that affect the system boundary). The integrity of a closed system boundary, verified in accordance with the methodologies described above, is not compromised throughout the effective surveillance period by the subsequent isolation of the keepfill system and/or depressurization of a closed system.

The boundaries for air filled closed systems are verified to be intact by verification that no work has been performed since the last leak rate test in accordance with TRS 3.6.4.2, and by the system boundary administrative controls (i.e., procedure and checkoff lists for evolutions that affect the system boundary).

The Frequency corresponds to the lnservice Testing Program requirements for performing valve testing at least once every 92 days.

TRS 3.6.4.2 When restoring a closed system, testing must be performed to verify system integrity. Explicit quantification of the leakage is not required for water filled closed systems. However, testing must be sufficient to assure that an essentially leaktight barrier exists (no gross leakage). For air filled closed systems, ~xplicit leakage quantification is required, and is performed in accordance with the Leakage Rate Test Program.

The Frequency of testing is in accordance with the Leakage Rate Test Program.

SUSQUEHANNA - UNIT 2 TRM / B 3.6-10

Rev. 2 BASES REFERENCES Primary Containment Closed System Boundaries B 3.6.4

1. NUREG-75/087, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants", September 1975.

2. FSAR Section 6.2.4, "Containment Isolation System."

3. 10 CFR 50, Appendix A, "General Design Criteria for Nuclear Power Plants."

SUSQUEHANNA - UNIT 2 TRM / B 3.6-11

Rev. 1 Ultimate Heat Sink (UHS) Ground Water Level B 3.7.2 B 3.7.2 Ultimate Heat Sink (UHS) Ground Water Level BASES TRO ACTIONS TRS The UHS provides the source of cooling water for both the RHRSW System and the ESW System. After removing heat from the various plant systems (through the RHRSW System or ESW System), the water is discharged to the spray pond (UHS) by way of a network of sprays that dissipate the heat to the atmosphere or directly to the UHS via a bypass valve.

Ground water elevation is monitored to assure that elevated ground water beneath the spray pond cannot undermine its support.

The TRO and Applicability are modified by a Note, which identifies that for the UHS the TRO requirements are not Applicable in Modes 1, 2, and 3.

In thes_e Modes Technical Specification 3.7.1, "RHRSW and UHS",

establishes the requirements for the UHS. The TRO requirements for the Ground Water Level are applicable at all times.

The Actions are defined to ensure proper corrective measures are taken in response to the nonfunctional components/conditions.

If the groundwater level at any spray pond area observation well is greater than or equal to 663 feet Mean Sea Level (MSL), a condition report must be initiated and processed in accordance with station reporting and Corrective Action Program procedures (Reference 2).

B.1 If the UHS is nonfunctional, required support systems shall be evaluated and declared nonfunctional/inoperable, as applicable.

The TRSs are defined to be performed at the specified Frequency to ensure that the UHS is maintained FUNCTIONAL and the ground water level is maintained within limits. TRS 3.7.2.1 identifies that Technical Specification Surveillance Requirements (SRs) 3.7.1.1 and 3.7.1.2 are required to be met. These SRs are identified because they define the required surveillances to establish FUN(?TIONALITY.

TRS 3.7.2.2 Ground water level is to be determined at observation wells 1, 3, 4, 5, 6, and 1113.

SUSQUEHANNA - UNIT 2 TRM / B 3.7-2

Rev. 1 BASES REFERENCES

1.

FSAR Section 9.2.7 Ultimate Heat Sink (UHS) Ground Water Level B 3.7.2

2.

FSAR Section 2.5.5.2.2.1.1 SUSQUEHANNA - UNIT 2 TRM / B 3.7-2a

Rev. 1 Solid Radwaste System B 3.7.4 B 3. 7.4 Solid Radwaste System BASES TRO ACTIONS TRS The FUNCTIONALITY of the solid radwaste system ensures that the system will be available for use whenever solid radwaste requires processing and packaging prior to being shipped offsite. This specification implements the requirements of 1 O CFR 50.36a and General Design Criterion 60 of Appendix A to 10 CFR 50. The process parameters included in establishing the PROCESS CONTROL PROGRAM may include, but are not limited to waste type, waste pH, waste/liquid/waste processing times and stabilization use/catalyst ratios, waste oil content, waste principal chemical constituents, mixing and curing times.

The PROCESS CONTROL PROGRAM ensures compliance with 10 CFR 20 (20.1301 ), 10 CFR 71 and other Federal Regulations governing disposal of the waste.

This action ensures suspension of radwaste shipments when there is noncompliance with Federal Regulations applicable to those shipments, i.e., 10 CFR 20.1301, and/or 10 CFR 71.

8.1 If the solid radwaste system is nonfunctional, restore the system to FUNCTIONAL status within 31 days.

C.1 If the Required Action and associated Completion Time of Condition B are not met, a condition report must be initiated and processed in accordance with station Corrective Action Program procedures.

The TRSs are defined to be performed at the specified Frequency to ensure that the Solid Radwaste System is maintained FUNCTIONAL.

The Solid Radwaste System is demonstrated FUNCTIONAL (TRS 3.7.4.1) by:

1.

