ML022970126

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Draft - Outlines (Facility Ltr Dtd 08/08/02)
ML022970126
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 09/23/2002
From: Alfonso M
Exelon Nuclear
To: Conte R
NRC/RGN-I/DRS/OSB
Conte R
References
50-277/02-302, 50-278/02-302
Download: ML022970126 (33)
v • d • e


Text

ES-401 BWR RO Examination Outline Printed: 08/07/2002 Facility: Peach Bottom Atomic Power Station Form ES-401-2 Exam Date: 09/23/2002 Exam Level: RO K/A Category Points A3 A4 G Tier Group K1 K2 K3 K4 K5 K6 Al A2 Point A2 IA3 A4 IG Total 2 2 1 13 1 2 3 3

1. ___ ___

3 5 0 1 19 Emergency 2 4 6 Abnormal Plant 3 1 1 1 1 0 0 4 Evolutions Totals 7 10 7 8 2 2 36 Tier I 2 2 3 2 3 3 2 3 2 3 3 28 2.

2 2 2 2 2 2 1 2 2 1 2 1 19 Plant Systems 3 0 0 1 1 0 1 0 0 0 1 0 4 Tier Totals 4 4 6 5 5 5 4 5 3 6 4 51 Cat I Cat 2 Cat 3 Cat 4

3. Generic Knowledge And Abilities 3 4 3 3 13 Note:
1. Attempt to distribute topics among all K/A Categories; select at least one topic from every K/A category within each tier.
2. Actual point totals must match those specified in the table.
3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category tier.

BWR RO( ,mination Outline Facility: L_, Bottom Atomic Power Stat Printed: 08/0( )2 ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Groun 1 l?*rm l*.*_dlfl 1_")

E/APE # E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp. Points 295005 Main Turbine Generator Trip /3 X AA1.04 - Main generator controls 2.7 1 295006 SCRAM / 1 X AK3.03 - Reactor pressure response 3.8 1 295007 High Reactor Pressure / 3 X AK2.06 - PCIS/NSSSS: Plant-Specific 3.5 1 295009 Low Reactor Water Level / 2 X AK2.04 - Reactor water cleanup 2.6 1 295015 Incomplete SCRAM / 1 X AK3.01 - Bypassing rod insertion blocks 3.4 1 295015 Incomplete SCRAM / 1 X AK2.04 - RPS 4.0 1 295024 High Drywell Pressure / 5 X EA1.03 - LPCS: Plant-Specific 4.0 1 295025 High Reactor Pressure / 3 X EKl1.02 - Reactor vessel integrity 4.1 1 295031 Reactor Low Water Level / 2 X EK1.03 - Water level effects on reactor power 3.7 1 295031 Reactor Low Water Level / 2 X EA2.01 - Reactor water level 4.6* 1 295037 SCRAM Condition Present and Reactor Power Above X 2.1.27 - Knowledge of system purpose and/or function. 2.8 1 APRM Downscale or Unknown / 1 500000 High Containment Hydrogen Concentration / 5 X EK3.07 - Operation of drywell vent 3.1 1 500000 High Containment Hydrogen Concentration / 5 X EA2.01 - Hydrogen monitoring system availability 3.1 1 K/A Category Totals: 2 3 3 2 2 1 Group Point Total: 13 1

BWR RO( mination Outline Printed: 08/0( 12 Facility: _*al Bottom Atomic Power Stat ES - 401 Emereencv and Abnormal Plant Evolutions - Tier 1 / Gronn 2 ]L*n t.m 17.*_4fl1_')

E/APE # E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp. Points 295001 Partial or Complete Loss of Forced Core Flow X AA1.07 - Nuclear boiler instrumentation system 3.1 1 Circulation / 1 295002 Loss of Main Condenser Vacuum / 3 X AK3.03 - Reactor feedpump turbine trip: Plant-Specific 3.3 1 295003 Partial or Complete Loss of A.C. Power / 6 X AK2.01 - Station batteries 3.2 1 295003 Partial or Complete Loss of A.C. Power / 6 X AA1.02 - Emergency generators 4.2* 1 295008 High Reactor Water Level / 2 X AK2.08 - Main turbine: Plant-Specific 3.4 1 295012 High Drywell Temperature / 5 X AA1 .01 - Drywell ventilation system 3.5 1 295013 High Suppression Pool Temperature / 5 X AKI.03 - Localized heating 3.0 1 295016 Control Room Abandonment / 7 X AK3.01 - Reactor SCRAM 4.1* 1 295017 High Off-Site Release Rate / 9 X 2.4.4 - Ability to recognize abnormal indications for 4.0 1 system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

295017 High Off-Site Release Rate / 9 X AK2.09 - Condenser air removal system: Plant-Specific 2.8 1 295018 Partial or Complete Loss of Component Cooling X AK1.01 - Effects on component/system operations 3.5 1 Water / 8 295019 Partial or Complete Loss of Instrument Air / 8 X AK3.02 - Standby air compressor operation 3.5 1 295022 Loss of CRD Pumps / 1 X AA1.02 - RPS 3.6 1 295029 High Suppression Pool Water Level / 5 X EK2.08 - Drywell/suppression chamber ventilation 2.6 1 1

BWR RO( 'mination Outline Printed: 08/0( 12 Facility: 1f , Bottom Atomic Power Stat ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-2 E/APE # E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp. Points 295030 Low Suppression Pool Water Level / 5 X EK1.02 - Pump NPSH 3.5 1 295030 Low Suppression Pool Water Level / 5 X EA1.06 - Condensate storage and transfer (make-up to 3.4 1 the suppression pool): Plant-Specific 295033 High Secondary Containment Area Radiation Levels / X EK2.02 - Process radiation monitoring system 3.8 1 9

