ML022660573

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Init Exam - 09/2002- Final Outlines
ML022660573
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 03/07/2002
From:
Omaha Public Power District
To:
Office of Nuclear Reactor Regulation
References
50-285/02-301 50-285/02-301
Download: ML022660573 (43)
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Text

Sep 16, 2002 8:31 PM PWR RO Written Examination Outline Summary Page 1 of 1 System/Mode System Title K1 K2 K3 A1 A2 G Points EPE/APE Tier 1 / Group 1 000005 Inoperable/Stuck Control Rod 1 1 000015 Reactor Coolant Pump Malfunctions 1 1 2 000024 Emergency Boration 1 1 2 000062 Loss of Nuclear Service Water 1 1 2 000067 Plant Fire on Site 1 1 2 000068 Control Room Evacuation 1 1 2 000074 Inadequate Core Cooling 1 1 000076 High Reactor Coolant Activity 1 1 CE-A11 RCS Overcooling 1 1 CE-E05 Excess Steam Demand 1 1 2 1 1 2 4 3 5 16 EPE/APE Tier 1 / Group 2 000001 Continuous Rod Withdrawal 1 1 000003 Dropped Control Rod 1 1 2 000007 Reactor Trip 1 1 2 000008 Pressurizer Vapor Space Accident 1 1 2 000009 Small Break LOCA 1 1 000011 Large Break LOCA 1 1 2 000029 Anticipated Transient Without Scram (ATWS) 1 1 000033 Loss of Intermediate Range Nuclear Instrumentation 1 1 000037 Steam Generator Tube Leak 1 1 000038 Steam Generator Tube Rupture 1 1 000059 Accidental Liquid Radwaste Release 1 1 000061 Area Radiation Monitoring (ARM) System Alarms 1 1 CE-E06 Loss of Feedwater 1 1 2 1 3 2 4 5 17 EPE/APE Tier 1 / Group 3 000028 Pressurizer Level Control Malfunction 1 1 000036 Fuel Handling Incidents 1 1 000056 Loss of Off-Site Power 1 1 2 1 3 Grand Total of EPE/APE K&A Selection: 3 2 5 6 9 11 36

PWR RO Written Examination Outline Summary Sep 16, 2002 8:32 PM Page 1 of 2 System/Mode System Title K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G Points Plant System Tier 2 / Group 1 001000 Control Rod Drive System 1 1 2 003000 Reactor Coolant Pump System 1 1 2 004000 Chemical and Volume Control System 1 1 2 013000 Engineered Safety Features Actuation System 1 1 2 015000 Nuclear Instrumentation System 1 1 2 017000 In-Core Temperature Monitor System 1 1 2 022000 Containment Cooling System 1 1 2 059000 Main Feedwater System 1 1 2 061000 Auxiliary / Emergency Feedwater System 1 1 2 068000 Liquid Radwaste System 1 1 2 071000 Waste Gas Disposal System 1 1 2 072000 Area Radiation Monitoring System 1 1 4 1 2 2 1 2 1 1 2 3 4 23 Plant System Tier 2 / Group 2 002000 Reactor Coolant System 1 1 2 006000 Emergency Core Cooling System 1 1 2 010000 Pressurizer Pressure Control System 1 1 011000 Pressurizer Level Control System 1 1 2 012000 Reactor Protection System 1 1 014000 Rod Position Indication System 1 1 016000 Non-Nuclear Instrumentation System 1 1 026000 Containment Spray System 1 1 2 035000 Steam Generator System 1 1 039000 Main and Reheat Steam System 1 1 062000 A.C. Electrical Distribution 1 1 2 064000 Emergency Diesel Generators 1 1 2 075000 Circulating Water System 1 1 079000 Station Air System 1 1 1 1 1 1 1 1 2 4 1 3 4 20 Plant System Tier 2 / Group 3 005000 Residual Heat Removal System 1 1 2 008000 Component Cooling Water System 1 1 041000 Steam Dump System and Turbine Bypass Control 1 1 076000 Service Water System 1 1 2 103000 Containment System 1 1 2