Operating the solid radwaste system at least once in the previous 92 days in accordance with the PROCESS CONTROL PROGRAM, or SUSQUEHANNA - UNIT 2 TRM / B 3.7-15

Rev. 1 BASES TRS (continued)

REFERENCES Solid Radwaste System B 3.7.4

2.

Verification of the existence of a valid contract for SOLIDIFICATION to be performed by a contractor in accordance with a PROCESS CONTROL PROGRAM.

The PROCESS CONTROL PROGRAM shall be used to verify (TRS 3.7.4.2) the SOLIDIFICATION of wet radioactive waste (e.g., filter sludges, spent resins, evaporator bottoms, and sodium sulfate solutions).

1.

10CFR20.1301.

2.

10 CFR 71.

SUSQUEHANNA - UNIT 2 TRM / B 3.7-16

Rev. 1 24 voe Electrical Power Subsystem B 3.8.4 B 3.8.4 24 voe Electrical Power Subsystem BASES TRO ACTIONS Two independent 24 VOC subsystems (20670 and 20680) are provided for operation of the reactor monitoring instrumentation systems (Ref. 1 ).

Each subsystem contains a +24 volt battery bank and a -24 volt battery bank, connected in series, and also connected to the main control room ground at the center point of the banks. The system also includes four half capacity battery chargers (20673, 20674, 20683, and 20684).

Battery reliability and independence are required for Unit availability only.

The devices connected to the 24 voe subsystems are the process radiation monitors, the source range monitors, and the intermediate range monitors. These loads are nominally rated for operation at 24 VOC.

Class 1 E 24 VOC power is not required for the safety-related system requirements of the intermediate range monitors due to their fail-safe design. other loads on the 24 VOC batteries have no safety related function. The 24 VOC batteries are conservatively designed and maintained in accordance with Class 1 E battery requirements.

The ACTIONS are defined to ensure proper corrective measures are taken in response to the nonfunctional components.

The ACTIONS have been modified by a Note to darify the application of Completion Time rules. The Conditions of this TRO may be entered independently for each subsystem and battery parameter. The Completion Time(s) of will be tracked separately for each subsystem and battery parameter starting from the time the Condition was entered as a result of discovery of that subsystem or battery parameter being nonfunctional or not within specified limits.

A.1, A.2, and A.3 With parameters of one or more cells in one or more batteries not within limits (i.e., Category A limits not met or Category B limits not met, or Category A and B limits not met) but within the Category C limits specified in Table 3.8.4-1, the battery is degraded but there is still sufficient capacity to perform the intended function. Therefore, the affected battery is not required to be considered nonfunctional solely as a result of Category A or B limits not met; and continued operation is permitted for a limited period.

SUSQUEHANNA - UNIT 2 TRM / B 3.8-6

Rev. 1 BASES ACTIONS

( continued)

A.1, A.2, and A.3 (continued) 24 voe Electrical Power Subsystem 8 3.8.4 The pilot cell electrolyte level and float voltage are required to be verified to meet the Category C limits within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months (Required Action A.1). This check provides a quick indication of the status of the remainder of the battery cells. One hour provides time to inspect the electrolyte level and to confirm the float voltage of the pilot cells. One hour is considered a reasonable amount of time to perform the required verification.

Verification that the Category C limits are met (Required Action A.2) provides assurance that during the time needed to restore the parameters to the Category A and 8 limits, the battery is still capable of performing its intended function. A period of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months is allowed to complete the initial verification because specific gravity measurements must be obtained for each connected cell. Taking into consideration both the time required to perform the required verification and the assurance that the battery cell parameters are not severely degraded, this time is considered reasonable. The verification is repeated at 7 day intervals until the parameters are restored to Category A and 8 limits. This periodic verification is consistent with the normal Frequency of pilot cell Surveillances.

Continued operation is only permitted for 31 days before battery cell parameters must be restored to within Category A and 8 limits. Taking into consideration that, while battery capacity is degraded, sufficient capacity exists to perform the intended function and to allow time to fully restore the battery cell parameters to normal limits, this time is acceptable for operation prior to declaring the DC batteries nonfunctional.

8.1 When any battery parameter is outside the Category C limit for any connected cell, sufficient capacity to supply the maximum expected load requirement is not ensured and the corresponding DC electrical power subsystem must be declared nonfunctional. Additionally, other potentially extreme conditions, such as not completing the Required Actions of Condition A within the required Completion Time or average electrolyte temperature of representative cells falling below 60°F, also are cause for immediately declaring the associated DC electrical power subsystem nonfunctional.

C.1 If any +/- 24 VDC battery bank is nonfunctional, or deenergized for any reason, it cannot perform its intended function. The supported equipment associated with the nonfunctional battery bank must immediately be_

evaluated and declared nonfunctional/inoperable, as applicable.

SUSQUEHANNA - UNIT 2 TRM / 8 3.8-7

Rev. 1 BASES TRS 24 voe Electrical Power Subsystem B 3.8.4 The TRSs are performed at the specified Frequency to ensure that the 24 voe subsystems are maintained FUNCTIONAL.

TRS 3.8.4.1 Verifying battery terminal voltage while on float charge for the batteries helps to ensure the effectiveness of the charging system and the ability of the batteries to perform their intended function. Float charge is the condition in which the charger is supplying the continuous charge required to overcome the internal losses of a battery (or battery cell) and maintain the battery (or a battery cell) in a fully charged state. The voltage requirements are based on the nominal design voltage of the battery and are consistent with the initial voltages assumed in the battery sizing calculations. The 7 day Frequency is consistent with manufacturer recommendations and IEEE-450 (Ref. 2).