295038 High Off-Site Release Rate / 9 X EK2.01 - Radwaste 3.1 1 600000 Plant Fire On Site / 8 X AK1.02 - Fire Fighting 2.9 1 K/A Category Totals: 4 6 3 5 0 1 Group Point Total: 19 2

BWR RO( nruination Outline Printed: 08/T( 12 Facility: Bottom Atomic Power Stat ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 3 Form ES-401-2 E/APE /APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp. Points 295021 Loss of Shutdown Cooling / 4 X AK1.04 - Natural circulation 3.6 1 295023 Refueling Accidents / 8 X AA 1.04 - Radiation monitoring equipment 3.4 1 295035 Secondary Containment High Differential Pressure / 5 X EK2.04 - Blow-out panels: Plant-Specific 3.3 1 295036 Secondary Containment High Sump/Area Water X EK3.01 - Emergency depressurization 2.6 1 Level / 5 K/A Category Totals: 1 1 1 1 0 0 Group Point Total: 4 1

( BWR RO F( .ination Outline Printed: 08( " "'002 Facility: Peach Bottom Atomic Power Stat ES - 401 Plant Systems - Tier 2 / Groun 1 Sys/Ev# System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KATopic Imp. Points 201001 Control Rod Drive Hydraulic System / X K5.02 - Flow indication 2.6 1 1

201002 Reactor Manual Control System / 1 X K4.01 - Detection of sequence timer 2.7 1 malfunction 201002 Reactor Manual Control System / 1 X K6.01 - Select matrix power 2.5 1 202002 Recirculation Flow Control System / 1 X K5.01 - Fluid coupling: BWR-3, 4 2.8 1 203000 RHR/LPCI: Injection Mode (Plant X K2.03 - Initiation logic 2.7* 1 Specific) / 2 206000 High Pressure Coolant Injection X 2.1.23 - Ability to perform specific system and 3.9 1 System / 2 integrated plant procedures during different modes of plant operation.

211000 Standby Liquid Control System / 1 X KI.06 - Reactor vessel 3.7 1 211000 Standby Liquid Control System / 1 X K3.01 - tAbility to shutdown the reactor in 4.3* 1 certain conditions 212000 Reactor Protection System / 7 X A4.09 - SCRAM instrument volume level 3.9 1 215005 Average Power Range Monitor/Local X K3.01 - RPS 4.0 1 Power Range Monitor System / 7 215005 Average Power Range Monitor/Local X K4.08 - Sampling of overall core power in each 2.7 1 Power Range Monitor System / 7 APRM (accomplished through LPRM I ---- - assignments and symmetrical rod patterns) 1

BWR RO F_ ýination Outline Printed: 08_-"002 Facility: Peach Bottom Atomic Power Stat ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Ev# System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KATopic Imp. Points 216000 Nuclear Boiler Instrumentation / 7 X A2.14 - Recirculation flow: Design-Specific 2.9 1 217000 Reactor Core Isolation Cooling X K5.04 - Testable check valve operation 2.6 1 System (RCIC) / 2 1 1 217000 Reactor Core Isolation Cooling X K1.01 - Condensate storage and transfer system 3.5 1 System (RCIC) / 2 218000 Automatic Depressurization System / X 2.4.49 - Ability to perform without reference to 4.0 1 3 procedures those actions that require immediate operation of system components and controls.

223001 Primary Containment System and X A1.01 - Drywell temperature 3.5 1 Auxiliaries / 5 223001 Primary Containment System and X A4.05 - Containment/drywell oxygen 3.6 1 Auxiliaries / 5 concentration 223002 Primary Containment Isolation X A2.06 - Containment instrumentation failures 3.0 1 System/Nuclear Steam Supply Shut-Off / 5 223002 Primary Containment Isolation X K3.04 - Reactor building radiation level 3.4 1 System/Nuclear Steam Supply Shut-Off/ 5 239002 Relief/Safety Valves / 3 X K2.01 - SRV solenoids 2.8* 1 239002 Relief/Safety Valves / 3 X A2.01 - Stuck open vacuum breakers 3.0 1 259001 Reactor Feedwater System / 2 X 2.1.27 - Knowledge of system purpose and/or 2.8 1 1____ _1__1_ _ _1_ _1_1__1function. 1_

2

BWR RO k "ination Outline Printed: 08(-C002 Facility: Peach Bottom Atomic Power Stat ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-2 Sys/Ev # System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 259002 Reactor Water Level Control System / X K6.04 - Reactor feedwater flow input 3.1 1 2

259002 Reactor Water Level Control System / X A3.03 - Changes in main steam flow 3.2 1 2

261000 Standby Gas Treatment System / 9 X A4.01 - fOff-site release levels: Plant-Specific 3.2* 1 261000 Standby Gas Treatment System / 9 X A3.03 - Valve operation 3.0 1 264000 Emergency Generators (Diesel/Jet) / 6 X K6.02 - Fuel oil pumps 3.6 1 264000 Emergency Generators (Diesel/Jet) / 6 X A1.09 - Maintaining minimum load on 3.0 1 emergency generator (to prevent reverse power)

K/A Category Totals: 2 2 3 2 3 3 2 3 2 3 3 Group Point Total: 28 3

P BWR RO k ination Outline Printed: 08( '002 Facility: Peach Bottom Atomic Power Stat ES - 401 Plant Systems - Tier 2 / Group 2 Form ES-401-2 Sys/Ev N System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 201006 Rod Worth Minimizer System (RWM) X K6.02 - Reactor water level control input: 2.9 1 (Plant Specific) / 7 P-Spec(Not-BWR6) 204000 Reactor Water Cleanup System / 2 X A3.06 - Lights and alarms 3.1 1 204000 Reactor Water Cleanup System /2 X K3.01 - Reactor water quality 3.2 1 205000 Shutdown Cooling System (RHR X K2.02 - Motor operated valves 2.5* 1 Shutdown Cooling Mode) / 4 1 1 1 1 1 1 205000 Shutdown Cooling System (RHR X A1.02 - SDC/RHR pump flow 3.3 Shutdown Cooling Mode) / 4 215002 Rod Block Monitor System / 7 X 2.4.31 - Knowledge of annunciators alanns and 3.3 1 indications, and use of the response instructions.