PWR RO Written Examination Outline Summary Sep 16, 2002 8:32 PM Page 2 of 2 System/Mode System Title K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G Points 2 2 1 1 2 8 Grand Total of Plant System K&A Selection: 7 2 5 3 3 3 3 5 4 6 10 51

Sep 16, 2002 8:33 PM PWR RO Written Examination Outline Summary Page 1 of 1 System/Mode System Title Cat 1 Cat 2 Cat 3 Cat 4 Points Generic Knowledge and Abilities Tier 3 000000 Generic Knowledges and Abilities 4 3 2 4 13 4 3 2 4 13 Grand Total of Generic K&A Selection: 4 3 2 4 13

PWR RO Written Examination Outline Sep 16, 2002 8:33 PM Page 1 of 13 System/Mode System Title KA Number Title RO Value 10 CFR 55 Tier 1 Group 1 000005 Inoperable/Stuck Control Rod 2.1.32  : Ability to explain and apply all system limits and precautions. 3.4 41.10 / 43.2 /

45.12 000015 Reactor Coolant Pump Malfunctions 2.4.49  : Ability to perform without reference to procedures those actions that require immediate operation of 4.0 41.10 / 43.2 /

system components and controls. 45.6 000015 Reactor Coolant Pump Malfunctions AA1.05 Ability to operate and / or monitor the following as they apply to the Reactor Coolant Pump 3.8 41.7 / 45.5 / 45.6 Malfunctions (Loss of RC Flow):: RCS flow 000024 Emergency Boration AK1.04 Knowledge of the operational implications of the following concepts as they apply to Emergency 2.8 41.8 / 41.10 /

Boration:: Low temperature limits for boron concentration 45.3 000024 Emergency Boration AK2.03 Knowledge of the interrelations between the Emergency Boration and the following:: Controllers and 2.6 41.7 / 45.7 positioners 000062 Loss of Nuclear Service Water 2.2.25  : Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.2.5 43.2 000062 Loss of Nuclear Service Water AA1.06 Ability to operate and / or monitor the following as they apply to the Loss of Nuclear Service Water:: 2.9 41.7 / 45.5 / 45.6 Control of flow rates to components cooled by the SWS 000067 Plant Fire on Site 2.1.02  : Knowledge of operator responsibilities during all modes of plant operation. 3.0 41.10 / 45.13 000067 Plant Fire on Site AA2.17 Ability to determine and interpret the following as they apply to the Plant Fire on Site:: Systems that 3.5 43.5 / 45.13 may be affected by the fire 000068 Control Room Evacuation AA1.23 Ability to operate and / or monitor the following as they apply to the Control Room Evacuation:: Manual 4.3 41.7 / 45.5 / 45.6 trip of reactor and turbine 000068 Control Room Evacuation AK3.14 Knowledge of the reasons for the following responses as they apply to the Control Room Evacuation::3.2* 41.5 / 41.10 /

Safety injection setpoint of main steam line pressure 45.6 / 45.13

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 2 of 13 System/Mode System Title KA Number Title RO Value 10 CFR 55 000074 Inadequate Core Cooling EA2.04 Ability to determine or interpret the following as they apply to a Inadequate Core Cooling:: Relationship 3.7 43.5 / 45.13 between RCS temperature and main steam pressure 000076 High Reactor Coolant Activity AA2.02 Ability to determine and interpret the following as they apply to the High Reactor Coolant Activity:: 2.8 43.5 / 45.13 Corrective actions required for high fission product activity in RCS CE-A11 RCS Overcooling AA1.02 Ability to operate and / or monitor the following as they apply to the (RCS Overcooling): Operating 3.2 41.7 / 45.5 / 45.6 behavior characteristics of the facility.