TRS 3.8.4.2 This TRS verifies that Category A battery cell parameters are consistent with IEEE-450, which recommends regular battery inspections, including voltage, specific gravity, and electrolyte temperature of pilot cells.

TRS 3.8.4.3 Verification that Category B battery cell parameters are within limits is

consistent with IEEE-450, which recommends regular battery inspections, including voltage, specific gravity, and electrolyte temperature of pilot cells.

Visual inspection to detect corrosion of the battery cells and connections, or measurement of the resistance of each inter-cell, inter-rack, inter-tier, and terminal connection, provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance.

The connection resistance limits established for this TRS must be no more than 20% above the resistance as measured during installation or not above the ceiling value established by the manufacturer.

The 92 day Frequency is consistent with IEEE-450. This TRS must also be performed within 7 days of a battery discharge < 22 V or a battery overcharge > 30 V. Transients which may momentarily cause battery voltage to drop to :-::::: 22 V do not constitute a battery discharge provided the battery terminal voltage and float current return to pre-transient values. These inspections are also consistent with IEEE-450, which recommends special inspections following a severe discharge or overcharge, to ensure that no significant degradation of the battery occurs as a consequence of such discharge or overcharge.

SUSQUEHANNA - UNIT 2 TRM / B 3.8-8

Rev. 1 BASES TRS (continued)

TRS 3.8.4.4 24 VDC Electrical Power Subsystem B 3.8.4 This Surveillance verification that the average temperature of representative cells is within limits is consistent with a recommendation of IEEE-450 that states that the temperature of electrolytes in representative cells should be determined on a quarterly basis.

Lower than normal temperatures act to inhibit or reduce battery capacity.

This TRS ensures that the operating temperatures remain within an acceptable operating range. This limit is based on manufacturer's recommendations.

TRS 3.8.4.5 Visual inspection of the battery cells, cell plates, and battery racks provides an indication of physical damage or abnormal deterioration that could potentially degrade battery performance. The presence of physical damage or deterioration does not represent a failure of this TRS, provided an evaluation determines that the physical damage or deterioration does not affect the OPERABILITY of the battery (its ability to perform its design function).

The Frequency of this TRS is acceptable because other administrative controls ensure adequate battery performance during the 18 month interval. Fu*rther, operating experience has shown these components usually pass the TRS when performed at the 18 month Frequency; therefore, the Frequency is acceptable from a reliability standpoint.

TRS 3.8.4.6 Visual inspection of inter-cell, inter-rack, inter-tier, and terminal connections provides an indication of physical damage or abnormal deterioration that could indicate degraded battery condition. The anti-corrosion material is used to help ensure good electrical connections and to reduce terminal deterioration. The visual inspection for corrosion is not intended to require removal of and inspection under each terminal.

connection.

The removal of visible corrosion is a preventive maintenance TRS. The presence of visible corrosion does not necessarily represent a failure of this TRS, provided visible corrosion is removed during performance of this Surveillance.

The Frequency of this TRS is acceptable because other administrative controls ensure adequate battery performance during the 18 month interval. Further, operating experience has shown these components usually pass the TRS when performed at the 18 month Frequency; therefore, the Frequency is acceptable from a reliability standpoint.

SUSQUEHANNA - UNIT 2 TRM / B 3.8-9

Rev. 1 BASES TRS

( continued)

TRS 3.8.4.7 24 voe Electrical Power Subsystem B 3.8.4 Battery charger capability requirements are based on the design capacity of the chargers (Ref. 3). According to Regulatory Guide 1.32 (Ref. 4), the battery charger supply is required to be based on the largest combined demands of the various steady state loads and the charging capacity to restore the.battery from the design minimum charge state to the fully charged state, irrespective of the status of the unit during these demand occurrences. The minimum required amperes and duration ensures that these requirements can be satisfied.

The Frequency is acceptable, given the unit conditions required to perform the test and the other administrative controls existing to ensure adequate charger performance during these 24 rnonth intervals. In addition, this Frequency is intended to be consistent with expected fuel cycle lengths.

TRS 3.8.4.8 A battery service test is a special test of the battery's capability, as found, to satisfy the design requirements (battery duty cycle) of the DC electrical power system. The test can be conducted using actual or simulated loads. The battery service test may be performed by supplying a dummy load, verified to be greater than the actual emergency loads, while maintaining the battery terminal voltage~ 21 voe and 9.37 amperes for the entire 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months test. The discharge rate and test length corresponds to

the design duty cycle requirements as specified in Reference 1.

The Frequency of 24 months is consistent with the recommendations of Regulatory Guide 1.32 and Regulatory Guide 1.129 (Ref. 5), which state that the battery service test should be performed during refueling operations or at some other outage, with intervals between tests not to exceed 24 months.

This TRS is modified by a Note which allows a performance discharge test to be performed in lieu of a battery service test once per 60 months.

TRS 3.8.4.9 A battery performance discharge test is a test of constant current capacity of a battery, normally done in the as found condition, after having been in service, to detect any change in the capacity determined by the acceptance test. The test is intended to determine overall battery degradation due to age and usage.