219000 RHR/LPCI: Torus/Suppression Pool X A4.02 - Valve lineup 3.7* 1 Cooling Mode / 5 219000 RHR/LPCI: Torus/Suppression Pool X K5.01 - System venting 2.6 1 Cooling Mode / 5 226001 RHR/LPCI: Containment Spray X K4.12 - Prevention of inadvertent containment 2.9 1 System Mode / 5 spray activation 230000 RHR/LPCI: Torus/Suppression Pool X A 1.04 - System flow 3.2* 1 Spray Mode / 5 239001 Main and Reheat Steam System / 3 X K4.01 - Automatic isolation of steam lines 3.8 1 245000 Main Turbine Generator and Auxiliary X K3.02 - Reactor pressure 3.9 1 Systems / 4 1 1_11 _

I

( BWR RO k ination Outline Printed: 08T- "'002 Facility: Peach Bottom Atomic Power Stat ES - 401 Plant Systems - Tier 2 / Groun 2 S. . . . . ..

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Sys/Ev# System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 256000 Reactor Condensate System / 2 X K2.01 - System pumps 2.7* 1 262002 Uninterruptable Power Supply X KI.08 - Containment isolation system: 2.9 1 (A.C./D.C.) / 6- Plant-Specific 272000 Radiation Monitoring System / 7 X A2.06 - Downscale trips 2.8 1 290001 Secondary Containment / 5 X K1.02 - Primary containment system: 3.4 1 Plant-Specific 1 290001 Secondary Containment / 5 X A2.05 - High area temperature 3.1 1 300000 Instrument Air System (IAS) / 8 X K5.13 - Filters 2.9 1 400000 Component Cooling Water System X A4.01 - CCW indications and control 3.1 1 (CCWS) / 8 K/A Category Totals: 2 2 2 2 2 1 2 2 1 2 1 Group Point Total: 19 2

( BWR RO "ination Outline Printed: 089X-" 002 Facility: Peach Bottom Atomic Power Stat ES - 401 Plant Systems - Tier 2 / GrouD 3 Fnrm ES-Afll-1 Sys/Ev # System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 215001 Traversing In-Core Probe / 7 X K6.04 - Primary containment isolation system: 3.1 1 Mark-I&II(Not-BWR1) 1 233000 Fuel Pool Cooling and Clean-up / 9 X A4.06 - System temperature 2.5* 1 234000 Fuel Handling Equipment / 8 X K3.04 - tcore modifications/alterations 2.9 1 290002 Reactor Vessel Internals / 5 X K4.01 - 2/3 core coverage following a DBA 3.7 1 1 1 -LOCA I K/A Category Totals: 0 0 1 1 0 1 0 0 0 1 0 Group Point Total: 4 I

Generic Knowledge and Abilities Outline (Tier 3)

( Printed: 08/07/20(

BWR RO Examination Outline Form ES-401-5 Facility: Peach Bottom Atomic Power Stat Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating 3.7 1 characteristics, reactor behavior, and instrument interpretation.

2.1.18 Ability to make accurate, clear and concise logs, records, status boards, and reports. 2.9 1 2.1.29 Knowledge of how to conduct and verify valve lineups. 3.4 1 Category Total: 3 Equipment Control 2.2.2 Ability to manipulate the console controls as required to operate the facility between 4.0 1 shutdown and designated power levels.

2.2.11 Knowledge of the process for controlling temporary changes. 2.5 1 2.2.22 Knowledge of limiting conditions for operations and safety limits. 3.4 1 2.2.34 Knowledge of the process for determining the internal and external effects on core 2.8 1 reactivity. I_ I Category Total: 4 Radiation Control 2.3.11 Ability to control radiation releases. 2.7 1 2.3.9 Knowledge of the process for performing a containment purge. 2.5 1 2.3.2 Knowledge of facility ALARA program. 2.5 1 Category Total: 3 Emergency Plan 2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support 3.0 1 procedures.

2.4.43 Knowledge of emergency communications systems and techniques. 2.8 1 2.4.25 Knowledge of fire protection procedures. 2.9 1 Category Total: 3 Generic Total: 13 I

ES-401 BWR SRO Examination Outline Printed: 08/07/2002 Facility: Peach Bottom Atomic Power Station Form ES-401-1 Exam Date: 09/23/2002 Exam Level: SRO 9-!

K/A Category Points Tier Group Point Total KI K2 K3 K4 K5 K6 Al1 A2 A3 A4 G 1.

9-,

I 4

p 5 4 iiiiii4 5 4 26 Emergency ~2

& 2 3 3 3 3 3 17 Abnormal Plant Tier *.* **6 Evolutions Totals 7 8 7 8 7 43 4-I-

  • 1 2 2 2 2 2 2 2 2 2 2 3 23 2.

2 1 1 2 1 1 2 1 1 1 0 2 13 Plant Systems 3 0 1 0 1 0 1 0 0 0 0 1 4 Tier Totals 3 4 4 4 3 5 3 3 3 2 6 40 Cat I Cat 2 Cat 3 Cat 4

3. Generic Knowledge And Abilities 4 5 4 4 17 Note:
1. Attempt to distribute topics among all K/A Categories; select at least one topic from every K/A category within each tier.
2. Actual point totals must match those specified in the table.
3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category tier.