CE-E05 Excess Steam Demand 2.4.50  : Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.3 45.3 CE-E05 Excess Steam Demand EK3.04 Knowledge of the reasons for the following responses as they apply to the (Excess Steam Demand): 3.2 41.5 / 41.10 /

RO or SRO function within the control room team as appropriate to the assigned position, in such a 45.6 / 45.13 way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 3 of 13 System/Mode System Title KA Number Title RO Value 10 CFR 55 Tier 1 Group 2 000001 Continuous Rod Withdrawal 2.4.11  : Knowledge of abnormal condition procedures. 3.1 41.10 / 43.5 /

45.13 000003 Dropped Control Rod AK1.15 Knowledge of the operational implications of the following concepts as they apply to Dropped Control 2.8 41.8 / 41.10 /

Rod:: Definition and application of power defect 45.3 000003 Dropped Control Rod AK2.03 Knowledge of the interrelations between the Dropped Control Rod and the following:: Metroscope 3.1* 41.7 / 45.7 000007 Reactor Trip EA1.07 Ability to operate and monitor the following as they apply to a reactor trip:: MT/G trip; verification that 4.3 41.7 / 45.5 / 45.6 the MT/G has been tripped 000007 Reactor Trip EK3.01 Knowledge of the reasons for the following as the apply to a reactor trip:: Actions contained in EOP for4.0 41.5 / 41.10 /

reactor trip 45.6 / 45.13 000008 Pressurizer Vapor Space Accident AA1.05 Ability to operate and / or monitor the following as they apply to the Pressurizer Vapor Space 3.4 41.7 / 45.5 / 45.6 Accident:: LPI System 000008 Pressurizer Vapor Space Accident AA2.12 Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident::3.4 43.5 / 45.13 PZR level indicators 000009 Small Break LOCA EA2.13 Ability to determine or interpret the following as they apply to a small break LOCA:: Charging pump 3.4 43.5 / 45.13 flow indication 000011 Large Break LOCA EA2.03 Ability to determine or interpret the following as they apply to a Large Break LOCA:: Consequences of 3.7 43.5 / 45.13 managing LOCA with loss of CCW 000011 Large Break LOCA EK3.10 Knowledge of the reasons for the following responses as the apply to the Large Break LOCA:: PTS 3.7 41.5 / 41.10 /

limits on RCS pressure and temperature 45.6 / 45.13 000029 Anticipated Transient Without Scram 2.4.50  : Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.3 45.3 (ATWS)

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 4 of 13 System/Mode System Title KA Number Title RO Value 10 CFR 55 000033 Loss of Intermediate Range Nuclear 2.2.25  : Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.2.5 43.2 Instrumentation 000037 Steam Generator Tube Leak 2.1.14  : Knowledge of system status criteria which require the notification of plant personnel. 2.5 43.5 / 45.12 000038 Steam Generator Tube Rupture EA2.07 Ability to determine or interpret the following as they apply to a SGTR:: Plant conditions, from survey 4.4 43.5 / 45.13 of control room indications 000059 Accidental Liquid Radwaste Release AK3.03 Knowledge of the reasons for the following responses as they apply to the Accidental Liquid Radwaste 3.0 41.5 / 41.10 /

Release:: Declaration that a radioactive-liquid monitor is inoperable 45.6 / 45.13 000061 Area Radiation Monitoring (ARM) System 2.4.04  : Ability to recognize abnormal indications for system operating parameters which are entry-level 4.0 41.10 / 43.2 /

Alarms conditions for emergency and abnormal operating procedures. 45.6 CE-E06 Loss of Feedwater EK1.03 Knowledge of the operational implications of the following concepts as they apply to the (Loss of 3.2 41.8 / 41.10 /

Feedwater): Annunciators and conditions indicating signals, and remedial actions associated with the 45.3 (Loss of Feedwater).

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 5 of 13 System/Mode System Title KA Number Title RO Value 10 CFR 55 Tier 1 Group 3 000028 Pressurizer Level Control Malfunction AA2.09 Ability to determine and interpret the following as they apply to the Pressurizer Level Control 2.9 43.5 / 45.13 Malfunctions:: Charging and letdown flow capacities 000036 Fuel Handling Incidents 2.4.50  : Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.3 43.7/45.3 000056 Loss of Off-Site Power AA2.24 Ability to determine and interpret the following as they apply to the Loss of Offsite Power:: CCW pump 3.0 43.5 / 45.13 ammeter, flowmeter and run indicator