SUSQUEHANNA - UNIT 2 TRM / B 3.8-10

Rev. 1 BASES TRS (continued)

TRS 3.8.4.9 (continued) 24 VDC Electrical Power Subsystem B 3.8.4 A modified discharge test is a test of the battery capacity and its ability to provide a high rate, short duration load (usually the highest rate of the duty cycle). This will confirm the battery's ability to meet the critical period of the load duty cycle, in addition to determining its percentage of rated capacity. Initial conditions for the modified performance discharge test should be identical to those specified for a service test.

The modified performance discharge test is a test of simulated duty cycle consisting of two different discharge rates. The first discharge rate consists of the one minute published rate for the battery or the largest current loads of the duty cycle, followed by a second discharge rate which employs the test rate for the performance discharge test. These discharge rates envelope the duty cycle of the service test. Since the ampere-hours removed by a published one minute discharge rate represent a very small portion of the battery capacity, the test rate can be changed to that for the performance discharge test without compromising the results of the performance discharge test. The battery terminal voltage for the modified performance discharge test should remain above the minimum battery terminal voltage specified in the service test.

Either the battery performance discharge test or the modified performance discharge test is acceptable for satisfying this TRS.

The acceptance criteria for this TRS is consistent with IEEE-450 and IEEE-485 (Ref. 6). These references recommend that the battery be replaced if its capacity is-below 80% of the manufacturer's rating. A capacity of 80% shows that the battery rate of deterioration is increasing, even if there is ample capacity to meet the load requirements.

The Frequency for this test is normally 60 months. If the battery shows degradation, or if the battery has reached 85% of its expected life and capacity is < 100% of.the manufacturer's rating, the Frequency is reduced to 12 months. However, if the battery shows no degradation but has reached 85% of its expected life, the Frequency is only reduced to 24 months for batteries that retain capacity ~ 100% of the manufacturer's rating. Degradation is indicated, according to IEEE-450, when the battery capacity drops by more than 10% relative to its capacity on the previous performance test or when it is 10% below the manufacturer's rating. All these Frequencies are consistent with the recommendations in IEEE-450.

SUSQUEHANNA - UNIT 2 TRM / B 3.8-11

Rev. 1 BASES TRS (continued)

Table 3.8.4-1 24 VDC Electrical Power Subsystem B 3.8.4 This table delineates the limits on electrolyte level, float voltage, and specific gravity for three different categories. The meaning of each category is discussed below.

Category A defines the normal parameter limit for each designed pilot cell in each battery. The cells selected as pilot cells are those whose temperature, voltage, and electrolyte specific gravity approximate the state of charge of the entire battery.

The Category A limits specified for electrolyte level are based on manufacturer's recommendations and are consistent with the guidance in IEEE-450, with the extra1/4 inch allowance above the high water level indication for operating margin to account for temperature and charge effects. In addition to this allowance, footnote a to Table 3.8.4-1 permits the electrolyte level to be above the specified maximum level during equalizing charge, provided it is not overflowing. The level excursion is due to gas generation during an equalizing charge and would be expected to return to normal (i.e., between the high and low level marks) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months days following completion of the equalizing charge.

These limits ensure that the plates suffer no physical damage, and that.

adequate electron transfer capability is maintained in the event of transient conditions. IEEE-450 recommends that electrolyte level readings should be made only after the battery has been at float charge for at least 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

The Category A limit specified for float voltage is 2 2.13 V per cell. This value is based on the recommendation of IEEE-450, which states that prolonged operation of cells below 2.13 V can reduce the life expectancy of cells. The Category A limit specified for specific gravity for each pilot

cell is 2 1.200 (0.015 below the manufacturer's fully charged nominal specific gravity or a battery charging current that had stabilized at a low value). This value is characteristic of a charged cell with adequate capacity. Accbrding to IEEE-450, the specific gravity readings are based on a temperature of 77°F (25°C).

The specific gravity readings are corrected for actual electrolyte temperature. For each 3°F (1.67°C) above 77°F (25°C), 1 point (0.001) is added to the reading; 1 point is subtracted for each 3°F below 77°F. The specific gravity of the electrolyte in a cell increases with a loss of water due to electrolysis or evaporation.

Category B defines the normal parameter limits for each connected cell.

The term "connected cell" excludes any battery cell that may be jumpered out.

SUSQUEHANNA - UNIT 2 TRM / B 3.8-12

Rev. 1 BASES TRS (continued)

Table 3.8.4-1 (continued) 24 VDC Electrical Power Subsystem B 3.8.4 The Category B limits specified for electrolyte level and float voltage are the same as those specified for Category A and have been discussed above. The Category B limit specified for specific gravity for each connected cell is 21.195 (0.020 below the manufacturer's fully charged, nominal specific gravity) with the average of all connected cells 1.205 (0.010 below the manufacturer's fully charged, nominal specific gravity).

These values are based on manufacturer's recommendations. The minimum specific gravity value required for each cell ensures that the effects of a highly charged or newly installed cell do not mask overall degradation of the battery.

Category C defines the limits for each connected cell. These values, although reduced, provide assurance that sufficient capacity exists to perform the intended function and maintain a margin of safety. When any battery parameter is outside the Category C limits, the assurance of sufficient capacity described above no longer exists, and the battery must be declared nonfunctional.