I

BWR SR(ý amination Outline Printed: 08/0( 12 Facility: ( ..... i Bottom Atomic Power Stat ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 *nrrn 1*,,*.Aii1-1 E/APE # E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp. Points 295003 Partial or Complete Loss of A.C. Power / 6 X AK2.01 - Station batteries 3.2 1 295003 Partial or Complete Loss of A.C. Power / 6 X AA1.02 - Emergency generators 4.3* 1 295006 SCRAM / 1 X AK3.03 - Reactor pressure response 3.9* 1 295007 High Reactor Pressure / 3 X AA2.02 - Reactor power 4.1

  • 1 295007 High Reactor Pressure / 3 X AK2.06 - PCIS/NSSSS: Plant-Specific 3.7 1 295009 Low Reactor Water Level / 2 X AK2.04 - Reactor water cleanup 2.6 1 295010 High Drywell Pressure / 5 X AA2.03 - Drywell radiation levels 3.6 1 295010 High Drywell Pressure / 5 X 2.1.14 - Knowledge of system status criteria which 3.3 1 require the notification of plant personnel.

295013 High Suppression Pool Temperature / 5 X 2.2.22 - Knowledge of limiting conditions for operations 4.1 1 and safety limits.

295013 High Suppression Pool Temperature / 5 X AK1.03 - Localized heating 3.3 1 295015 Incomplete SCRAM / 1 X AK3.01 - Bypassing rod insertion blocks 3.7 1 295016 Control Room Abandonment / 7 X AK3.01 - Reactor SCRAM 4.2* 1 295017 High Off-Site Release Rate / 9 X 2.4.4 - Ability to recognize abnormal indications for 4.3 1 system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

295017 High Off-Site Release Rate / 9 X AK2.09 - Condenser air removal system: Plant-Specific 2.9 1 I

BWR SRq- amination Outline Printed: 08/0( 12 Facility: L.. i Bottom Atomic Power Stat ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 1 Form ES-401-1 E/APE # E/APE Name / Safety Function KI K2 K3 Al A2 G KA Topic Imp. Points 295023 Refueling Accidents / 8 X AA1.04 - Radiation monitoring equipment 3.7 1 295024 High Drywell Pressure / 5 X EA1.03 - LPCS: Plant-Specific 3.9 1 295025 High Reactor Pressure / 3 X 2.2.22 - Knowledge of limiting conditions for operations 4.1 1 and safety limits.

295025 High Reactor Pressure / 3 X EK1.02 - Reactor vessel integrity 4.2 1 295026 Suppression Pool High Water Temperature / 5 X EA2.03 - Reactor pressure 4.0 1 295030 Low Suppression Pool Water Level / 5 X EK1.02 - Pump NPSH 3.8 1 295030 Low Suppression Pool Water Level / 5 X EA1.06 - Condensate storage and transfer (make-up to 3.4 1 the suppression pool): Plant-Specific 295031 Reactor Low Water Level / 2 X EKI.03 - Water level effects on reactor power 4.1 1 295031 Reactor Low Water Level / 2 X EA2.01 - Reactor water level 4.6* 1 295038 High Off-Site Release Rate / 9 X EK2.01 - Radwaste 3.4 1 500000 High Containment Hydrogen Concentration / 5 X EK3.07 - Operation of drywell vent 3.7 1 500000 High Containment Hydrogen Concentration / 5 X EA2.01 - Hydrogen monitoring system availability 3.5 1 K/A Category Totals: 4 5 445 4 Group Point Total: 26 2

BWR SRq amination Outline Printed: 08/0( 12 Facility: L ... Bottom Atomic Power Stat ES - 401 Emergency and Abnormal Plant Evolutions - Tier 1 / Group 2 Form ES-401-1 E/APE # E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp. Points 295002 Loss of Main Condenser Vacuum / 3 X AK3.03 - Reactor feedpump turbine trip: Plant-Specific 3.3 1 295008 High Reactor Water Level / 2 X AK2.08 - Main turbine: Plant-Specific 3.5 1 295012 High Drywell Temperature / 5 X AA1.01 - Drywell ventilation system 3.6 1 295018 Partial or Complete Loss of Component Cooling X AKI.01 - Effects on component/system operations 3.6 1 Water / 8 295019 Partial or Complete Loss of Instrument Air / 8 X 2.4.49 - Ability to perform without reference to 4.0 1 procedures those actions that require immediate operation of system components and controls.

295019 Partial or Complete Loss of Instrument Air / 8 X AK3.02 - Standby air compressor operation 3.4 1 295020 Inadvertent Containment Isolation / 5 X AA2.05 - Reactor water level 3.6 1 295021 Loss of Shutdown Cooling /4 X AKI.04 - Natural circulation 3.7 1 295022 Loss of CRD Pumps / 1 X AA1.02 - RPS 3.6 1 295028 High Drywell Temperature 5 X 2.1.32 - Ability to explain and apply system limits and 3.8 1 precautions.

295029 High Suppression Pool Water Level / 5 X EK2.08 - Drywell/suppression chamber ventilation 2.9 1 295032 High Secondary Containment Area Temperature / 5 X EA2.02 - Equipment operability 3.5 1 295032 High Secondary Containment Area Temperature / 5 X 2.1.14 - Knowledge of system status criteria which 3.3 1 require the notification of plant personnel.

295033 High Secondary Containment Area Radiation Levels / X EK2.02 - Process radiation monitoring system 4.1 1 9

BWR SRQ- amination Outline Printed: 08/0 ( 12 Facility: 1( _ Bottom Atomic Power Stat i3 " i "Ump.