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 6 of 13 System/Mode System Title KA Number Title RO Value 10 CFR 55 Tier 2 Group 1 001000 Control Rod Drive System K4.17 Knowledge of CRDS design feature(s) and/or interlock(s) which provide for the following:: Override 2.9* 41.7/43.6 (bypass) for rod bank motion when one rod is bottomed 001000 Control Rod Drive System K6.11 Knowledge of the effect of a loss or malfunction on the following CRDS components:: Location and 2.9 41.7 / 45.7 operation of CRDS fault detection (trouble alarms) and reset system, including rod control annunciator 003000 Reactor Coolant Pump System A4.03 Ability to manually operate and/or monitor in the control room:: RCP lube oil and lift pump motor 2.8 41.7 / 45.5 to controls 45.8 003000 Reactor Coolant Pump System K1.12 Knowledge of the physical connections and/or cause-effect relationships between the RCPS and the 3.0 41.2 to 41.9 /

following systems:: CCWS 45.7 to 45.8 004000 Chemical and Volume Control System A3.04 Ability to monitor automatic operation of the CVCS, including:: VCT pressure control 2.8 41.7 / 45.5 004000 Chemical and Volume Control System K3.02 Knowledge of the effect that a loss or malfunction of the CVCS will have on the following:: PZR LCS 3.7 41.7 / 45.6 013000 Engineered Safety Features Actuation 2.1.02  : Knowledge of operator responsibilities during all modes of plant operation. 3.0 41.10 / 45.13 System 013000 Engineered Safety Features Actuation K1.13 Knowledge of the physical connections and/or cause effect relationships between the ESFAS and the2.8 41.2 to 41.9 /

System following systems:: HVAC 45.7 to 45.8 015000 Nuclear Instrumentation System 2.4.50  : Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.3 45.3 015000 Nuclear Instrumentation System A1.01 Ability to predict and/or monitor changes in parameters to prevent exceeding design limits) associated 3.5 41.5 / 45.5 with operating the NIS controls including:: NIS calibration by heat balance 017000 In-Core Temperature Monitor System 2.1.32  : Ability to explain and apply all system limits and precautions. 3.4 41.10 / 43.2 /

45.12

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 7 of 13 System/Mode System Title KA Number Title RO Value 10 CFR 55 017000 In-Core Temperature Monitor System K3.01 Knowledge of the effect that a loss or malfunction of the ITM system will have on the following:: 3.5* 41.7 / 45.6 Natural circulation indications 022000 Containment Cooling System A3.01 Ability to monitor automatic operation of the CCS, including:: Initiation of safeguards mode of operation 4.1 41.7 / 45.5 022000 Containment Cooling System K1.01 Knowledge of the physical connections and/or cause-effect relationships between the CCS and the 3.5 41.2 to 41.9 /

following systems:: SWS/cooling system 45.7 to 45.8 059000 Main Feedwater System 2.2.22  : Knowledge of limiting conditions for operations and safety limits. 3.4 43.2 / 45.2 059000 Main Feedwater System K1.05 Knowledge of the physical connections and/or cause-effect relationships between the MFW and the 3.1* 41.2 to 41.9 /

following systems:: RCS 45.7 to 45.8 061000 Auxiliary / Emergency Feedwater System A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) 3.2* 41.5 / 43.5 /

based on those predictions, use procedures to correct, control, or mitigate the consequences of those 45.3 / 45.13 malfunctions or operations:: Loss of air to steam supply valve 061000 Auxiliary / Emergency Feedwater System K2.03 Knowledge of bus power supplies to the following:: AFW diesel driven pump 4.0* 41.7 068000 Liquid Radwaste System A4.02 Ability to manually operate and/or monitor in the control room:: Remote radwaste release 3.2* 41.7 / 45.5 to 45.8 068000 Liquid Radwaste System K6.10 Knowledge of the effect of a loss or malfunction on the following will have on the Liquid Radwaste 2.5 41.7 / 45.7 System :: Radiation monitors 071000 Waste Gas Disposal System A4.27 Ability to manually operate and/or monitor in the control room:: Opening and closing of the decay tank 3.0* 41.7 / 45.5 to discharge control valve 45.8 071000 Waste Gas Disposal System K5.04 Knowledge of the operational implication of the following concepts as they apply to the Waste Gas 2.5 41.5 / 45.7 Disposal System:: Relationship of hydrogen/oxygen concentrations to flammability