The Category C limit specified for electrolyte level (above the top of the plates and not overflowing) ensures that the plates suffer no physical damage and maintain adequate electron transfer capability. The Category C Allowable Value for voltage is based on IEEE-450, which states that a cell voltage of 2.07 V or below, under float conditions and not caused by elevated temperature of the cell, indicates internal cell problems and may require cell replacement.

The Category C limit on average specific gravity ;::: 1.195, is based on manufacturer's recommendations (0.020 below the manufacturer's recommended fully charged, nominal specific gravity). In addition to that limit, it is required that the specific gravity for each connected cell must be no less than 0.020 below the average of all connected cells. This limit ensures that the effect of a highly charged or new cell does not mask overall degradation of the battery.

The footnotes to Table 3.8.4-1 that apply to specific gravity are applicable to Category A, B, and C specific gravity. Footnote (b) of Table 3.8.4-1 requires the above mentioned correction for electrolyte temperature. A battery charging current of< 0.01 amp when on float charge is acceptable for meeting specific gravity limits because maintaining this current provides an indication that the state of charge of the battery is acceptable.

SUSQUEHANNA - UNIT 2 TRM / B 3.8-13

Rev. 1 BASES TRS (continued)

REFERENCE Table 3.8.4-1 (continued) 24 VDC Electrical Power Subsystem B 3.8.4 Because of specific gravity gradients that are produced during the recharging process, delays of several days may occur while waiting for the specific gravity to stabilize. However, following a minor battery recharge (such as an equalizing charge that does not follow a deep discharge) specific gravity gradients are not significant. A stabilized charger current is an acceptable alternative to specific gravity measurement for determining the state of charge. This phenomenon is discussed in IEEE-450. Footnote (c) to Table 3.8.4-1 allows the float charge current to be used as an alternate to specific gravity.

1.

FSAR Section 8.3.

2.

IEEE 450-1995, "IEEE Recommended Practice For Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries For Stationary Applications."

3.

IEEE-308, "IEEE Standard Criteria for Class 1 E Power Systems for Nuclear Power Generating Stations."

4.

Regulatory Guide 1.32, "Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants," Revision 2, February 1977.

5.

Regulatory Guide 1.129, Maintenance, Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants," April 1977, February 1978.

6.

IEEE-485-1883, "IEEE Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications."

SUSQUEHANNA - UNIT 2 TRM / B 3.8-14

Rev. 1 BASES 24 VDC Electrical Power Subsystem B 3.8.4

- THIS PAGE INTENTIONALLY LEFT BLANK SUSQUEHANNA - UNIT 2 TRM / B 3.8-15

SUSQUEHANNA STEAM ELECTRIC STATION Rev.29 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)

SECTION PAGE 1.0 USE AND APPLICATION............................................................................ 1.0-1 1.1 Definitions.............................................................................................. 1.0-1 2.0 PLANT PROGRAMS AND SETPOINTS....................................................... 2.0-1 2.1 Plant Programs...................................................................................... 2.0-1 2.2 Instrument Trip Setpoint Table............................................................... 2.0-5 3.0 APPLICABILITY................................................................. *.......................... 3.0-1 3.0 Technical Requirement for Operation (TRO) Applicability...................... 3.0-1 3.0 Technical Requirement Surveillance (TRS) Applicability........................ 3.0-3 3.1 REACTIVITY CONTROL SYSTEMS....... :.................................................... 3.1-1 3.1.1 Anticipated Transient Without Scram Alternate Rod Injection (ATWS-ARI) lnstrumentation.................................................................. 3.1-1 3.1.2 Control Rod Drive (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 3.2 3.2.1 3.3 3.3.1 3.3.2 3.3.3 3.3.4 3.3.5 3.3.6 3.3.7 3.3.8 3.3.9 3.3.10 3.3.11 3.3.12 Check Valve...................................................... :.................................... 3.1-9 CORE OPERATING LIMITS REPORT........................................................ 3.2-1 Core Operating Limits Report................................................................. 3.2-1 INSTRUMENTATION.................................................................................. 3.3-1 Radiation Monitoring Instrumentation..................................................... 3.3-1 Seismic Monitoring Instrumentation........................................................ 3.3-4 Meteorological Monitoring Instrumentation............................................. 3.3-7 TRM Post-Accident Monitoring Instrumentation..................................... 3.3-9 Section Not Used.................................................................................... 3.3-12 TRM Isolation Actuation Instrumentation................................................ 3.3-13 Main Turbine Overspeed Protection System.......................................... 3.3-17 Section Not Used................................................................................... 3.3-19 OPRM Instrumentation Configuration..................................................... 3.3-21 Reactor Recirculation Pump MG Set Stops............... :............................ 3.3-22 MVP Isolation lnstrumentation................................................................ 3.3-24 Water Monitoring Instrumentation.......................................................... 3.3-26 3.4 REACTOR COOLANT SYSTEM.................................................................. 3.4-1 3.4.1 Reactor Coolant System Chemistry........................................................ 3.4-1 3.4.2 Section Not Used...................................,..................................... :......... 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 Materials...................................................................... 3.4-13 3.4.6 Reactor Recirculation Single Loop Operation (SLO)