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E/APE # E/APE Name / Safety Function K1 K2 K3 Al A2 G KA Topic Imp. Points 295034 Secondary Containment Ventilation High Radiation / X EA2.01 - Ventilation radiation levels 4.2 1 9

295036 Secondary Containment High Sump/Area Water X EK3.01 - Emergency depressurization 2.8 1 Level / 5 600000 Plant Fire On Site / 8 X AK1.02 - Fire Fighting 3.1 1 K/A Category Totals: 3 3 3 2 3 3 Group Point Total: 17 2

( BWR SRO 1 iination Outline Printed: 08( "'002 Facility: Peach Bottom Atomic Power Stat ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-1 Sys/Ev # System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 202002 Recirculation Flow Control System / I X 2.1.33 - Ability to recognize indications for 4.0 1 system operating parameters which are entry-level conditions for technical specifications.

202002 Recirculation Flow Control System / 1 X K5.01 - Fluid coupling: BWR-3, 4 2.8 1 203000 RHR/LPCI: Injection Mode (Plant X 2.1.33 - Ability to recognize indications for 4.0 1 Specific) / 2 system operating parameters which are entry-level conditions for technical specifications.

203000 RHR/LPCI: Injection Mode (Plant X K2.03 - Initiation logic 2.9* 1 Specific) / 2 211000 Standby Liquid Control System / 1 X K3.01 - tAbility to shutdown the reactor in 4.4* 1 certain conditions 211000 Standby Liquid Control System! 1 X K1.06 - Reactor vessel 3.7 1 212000 Reactor Protection System / 7 X A4.09 - SCRAM instrument volume level 3.8 1 215005 Average Power Range Monitor/Local X K3.01 - RPS 4.0 1 Power Range Monitor System / 7 215005 Average Power Range Monitor/Local X K4.08 - Sampling of overall core power in each 3.1 1 Power Range Monitor System / 7 APRM (accomplished through LPRM assignments and symmetrical rod patterns) 216000 Nuclear Boiler Instrumentation / 7 X A2.14 - Recirculation flow: Design-Specific 2.9 1

BWR SRO ] nination Outline Printed: 08( '002 Facility: Peach Bottom Atomic Power Stat ES - 401 Plant Systems - Tier 2 / Group 1 Form ES-401-1 Sys/Ev # System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 217000 Reactor Core Isolation Cooling X K5.04 - Testable check valve operation 2.7 1 System (RCIC) / 2 223001 Primary Containment System and X A1.01 - Drywell temperature 3.6 1 Auxiliaries / 5 223001 Primary Containment System and X A4.05 - Containment/drywell oxygen 3.6 1 Auxiliaries / 5 concentration 223002 Primary Containment Isolation X A2.06 - Containment instrumentation failures 3.2 1 System/Nuclear Steam Supply Shut-Off/ 5 226001 RHR/LPCI: Containment Spray X K4.12 - Prevention of inadvertent containment 2.9 1 System Mode / 5 spray activation 239002 Relief/Safety Valves / 3 X K2.01 - SRV solenoids 3.2* 1 239002 Relief/Safety Valves / 3 X 2.2.25 - Knowledge of bases in technical 3.7 1 specifications for limiting conditions for operations and safety limits.

259002 Reactor Water Level Control System / X K6.04 - Reactor feedwater flow input 3.1 1 2 X 1 259002 Reactor Water Level Control System / X A3.03 - Changes in main steam flow 3.2 1 2

261000 Standby Gas Treatment System / 9 X A3.03 - Valve operation 2.9 1 264000 Emergency Generators (Diesel/Jet) / 6 X K6.02 - Fuel oil pumps 3.6 1

( BWR SRO k fination Outline Printed: 08( -1002 Facility: Peach Bottom Atomic Power Stat ES - 401 Plant Systems - Tier 2 /Groun 1 l*nrm 1*'*_Afi1.1 Sys/Ev # System / Evolution Name 1K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 264000 Emergency Generators (Diesel/Jet) / 6 X Al.09 - Maintaining minimum load on 3.1 1 emergency generator (to prevent reverse power) 290001 Secondary Containment / 5 X KI.02 - Primary containment system: 3.6' 1 I I -- I-- IPlant-Specific K/A Category Totals: 2 2 2 2 2 2 2 2 2 2 3 Group Point Total: 23

( BWR SRO 1* iination Outline Printed: 08 -'002 Facility: Peach Bottom Atomic Power Stat ES - 401 Plant Systems - Tier 2 / Groun 2 Fn.rm ES*-4fl1 -1 Sys/Ev # System / Evolution Name KI K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 201002 Reactor Manual Control System / 1 X K4.01 - Detection of sequence timer 2.7 1 malfunction 201002 Reactor Manual Control System / 1 X K6.01 - Select matrix power 2.6 1 201006 Rod Worth Minimizer System (RWM) X K6.02 - Reactor water level control input: 2.9 1 (Plant Specific) / 7 P-Spec(Not-BWR6) 204000 Reactor Water Cleanup System / 2 X A3.06 - Lights and alarms 3.1 1 205000 Shutdown Cooling System (RHR X A1.02 - SDC/RHR pump flow 3.2 1 Shutdown Cooling Mode) / 4 205000 Shutdown Cooling System (RHR X K2.02 - Motor operated valves 2.7* 1 Shutdown Cooling Mode) / 4 214000 Rod Position Information System / 7 X 2.4.6 - Knowledge symptom based EOP 4.0 1 mitigation strategies.