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 8 of 13 System/Mode System Title KA Number Title RO Value 10 CFR 55 072000 Area Radiation Monitoring System K4.03 Knowledge of ARM system design feature(s) and/or interlock(s) which provide for the following:: Plant 3.2* 41.7 ventilation systems

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 9 of 13 System/Mode System Title KA Number Title RO Value 10 CFR 55 Tier 2 Group 2 002000 Reactor Coolant System 2.1.32  : Ability to explain and apply all system limits and precautions. 3.4 41.10 / 43.2 /

45.12 002000 Reactor Coolant System K6.06 Knowledge of the effect or a loss or malfunction on the following RCS components:: Sensors and 2.5 41.7 / 45.7 detectors 006000 Emergency Core Cooling System A1.16 Ability to predict and/or monitor changes in parameters: RCS temperature, including superheat, 4.1 41.5 / 45.5 saturation, and subcooled 006000 Emergency Core Cooling System K4.05 Knowledge of ECCS design feature(s) and/or interlock(s) which provide for the following:: Autostart of 4.3 41.7 HPI/LPI/SIP 010000 Pressurizer Pressure Control System A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) 3.9 41.5 / 43.5 /

based on those predictions, use procedures to correct, control, or mitigate the consequences of those 45.3 / 45.13 malfunctions or operations:: Spray valve failures 011000 Pressurizer Level Control System A2.10 Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) 3.4 41.5 / 43.5 /

based on those predictions, use procedures to correct, control, or mitigate the consequences of those 45.3 / 45.13 malfunctions or operations:: Failure of PZR level instrument - high 011000 Pressurizer Level Control System K2.01 Knowledge of bus power supplies to the following:: Charging pumps 3.1 41.7 012000 Reactor Protection System K1.04 Knowledge of the physical connections and/or cause effect relationships between the RPS and the 3.2* 41.2 to 41.9 /

following systems:: RPIS 45.7 to 45.8 014000 Rod Position Indication System A4.01 Ability to manually operate and/or monitor in the control room:: Rod selection control 3.3 41.7 / 45.5 to 45.8 016000 Non-Nuclear Instrumentation System K5.01 Knowledge of the operational implication of the following concepts as they apply to the NNIS:: 2.7* 41.5 / 45.7 Separation of control and protection circuits 026000 Containment Spray System 2.1.23  : Ability to perform specific system and integrated plant procedures during all modes of plant operation.3.9 45.2 / 45.6

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 10 of 13 System/Mode System Title KA Number Title RO Value 10 CFR 55 026000 Containment Spray System A1.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated3.6* 41.5 / 45.5 with operating the CSS controls including:: Containment temperature 035000 Steam Generator System A4.02 Ability to manually operate and/or monitor in the control room:: Fill of dry S/G 2.7 41.7 / 45.5 to 45.8 039000 Main and Reheat Steam System A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) 3.4 41.5 / 43.5 /

based on predictions, use procedures to correct, control, or mitigate the consequences of those 45.3 / 45.13 malfunctions or operations:: Indications and alarms for main steam and area radiation monitors (during SGTR) 062000 A.C. Electrical Distribution 2.1.02  : Knowledge of operator responsibilities during all modes of plant operation. 3.0 41.10 / 45.13 062000 A.C. Electrical Distribution A2.06 Ability to (a) predict the impacts of the following malfunctions or operations on the ac distribution 3.4* 41.5 / 43.5 /

system; and (b) based on those predictions, use procedures to correct, control, or mitigate the 45.3 / 45.13 consequences of those malfunctions or operations:: Keeping the safeguards buses electrically separate 064000 Emergency Diesel Generators A3.13 Ability to monitor automatic operation of the ED/G system, including:: Rpm controller/megawatt load 3.0* 41.7 / 45.5 control (breaker-open/breaker-closed effects) 064000 Emergency Diesel Generators K3.03 Knowledge of the effect that a loss or malfunction of the ED/G system will have on the following:: 3.6 41.7 / 45.6 ED/G (manual loads) 075000 Circulating Water System A4.01 Ability to manually operate and/or monitor in the control room:: Emergency/essential SWS pumps 3.2* 41.7 / 45.5 to 45.8 079000 Station Air System 2.4.31  : Knowledge of annunciators alarms and indications, and use of the response instructions. 3.3 41.10 / 45.3