Flow Rate Restriction............................................................................. 3.4-14 SUSQUEHANNA - UNIT 2 TOC-1

SUSQUEHANNA STEAM ELECTRIC STATION Rev. 29 TABLE OF CONTENTS {TECHNICAL REQUIREMENTS MANUAL)

SECTION TITLE PAGE 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS), REACTOR PRESSURE VESSEL (RPV) WATER INVENTORY CONTROL AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM............... 3.5-1 3.5.1 ADS Manual Inhibit................................................................................ 3.5-1 3.5.2 ECCS, RPV Water Inventory Control, 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................................................................................................ 3.6-3 3.6.3 Suppression Pool Alarm Instrumentation............................................... 3.6-4 3.6.4 Primary Containment Closed System Boundaries.................................. 3.6-7 3.7 3.7.1 3.7.2 3.7.3 3.7.3.1 3.7.3.2 3.7.3.3 3.7.3.4 3.7.3.5 3.7.3.6 3.7.3.7 3.7.3.8 3.7.4 3.7.5 3.7.5.1 3.7.5.2 3.7.5.3 3.7.6 3.7.7 3.7.8 3.7.9 3.7.10 3.7.11 PLANT SYSTEMS....................................................................................... 3.7-1 Emergency Service Water System (ESW) Shutdown............................. 3. 7-1 Ultimate Heat Sink (UHS) and Ground Water Level............................... 3.7-3 Fire Protection........................................................................................ 3.7-4 Fire Suppression Water Supply System................................................. 3.7-4 Spray and Sprinkler Systems................................................................. 3.7-8 CO2 systems........................ _................................................................. 3.7-12 Halon Systems....................................................................................... 3.7-16 Fire Hose Stations.................................................................................. 3.7-18 Yard Fire Hydrants and Hydrant Hose Houses....................................... 3.7-22 Fire Rated Assemblies........................................................................... 3. 7-24 Fire Detection Instrumentation............................................................... 3.7-26 Solid Radwaste System......................................................................... 3.7-34 Explosive Gas and Storage Tank Radioactivity Monitoring Program................................................................................ 3. 7-37 Main Condenser Off gas Hydrogen Monitor............................................ 3. 7-37 Main Condenser Offgas Explosive Gas Mixture..................................... 3. 7-38 Liquid Holdup Tanks................................................. :*************************... 3.7-39 ESSW Pumphouse Ventilation............................................................... 3.7-40 Main Condenser Offgas Pretreatment Logarithmic Radiation Monitoring Instrumentation..................................................................... 3. 7-41 Snubbers............................................ *.................................................... 3. 7-43 Control Structure HVAC......................................................................... 3.7-49 Spent Fuel Storage Pools (SFSPs)........................................................ 3.7-51 Structural Integrity.................................................................................. 3.7-54 SUSQUEHANNA - UNIT 2 TOC-2

SUSQUEHANNA STEAM ELECTRIC STATION Rev.29 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)

SECTION 3.8 3.8.1 3.8.2 3.8.2.1 3.8.2.2 3.8.3 3.8.4 3.8.5 3.8.6 3.8.7 3.9 3.9.1 3.9.2 3.9.3 3.10 3.10.1 3.10.2 3.10.3 3.10.4 3.11 3.11.1 3.11.1.1 3.11.1.2 3.11.1.3 3.11.1.4 3.11.1.5 3.11.2 3.11.2.1 3.11.2.2 3.11.2.3 3.11.2.4 3.11.2.5 3.11.2.6 3.11.3 3.11.4 3.11.4.1 3.11.4.2 3.11.4.3 TITLE PAGE ELECTRICAL POWER................................................................................ 3.8-1 Primary Containment Penetration Conductor Overcurrent Protective Devices................................................................................. 3.8-1 Motor Operated Valves Thermal Overload Protection............................ 3.8.5 Motor Operated Valves (MOV) Thermal Overload Protection -

Continuous............................................................................................. 3.8-5 Motor Operated Valves (MOV) Thermal Overload Protection -

Automatic............................................................................................... 3.8-11 Diesel Generator (DG) Maintenance Activities....................................... 3.8-13 24 voe Electrical Power Subsystem...................................................... 3.8-15 Degraded Voltage Protection.................................................................. 3.8-21 Emergency Switchgear Room Cooling.................................................... 3.8-24 Battery Monitoring and Maintenance Program....................................... 3.8-26 REFUELING OPERATIONS........................................................................ 3.9-1 Decay Time............................................................................................ 3.9-1 Communications.................................................................................... 3.9-2 Refueling Platform.................................................................................. 3.9-3 MISCELLANEOUS..............................................................,....................... 3.10-1 Sealed Source Contamination................................................................ 3.10-1 Shutdown Margin Test RPS Instrumentation.......................................... 3.10-4 Independent Spent Fuel Storage Installation (ISFSI)............................... 3.10-7 Section Not Used................................................................................... 3.10-8 RADIOACTIVE EFFLUENTS....................................................................... 3.11-1 Liquid Effluents...........................................................'........................... 3.11-1 Liquid Effluents Concentration................................................................ 3.11-1 Liquid Effluents Dose............................................................................. 3.11-4 Liquid Radwaste Treatment System....................................................... 3.11-6 Liquid Radwaste Effluent Monitoring Instrumentation............................. 3.11-8 Radioactive Liquid Process Monitoring Instrumentation......................... 3.11-13 Gaseous Effluents.................................................................................. 3.11-17 Dose Rate.............................................................................................. 3.11-17 Dose - Noble Gases............................................................................... 3.11-20 Dose - Iodine, Tritium, and Radionuclides in Particulate Form............... 3.11-21 Gaseous Radwaste Treatment System.................................................. 3.11-22 Ventilation Exhaust Treatment System...........................,....................... 3.11-23 Radioactive Gaseous Effluent Monitoring Instrumentation..................... 3.11-25 Total Dose.............................................................................................. 3.11-33 Radiological Environmental Monitoring.................................................. 3.11-35 Monitoring Program................................................................................ 3.11-35 Land Use Census................................................................................... 3.11-45 lnterlaboratory Comparison Program..................................................... 3.11-47 SUSQUEHANNA - UNIT 2 TOC-3