234000 Fuel Handling Equipment / 8 X K3.04 - t"core modifications/alterations 3.8 1 245000 Main Turbine Generator and Auxiliary X K3.02 - Reactor pressure 4.0 1 Systems / 4 259001 Reactor Feedwater System / 2 X 2.4.49 - Ability to perform without reference to 4.0 1 procedures those actions that require immediate operation of system components and controls.

262002 Uninterruptable Power Supply X Ki.08 - Containment isolation system: 3.1 1 (A.C./D.C.) / 6 Plant-Specific I

BWR SRO 'ination

% Outline Printed: 08( '-"1002 Facility: Peach Bottom Atomic Power Stat ES -401 Plant Systems - Tier 2 / Groun 2 ll*nrm 1E,*.dNI-1 Sys/Ev# System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KATopic Imp. Points 272000 Radiation Monitoring System / 7 X A2.06 - Downscale trips 2.9 1 300000 Instrument Air System (IAS) / 8 X K5.13 - Filters 2.9 1 K/A Category Totals: 1 1 2 1 1 2 1 1 1 0 2 Group Point Total: 13 2

BWR SRO 1' iination Outline Printed: 08( 002 Facility: Peach Bottom Atomic Power Stat ES - 401 Plant Systems - Tier 2 / Groun 3 Form F*S-Afll-1 Sys/Ev # System / Evolution Name K1 K2 K3 K4 K5 K6 Al A2 A3 A4 G KA Topic Imp. Points 215001 Traversing In-Core Probe / 7 X K6.04 - Primary containment isolation system: 3.4 1 Mark-I&II(Not-BWR1) 256000 Reactor Condensate System / 2 X K2.01 - System pumps 2.8 1 288000 Plant Ventilation Systems / 9 X 2.4.6 - Knowledge symptom based EOP 4.0 1 mitigation strategies.

290002 Reactor Vessel Internals / 5 X K4.01 - 2/3 core coverage following a DBA 3.9 1 290002 Reactor Vessel Internals / 5 xLOCA K/A Category Totals: 0 1 0 1 0 1 0 0 0 0 1 Group Point Total: 4

Generic Knowledge and Abilities Outline (Tier 3)

Printed: 08/07/20(

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BWR SRO Examination Outline Form ES-401-5 Facility: Peach Bottom Atomic Power Stat Generic Category KA KA Topic Imp. Points Conduct of Operations 2.1.32 Ability to explain and apply system limits and precautions. 3.8 1 2.1.13 Knowledge of facility requirements for controlling vital / controlled access. 2.9 1 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating 4.4 1 characteristics, reactor behavior, and instrument interpretation.

2.1.18 Ability to make accurate, clear and concise logs, records, status boards, and reports. 3.0 1 Category Total: 4 Equipment Control 2.2.29 Knowledge of SRO fuel handling responsibilities. 3.8 1 2.2.21 Knowledge of pre and post maintenance operability requirements. 3.5 1 2.2.2 Ability to manipulate the console controls as required to operate the facility between 3.5 1 shutdown and designated power levels.

2.2.11 Knowledge of the process for controlling temporary changes. 3.4* 1 2.2.22 Knowledge of limiting conditions for operations and safety limits. 4.1 1 Category Total: 5 Radiation Control 2.3.6 Knowledge of the requirements for reviewing and approving release permits. 3.1 1 2.3.10 Ability to perform procedures to reduce excessive levels of radiation and guard against 3.3 1 personnel exposure.

2.3.11 Ability to control radiation releases. 3.2 1 2.3.9 Knowledge of the process for performing a containment purge. 3.4 1 Category Total: 4

Generic Knowledge and Abilities Outline (Tier 3)

Printed: 08/07/20(

BWR SRO Examination Outline Form ES-401-5 Facility: Peach Bottom Atomic Power Stat Generic Category KA KA Topic Imp. Points Emergency Plan 2.4.36 Knowledge of chemistry / health physics tasks during emergency operations. 2.8 1 2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support 4.0 1 procedures.

2.4.43 Knowledge of emergency communications systems and techniques. 3.5 1 2.4.25 Knowledge of fire protection procedures. 3.4 1 Category Total: 4 Generic Total: 17 2

Scenario Outline ES-D-1 Scenario Outline ES-D-1 Simulation Facility Peach Bottom Scenario No. #1 Op Test No.

Examiners Operators CRS PRO URO Scenario The scenario begins with the reactor at 100% power with the 'A' Loop Residual Heat Removal (RHR)

Summary out of service. During the turnover, the crew is directed to swap TBCCW pumps for inspection of a noisy bearing on the 'A' TBCCW pump. Following the swap of TBCCW, an 'A' RPS/PCIS drywell pressure instrument trips upscale resulting in a 'A' Half-scram. The Crew will investigate, evaluate Tech Specs and perform GP-25, Installation of Trips/Isolations to Satisfy Tech Spec/TRM Requirements.

After the Tech Spec determination, the running TBCCW pump trips and results in entry to ON-1 18, Loss of TBCCW. The standby TBCCW pump will not start and the crew must lower power to prevent overheating of the Isophase Bus.

Once power is lowered, a steam leak develops in the drywell requiring entry into OT-101, High Drywell Pressure. The crew will take actions for the rising drywell pressure and will manually scram the reactor. A failed 'B' RPS channel will result in an ATWS. The crew will enter T-101, RPV Control and Alternate Rod Insertion (ARI) will be successful.

With all rods in and the ATWS terminated, the crew will continue to take OT-1 01 actions. The crew will enter T-101 and T-102, Primary Containment Control, when the drywell reaches 2 psig. The crew will spray the torus but a failed drywell spray valve will prevent drywell sprays and drywell temperature will continue to rise, approaching the blowdown limit. The crew will either perform a depressurization to the Main Condenser or a T-1 12, Emergency Blowdown. The scenario may be terminated when the RPV depressurization is performed.