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 11 of 13 System/Mode System Title KA Number Title RO Value 10 CFR 55 Tier 2 Group 3 005000 Residual Heat Removal System K1.11 Knowledge of the physical connections and/or cause-effect relationships between the RHRS and the 3.5 41.2 to 41.9 /

following systems:: RWST 45.7 to 45.8 005000 Residual Heat Removal System K5.01 Knowledge of the operational implications of the following concepts as they apply the RHRS:: Nil 2.6 41.5 / 45.7 ductility transition temperature (brittle fracture) 008000 Component Cooling Water System K3.01 Knowledge of the effect that a loss or malfunction of the CCWS will have on the following:: Loads 3.4 41.7 / 45.6 cooled by CCWS 041000 Steam Dump System and Turbine A3.05 Ability to monitor automatic operation of the SDS, including:: Main steam pressure 2.9* 41.7 / 45.5 Bypass Control 076000 Service Water System 2.1.27  : Knowledge of system purpose and or function. 2.8 41.7 076000 Service Water System K3.05 Knowledge of the effect that a loss or malfunction of the SWS will have on the following:: RHR 3.0* 41.7 / 45.6 components, controls, sensors, indicators, and alarms, including rad monitors 103000 Containment System 2.2.25  : Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.2.5 43.2 103000 Containment System K1.05 Knowledge of the physical connections and/or cause-effect relationships between the containment 2.8* 41.2 to 41.9 /

system and the following systems:: Personnel access hatch and emergency access hatch 45.7 to 45.8

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 12 of 13 System/Mode System Title KA Number Title RO Value 10 CFR 55 Tier 3 Group 4 000000 Generic Knowledges and Abilities 2.1.11  : Knowledge of less than one hour technical specification action statements for systems. 3.0 43.2 / 45.13 000000 Generic Knowledges and Abilities 2.1.23  : Ability to perform specific system and integrated plant procedures during all modes of plant operation.3.9 45.2 / 45.6 000000 Generic Knowledges and Abilities 2.1.24  : Ability to obtain and interpret station electrical and mechanical drawings. 2.8 45.12 / 45.13 000000 Generic Knowledges and Abilities 2.1.33  : Ability to recognize indications for system operating parameters which are entry-level conditions for 3.4 43.2 / 43.3 / 45.3 technical specifications.

000000 Generic Knowledges and Abilities 2.2.01  : Ability to perform pre-startup procedures for the facility, including operating those controls 3.7 45.1 associated with plant equipment that could affect reactivity.

000000 Generic Knowledges and Abilities 2.2.13  : Knowledge of tagging and clearance procedures. 3.6 41.10 / 45.13 000000 Generic Knowledges and Abilities 2.2.23  : Ability to track limiting conditions for operations. 2.6 43.2 / 45.13 000000 Generic Knowledges and Abilities 2.3.01  : Knowledge of 10CFR20 and related facility radiation control requirements. 2.6 41.12 / 43.4 /

45.9 / 45.10 000000 Generic Knowledges and Abilities 2.3.09  : Knowledge of the process for performing a containment purge. 2.5 43.4 / 45.10 000000 Generic Knowledges and Abilities 2.4.26  : Knowledge of facility protection requirements including fire brigade and portable fire fighting 2.9 43.5 / 45.12 equipment usage.

000000 Generic Knowledges and Abilities 2.4.37  : Knowledge of the lines of authority during an emergency. 2.0 45.13

PWR RO Written Examination Outline (Last Page)

Sep 16, 2002 8:33 PM Page 13 of 13 System/Mode System Title KA Number Title RO Value 10 CFR 55 000000 Generic Knowledges and Abilities 2.4.46  : Ability to verify that the alarms are consistent with the plant conditions. 3.5 43.5 / 45.3 /

45.12 000000 Generic Knowledges and Abilities 2.4.48  : Ability to interpret control room indications to verify the status and operation of system, and 3.5 43.5 / 45.12 understand how operator actions and directives affect plant and system conditions.