SUSQUEHANNA STEAM ELECTRIC STATION Rev.29 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)

SECTION 3.12 3.12.1 3.12.2 3.12.3 4.0 4.1 4.2 4.3 4.4 4.5 4.5.1 4.5.2 4.5.3 4.6 4.7 TITLE PAGE LOADS CONTROL PROGRAM................................................................... 3.12-1 Crane Travel - Spent Fuel Storage Pool................................................. 3.12-1 Heavy Loads Requirements................................................................... 3.12.3 Light Loads Requirements..................................................................... 3.12-5 ADMINISTRATIVE CONTROLS..................................................................4.0-1 Organization........................................................................................... 4. 0-1 Reportable Event Action.........................................................................4.0-2 Safety Limit Violation..............................................................................4.0-3 Procedures and Programs.....................................................................4.0-4 Reporting Requirements........................................................................4.0-5 Startup Reports...................................................................................... 4.0-5 Annual Reports...................................................................................... 4.0-6 Section Not Used................................................................................... 4.0-6 Radiation Protection Program................................................................4.0-7 Section Not Used................................................................................... 4.0-8 SUSQUEHANNA - UNIT 2 TOC-4

SUSQUEHANNA STEAM ELECTRIC STATION Rev. 29 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)

SECTION B 3.0 B 3.0 B 3.1.1 B 3.1.2 B 3.1.3 B 3.1.4 B 3.2.1 B 3.3.1 B 3.3.2 B 3.3.3 B 3.3.4 B 3.3.5 B 3.3.6 B 3.3.7 B 3.3.8 B 3.3.9 B3.3.10 B 3.3.11 B 3.3.12 B 3.4.1 B 3.4.2 B 3.4.3 B 3.4.4 B 3.4.5 B 3.4.6 B 3.5.1 B 3.5.2 B 3.5.3 B 3.6.1 B 3.6.2 B 3.6.3 B 3.6.4 TITLE PAGE Technical Requirement for Operation (TRO) Applicability...................... B 3.0-1 Technical Requirement Surveillance (TRS) Applicability........................ 8 3.0-9 Anticipated Transient Without Scram Alternate Rod Injection (ATWS-ARI) lnstrumentation.................................................................. B 3.1-1 Control Rod Drive (CRD) Housing Support............................................ 8 3-. 1-4 Control Rod Block Instrumentation......................................................... 8 3.1-5 Control Rod Scram Accumulators Instrumentation and Check Valve........................................................................................... B 3.1-8 Core Operating Limits Report (COLR).................................................... B 3.2-1 Radiation Monitoring Instrumentation..................................................... 8 3.3-1 Seismic Monitoring lnstrumentation........................................................ B 3.3-2 Meteorological Monitoring Instrumentation............................................. 8 3.3-3 TRM Post-Accident Monitoring Instrumentation..................................... 8 3.3-4 Section Not Used................................................................................... 8 3.3-9 TRM Isolation Actuation Instrumentation................................................ 8 3.3-10 Turbine Overspeed Protection System................................................... B 3.3-14 Section Not Used................................................................................... B 3.3-15 OPRM lnstrumentation........................................................................... B 3.3-18 Reactor Recirculation Pump MG Set Stops............................................ B 3.3-20 MVP Isolation lnstrumentation................................................................ B 3.3-22 Water Monitoring Instrumentation.......................................................... 8 3.3-24 Reactor Coolant System Chemistry........................................................ B 3.4-1 Section Not Used................................................................................... 8 3.4-2 High/Low Pressure Interface Leakage Monitor....................................... B 3.4-4 Reactor Recirculation Flow and Rod Line Limit...................................... B 3.4-5 Reactor Vessel Materials....................................................................... 8 3.4-6 Reactor Recirculation Single Loop Operation (SLO)

Flow Rate Restriction............................................................................. 8 3.4-7 ADS Manual Inhibit................................................................................ B 3.5-1 ECCS, RPV Water Inventory Control, and RCIC System Monitoring Instrumentation..................................................................... 8 3.5-3 Long Term Nitrogen Supply to ADS....................................................... 8 3.5-4 Venting or Purging................................................................................. 8 3.6-1 Suppression Chamber-to-Drywell Vacuum Breaker Position lndication................................................................................................ B 3.6-3 Suppression Pool Alarm Instrumentation............................................... 8 3.6-4 Primary Containment Closed System Boundaries.................................. 8 3.6-6 SUSQUEHANNA - UNIT 2 TOC-5