Initial Condition IC-120, 100% power Turnover: See Attached "Shift Turnover" Sheet Event Malfunction Event Event No. No. Type* Description 1 PRO Swap of TBCCW pumps.

N CRS I URO Failed 'A' RPS Drywell pressure instrument (Tech Spec).

2 PRO CRS C PRO Trip of TBCCW pump results in Loss of TBCCW.

3 CRS R URO Power reduction in response to Loss of TBCCW.

4 CRS M URO Steam leak in the drywell.

5 PRO CRS I URO RPS 'B' fails to trip resulting in an ATWS (ARI is successful) 6 CRS C PRO DW Spray Valve fails to open during alignment for containment sprays.

7 CRS

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Scenario Outline ES-D-1 Scenario Outline ES-D-1 Simulation Facility Peach Bottom Scenario No. #2 Op Test No.

Examiners Operators CRS PRO URO Scenario The scenario begins with the reactor at 75% power with power ascension in progress. The 'A' Summary TBCCW pump is out of service for motor repair. The crew is directed to place the third Reactor Feedwater Pump in service and continue to raise power to 90% with reactor recirculation flow.

When reactivity manipulation is observed, an EHC logic problem causes pressure set to drift resulting in a high pressure condition. Once the crew takes actions to restore pressure and the CRS has evaluated Tech Specs, the 'G' Safety Relief Valve opens.

When the RO maximizes torus cooling, the 'A' RHR full flow test valve fails to open and torus conditions continue to degrade resulting in T-102, Primary Containment Control when 95 0 F is reached. When torus temperature cannot be maintained below 105 0 F, an attempt to scram the reactor will discover an electrical ATWS. The Crew will enter T-1 01, RPV Control and T-1 17, Level Power Control to intentionally lower reactor level. When level is lowered, the PCIS logic will fail to isolate the Reactor Water Cleanup system on low level and must be manually isolated.

After Standby Liquid Control is injecting and level/ power are controlled, the ATWS will be terminated by T-213, Scram Solenoid Deenergization. The scenario may be terminated after all control rods are verified inserted.

Initial Condition IC-121, 75% power Turnover: See Attached "Shift Turnover' Sheet Event Malfunction Event Event No. No. Type* Description I N URO Place the third Reactor Feedwater Pump in service.

PRO CRS R URO Raise reactor power with Reactor Recirculation Flow.

2 CRS I URO EHC logic failure causes reactor pressure to rise (Tech Spec).

3 PRO CRS C URO Safety Relief Valve fails open.

4 PRO CRS C PRO 'A' RHR Full Flow Test Valve fails to open.

5 CRS M URO Electrical ATWS.

6 PRO CRS I URO PCIS logic fails to isolate Reactor Water Cleanup.

7 PRO CRS

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Scenario Outline ES-D-1 Scenario Outline ES-D-1 Simulation Facility Peach Bottom Scenario No. #3 Op Test No.

Examiners Operators CRS PRO URO Scenario The scenario begins with the reactor at 100% with 'A' TBCCW pump out of service for motor repair.

Summary The turnover directs the crew to perform a fast start of the E-1 Diesel for the semi-annual surveillance. When the diesel is started, the field flash fails and the Diesel is declared inoperable.

After the Tech Spec determination, turbine vibration occurs due to turbine blade failures. Condenser is breached and air in-leakage results in lowering condenser vacuum. The crew takes actions in accordance with OT-106, Loss of Condenser Vacuum and reduces power in accordance with GP-9, Fast Power Reduction. A reactor scram and loss of Main Turbine and all Reactor Feedwater Pumps will result from the low condenser vacuum. The low reactor level will also cause automatic HPCI and RCIC starts.

A steam leak develops in HPCI and the crew will enter T-103, Secondary Containment Control. HPCI isolation logic fails and HPCI cannot be manually isolated. As Reactor Building conditions degrade, the crew will perform a T-1 12, Emergency Depressurization when max safe temperatures are exceeded in two areas. When ADS valves are opened, the 'K' SRV fails to open and an additional SRV is required to be opened. The scenario may be terminated after the emergency blowdown is in progress.

Initial Condition IC-14, 100% power Turnover: See Attached "Shift Turnover" Sheet Event Malfunction Event Event No. No. Type* Description I N PRO Diesel start for surveillance testing.

CRS I PRO Diesel field fails to flash and is declared inoperable (Tech Spec).

2 CRS C URO Turbine vibration due to turbine blade failures.

3 PRO CRS M URO Air inleakage and lowering condenser vacuum.

4 PRO CRS R URO Fast power reduction due to lowering condenser vacuum.

5 CRS M URO HPCI steam leak in the Reactor Building.

6 PRO CRS I URO HPCI isolation logic failure.

7 PRO CRS C URO ADS SRV fails to open on Emergency Blowdown.

8 PRO CRS

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Scenario Outline ES-D-1 Scenario Outline ES-D-1 Simulation Facility Peach Bottom Scenario No. #4 Op Test No.

Examiners Operators CRS PRO URO Scenario The scenario begins with the plant at 75% power with the "B" RHR Pump Blocked For Motor Summary Replacement. The turnover will direct the crew to perform a Main Turbine Stop Valve Routine Test.

A loss of Feedwater Heaters will require the crew to respond to a positive reactivity addition and reduce power to ensure thermal limits are not exceeded. The crew should recognize and respond to the failure of a RPS Low Vacuum Pressure Transmitter.

Following the Tech Spec determination, a steam leak develops in the Turbine Building. As the steam leak grows in magnitude, the crew should recognize the need to shutdown the plant. During the manual scram, a Reactor Mode Switch failure will require the crew to use the manual pushbuttons or Alternate Rod Insertion (ARI) to terminate the ATWS.