Sep 16, 2002 8:36 PM PWR SRO Written Examination Outline Summary Page 1 of 2 System/Mode System Title K1 K2 K3 A1 A2 G Points EPE/APE Tier 1 / Group 1 000001 Continuous Rod Withdrawal 1 1 2 000003 Dropped Control Rod 1 1 000005 Inoperable/Stuck Control Rod 2 2 000011 Large Break LOCA 1 1 2 000017 Reactor Coolant Pump Malfunctions (Loss of RC Flow) 1 1 000024 Emergency Boration 1 1 000029 Anticipated Transient Without Scram (ATWS) 1 1 000057 Loss of Vital AC Electrical Instrument Bus 1 1 000059 Accidental Liquid Radwaste Release 1 1 000062 Loss of Nuclear Service Water 1 1 2 000067 Plant Fire on Site 1 1 2 000068 Control Room Evacuation 1 1 2 000074 Inadequate Core Cooling 1 1 000076 High Reactor Coolant Activity 1 1 2 CE-A11 RCS Overcooling 1 1 CE-E05 Excess Steam Demand 1 1 2 3 2 5 4 4 6 24 EPE/APE Tier 1 / Group 2 000007 Reactor Trip 1 1 2 000008 Pressurizer Vapor Space Accident 1 1 2 000009 Small Break LOCA 1 1 2 000022 Loss of Reactor Coolant Makeup 1 1 000033 Loss of Intermediate Range Nuclear Instrumentation 1 1 000037 Steam Generator Tube Leak 1 1 000038 Steam Generator Tube Rupture 1 1 000058 Loss of DC Power 1 1 000060 Accidental Gaseous Radwaste Release 1 1 000061 Area Radiation Monitoring (ARM) System Alarms 1 1 CE-E06 Loss of Feedwater 1 1 2 CE-E09 Functional Recovery 1 1 1 1 2 3 4 5 16 EPE/APE Tier 1 / Group 3 000028 Pressurizer Level Control Malfunction 1 1 000036 Fuel Handling Incidents 1 1 000056 Loss of Off-Site Power 1 1

Sep 16, 2002 8:36 PM PWR SRO Written Examination Outline Summary Page 2 of 2 System/Mode System Title K1 K2 K3 A1 A2 G Points 2 1 3 Grand Total of EPE/APE K&A Selection: 4 3 7 7 10 12 43

PWR SRO Written Examination Outline Summary Sep 16, 2002 8:37 PM Page 1 of 1 System/Mode System Title K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G Points Plant System Tier 2 / Group 1 001000 Control Rod Drive System 1 1 2 003000 Reactor Coolant Pump System 1 1 2 004000 Chemical and Volume Control System 1 1 2 013000 Engineered Safety Features Actuation System 1 1 2 014000 Rod Position Indication System 1 1 015000 Nuclear Instrumentation System 1 1 2 017000 In-Core Temperature Monitor System 1 1 022000 Containment Cooling System 1 1 026000 Containment Spray System 1 1 2 061000 Auxiliary / Emergency Feedwater System 1 1 2 071000 Waste Gas Disposal System 1 1 2 3 1 2 1 1 1 1 1 1 3 4 19 Plant System Tier 2 / Group 2 002000 Reactor Coolant System 1 1 006000 Emergency Core Cooling System 1 1 2 010000 Pressurizer Pressure Control System 1 1 011000 Pressurizer Level Control System 1 1 2 012000 Reactor Protection System 1 1 016000 Non-Nuclear Instrumentation System 1 1 033000 Spent Fuel Pool Cooling System 1 1 035000 Steam Generator System 1 1 039000 Main and Reheat Steam System 1 1 062000 A.C. Electrical Distribution 1 1 064000 Emergency Diesel Generators 1 1 2 075000 Circulating Water System 1 1 079000 Station Air System 1 1 103000 Containment System 1 1 1 1 1 1 1 1 1 3 1 2 4 17 Plant System Tier 2 / Group 3 005000 Residual Heat Removal System 1 1 008000 Component Cooling Water System 1 1 041000 Steam Dump System and Turbine Bypass Control 1 1 076000 Service Water System 1 1 1 1 1 1 4 Grand Total of Plant System K&A Selection: 4 2 4 3 3 2 2 4 3 5 8 40