SUSQUEHANNA STEAM ELECTRIC STATION Rev. 29 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)

SECTION B 3.7.1 B 3.7.2 B 3.7.3.1 B 3.7.3.2 B 3.7.3.3 B 3.7.3.4 B 3.7.3.5 B 3.7.3.6 B 3.7.3.7 B 3.7.3.8 B 3.7.4 B 3.7.5.1 B 3.7.5.2 B 3.7.5.3 B 3.7.6 B 3.7.7 B 3.7.8 B 3.7.9 83.7.10 B 3.7.11 B 3.8.1 B 3.8:2.1 B 3.8.2.2 B 3.8.3 B 3.8.4 B 3.R5 B 3.8.6 B 3.8.7 B.3.9.1 B 3.9.2 B 3.9.3 B 3.10.1 B 3.10.2 B 3.10.3 TITLE PAGE Emergency Service Water System (Shutdown)...................................... B 3.7-1 Ultimate Heat Sink (UHS) Ground Water Level...................................... 8 3.7-2 Fire Suppression Water Supply System................................................. 8 3.7-3 Spray and Sprinkler Systems................................................................. 8 3.7-5 CO2 Systems......................................................................................... 8 3.7-7 Halon Systems....................................................................................... 8 3.7-8 Fire Hose Stations.................................................................................. B 3.7-10 Yard Fire Hydrants and Hydrant Hose Houses....................................... B 3.7-11 Fire Rated Assemblies........................................................................... 8 3.7-12 Fire Detection Instrumentation............................................................... 8 3.7-14 Solid Radwaste System......................................................................... 8 3.7-15 Main Condenser Offgas Hydrogen Monitor............................................ 8 3.7-17 Main Condenser Offgas Explosive Gas Mixture..................................... 8 3.7-19 Liquid Holdup Tanks.............................................................................. 8 3. 7-20 ESSW Pumphouse Ventilation............................................................... 8 3.7-21 Main Condenser Offgas Pretreatment Logarithmic Radiation Monitoring Instrumentation..................................................................... 8 3.7-22 Snubbers................................................................................................ 8 3.7-24.

Control Structure HVAC......................................................................... 8 3.7-31 Spent Fuel Storage Pools...................................................................... 8 3.7-33 Structural Integrity.................................................................................. 8 3.7-36 Primary Containment Penetration Conductor Overcurrent Protective Devices................................................................................. 8 3.8-1 Motor Operated Valves (MOV) Thermal Overload Protection -

Continuous............................................................................................. B 3.8-3 Motor Operated Valves (MOV) Thermal Overload Protection -

Automatic.............................................................................. -................. 8 3.8-4 Diesel Generator (DG) Maintenance Activities....................................... 8 3.8-5 24 VDC Electrical Power Subsystem...................................................... B 3.8-6 Degraded Voltage Protection................................................................. B 3.8-16 Emergency Switchgear Room Cooling.................. *................................. 8 3.8-17 Battery Monitoring and Maintenance Program....................................... 8 3.8-18 Decay Time.......... -................................. _.......................... :...................... B 3.9-1 Communications.................................................................................... 8 3.9-2 Refueling Platform.................................................................................. B 3.9-3 Sealed Source Contamination................................................................ 8 3.10-1 Shutdown Margin Test RPS Instrumentation.......................................... B 3.10-2 Independent Spent Fuel Storage Installation (ISFSI).............................. 8 3.10-4 SUSQUEHANNA - UNIT 2 TOC-6

SUSQUEHANNA STEAM ELECTRIC STATION Rev.29 TABLE OF CONTENTS (TECHNICAL REQUIREMENTS MANUAL)

SECTION TITLE PAGE B 3.11.1.1 Liquid Effluents Concentration................................................................ 8 3.11-1 B 3.11.1.2 Liquid Effluents Dose............................................................................. 8 3.11-4 B 3.11.1.3 Liquid Rad waste Treatment System....................................................... 8 3.11-6 B 3.11.1.4 Liquid Radwaste Effluent Monitoring Instrumentation............................. 8 3.11-7 B3.11.1.5 Radioactive Liquid Process Monitoring Instrumentation......................... 8 3.11-10 B 3.11.2.1 Dose Rate.............................................................................................. B 3.11-12 B 3.11.2.2 Dose-Noble Gases............................................................................... B 3.11-16 B3.11.2.3 Dose - Iodine, Tritium, and Radionuclides in Particulates Form................................................................................... B 3.11-18 B 3.11.2.4 Gaseous Radwaste Treatment System.................................................. 8 3.11-20 B.3.11.2.5 Ventilation Exhaust Treatment System.................................................... 8 3.. 11-21 B 3.11.2.6 Radioactive Gaseous Effluent Monitoring Instrumentation..................... 8 3.11-24 B 3.11.3 Total Dose.............................................................................................. 8 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 lnterlaboratory Comparison Program..................................................... B 3.11-36 B.3.12.1 Crane Travel - Spent Fuel Storage Pool................................................ 8 3.12-1 B.3.12.2 Heavy Loads Requirements................................................................... B 3.12-2 8.3.12.3 Light Loads Requirements..................................................................... 8 3.12-3 SUSQUEHANNA - UNIT 2 TOC-7

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