A failure of the Group I isolation will require a manual isolation and the 'D' MSL will fail to isolate. The crew will enter T-104, Radioactive Release and evaluate the release. When the release exceeds General Emergency level, the crew will perform an Emergency Blowdown per T-1 12, Emergency Blowdown. A failure prevents three ADS valves from opening which requires alternate depressurization methods.

Initial Condition IC-123, 75% power Turnover: See Attached "Shift Turnover" Sheet Event Malfunction Event Event No. No. Type* Description URO I N PRO Perform the Main Turbine Stop Valve Routine Test CRS URO 2 Override C PRO Loss Of Extraction Steam To Feedwater Heaters CRS URO 3 R PRO Reduce Reactor Power CRS URO 4 Override I PRO Failure of a Vacuum Transmitter (Tech Spec)

CRS URO 5 MSS10 M PRO Steam Leak In The Turbine Building CRS PCI01 URO Group I Failure To Auto Isolate (Manual works)/Failure Of The "D" 6 Override C PRO MSL To Manually Isolate CRS URO 7 Override I PRO Failure To Scram (Reactor Mode Switch/B RPS Auto Channel Failure)

CRS Override URO Unable To Restore Drywell Nitrogen/Only 2 SRVs Operate On 8 MSS08 C PRO Emergency Blowdown/Depressurization Via Alternate Methods CRS

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

ES-301 Administrative Topics Outline Form ES-301-1 N-Facility: Peach Bottom Unit 2 & 3 Date of Examination: Week of Sept.23, 2002 Examination Level (circle one): RO (_O Operating Test Number: SRO Administrative Describe method of evaluation:

Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Shift Staffing Evaluate Shift Staffing with the current Shift Lineup (JPM)

JPM Alternate Path Plant Parameter Evaluate a P1 Edit and take corrective action in accordance with Verification JPM GP-1 3, Resolution of Thermal Limit Violations (JPM)

A.2 Clearance and Review and approve a clearance prior to maintenance - Alternate Tagging JPM Path (JPM)

A.3 Control of Review and approve a Liquid Radwaste Discharge - Alternate Radiation Path (JPM)

Releases JPM A.4 Emergency Make an Emergency Plan Classification based on plant Classification conditions (JPM)

JPM

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Peach Bottom Unit 2 & 3 - Date of Examination: Week of Sept.23, 2002 Examination Level (circle one): (RO) SRO Operating Test Number: RO Administrative Describe method of evaluation:

Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A. 1 Plant Parameter Verification JPM APRM Scram Margin Check (JPM)

Temporary Procedure Initiate a Temporary Procedure change (JPM)

Change JPM A.2 Familiarity and When an instrument is reported damaged, use P&IDs to Use of P&IDs determine the effect on system operations. (JPM)

JPM A.3 Control of Perform the Plant Reactor Operator (PRO) actions for a Liquid Radiation Radwaste Discharge (JPM)

Releases JPM A.4 Emergency Communication Direct a Site Evacuation for a declared emergency (JPM)

JPM

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: Peach Bottom Unit 2 & 3 Date of Examination: Week of Sept.23, 2002 Exam Level (circle one): RO / SRO(l) / SRO(U) Operating Test No.: RO B.1 Control Room Systems System / JPM Title Type Safety Code* Function

a. Recirculation Flow Control System I Reset a Recirc MG N, A, S 1 Set Scoop Tube Lockup (Alternate Path - Recirc Pump speed inexplicably rises following reset)
b. Reactor Feedwater System / Shutdown a Feedwater Pump (Alternate Path - Feedpump Discharge Check Valve N, A, 2 slams during shutdown)
c. Main Steam System -Main Steam System Recovery N, S, L 3 following a Group 1 Isolation D, S 4
d. High Pressure Coolant Injection / Startup HPCI in the CST to CST Mode
e. PCIS / Raising Main Steam Line Tunnel PCIS Group 1 High D, S 5 Temperature Trip Setpoints
f. Emergency Generators I Unload and shutdown the Diesel D, S 6
g. Standby Gas Treatment I Manually start SBGT System D, S 9 B.2 Facility Walk-Through
a. Control Rod Drive / Low CRD Scram Header Pressure - D, A, R 1 Unit 3 (Alternate Path - Standby Regulator must be placed Abnormal in service)
b. Reactor Core Isolation Cooling / Resetting a RCIC D, R 2 Mechanical Overspeed Trip
c. Main and Reheat Steam System / Closing a Stuck Open D, A, R, L 4 MSIV (Alternate Path - Fuse Failure to Close MSIV) Abnormal
  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: Peach Bottom Unit 2 & 3 Date of Examination: Week of Sept.23, 2002 Exam Level (circle one): RO / SRO(I) / SRO(U) Operating Test No.: SRO(U)

B.1 Control Room Systems System / JPM Title Type Safety Code* Function

a. Main Steam System -Main Steam System Recovery N,S,L 3 following a Group 1 Isolation
b. PCIS / Raising Main Steam Line Tunnel PCIS Group 1 High D, S 5 Temperature Trip Setpoints
c. Emergency Generators / Unload and shutdown the Diesel D, S 6 B.2 Facility Walk-Through
a. Control Rod Drive / Low CRD Scram Header Pressure - D, A, R 1 Unit 3 (Alternate Path - Standby Regulator must be placed Abnormal in service)
b. Main and Reheat Steam System / Closing a Stuck Open D, A, R, L 4 MSIV (Alternate Path - Fuse Failure to Close MSIV) Abnormal
  • Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol room, (S)imulator, (L)ow-Power, (R)CA
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