Sep 16, 2002 8:37 PM PWR SRO Written Examination Outline Summary Page 1 of 1 System/Mode System Title Cat 1 Cat 2 Cat 3 Cat 4 Points Generic Knowledge and Abilities Tier 3 000000 Generic Knowledges and Abilities 5 4 3 5 17 5 4 3 5 17 Grand Total of Generic K&A Selection: 5 4 3 5 17

PWR SRO Written Examination Outline Sep 16, 2002 8:38 PM Page 1 of 13 System/Mode System Title KA Number Title SRO Value 10 CFR 55 Tier 1 Group 1 000001 Continuous Rod Withdrawal 2.4.11  : Knowledge of abnormal condition procedures. 4.0 41.10 / 43.5 /

45.13 000001 Continuous Rod Withdrawal AK2.03 Knowledge of the interrelations between the Continuous Rod Withdrawal and the following:: Sensors2.6 41.7 / 45.7 and detectors 000003 Dropped Control Rod AK2.03 Knowledge of the interrelations between the Dropped Control Rod and the following:: Metroscope 3.2* 41.7 / 45.7 000005 Inoperable/Stuck Control Rod 2.1.14  : Knowledge of system status criteria which require the notification of plant personnel. 3.3 43.5 / 45.12 000005 Inoperable/Stuck Control Rod 2.1.32  : Ability to explain and apply all system limits and precautions. 3.8 41.10 / 43.2 /

45.12 000011 Large Break LOCA EA2.03 Ability to determine or interpret the following as they apply to a Large Break LOCA:: Consequences of4.2 43.5 / 45.13 managing LOCA with loss of CCW 000011 Large Break LOCA EK3.10 Knowledge of the reasons for the following responses as the apply to the Large Break LOCA:: PTS 3.9 41.5 / 41.10 /

limits on RCS pressure and temperature 45.6 / 45.13 000017 Reactor Coolant Pump Malfunctions AK3.06 Knowledge of the reasons for the following responses as they apply to the Reactor Coolant Pump 3.1* 41.5 / 41.10 /

(Loss of RC Flow) Malfunctions (Loss of RC Flow) :: Performance of a core power map, calculations of quadrant power 45.6 / 45.13 tilt, monitoring of core imbalance 000024 Emergency Boration AK1.04 Knowledge of the operational implications of the following concepts as they apply to Emergency 3.6 41.8 / 41.10 /

Boration:: Low temperature limits for boron concentration 45.3 000029 Anticipated Transient Without Scram 2.4.50  : Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.3.3 45.3 (ATWS) 000057 Loss of Vital AC Electrical Instrument Bus AA2.10 Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus:: 2.5 43.5 / 45.13 Turbine load limiter control

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 2 of 13 System/Mode System Title KA Number Title SRO Value 10 CFR 55 000059 Accidental Liquid Radwaste Release AK1.03 Knowledge of the operational implications of the following concepts as they apply to Accidental Liquid 2.9* 41.8 / 41.10 /

Radwaste Release:: Effects of placing a radioactive source near a radiation monitor; in particular, near 45.3 a radioactive-liquid radiation monitor 000062 Loss of Nuclear Service Water 2.2.25  : Knowledge of bases in technical specifications for limiting conditions for operations and safety limits. 3.7 43.2 000062 Loss of Nuclear Service Water AA1.06 Ability to operate and / or monitor the following as they apply to the Loss of Nuclear Service Water:: 2.9 41.7 / 45.5 / 45.6 Control of flow rates to components cooled by the SWS 000067 Plant Fire on Site AA1.02 Ability to operate and / or monitor the following as they apply to the Plant Fire on Site:: Re-installation 2.5* 41.7 / 45.5 / 45.6 of a fire detector 000067 Plant Fire on Site AK3.03 Knowledge of the reasons for the following responses as they apply to the Plant Fire on Site:: Fire 2.5* 41.5 / 41.10 /

detector surveillance test 45.6 / 45.13 000068 Control Room Evacuation AA1.23 Ability to operate and / or monitor the following as they apply to the Control Room Evacuation:: Manual4.4 41.7 / 45.5 / 45.6 trip of reactor and turbine 000068 Control Room Evacuation AK3.14 Knowledge of the reasons for the following responses as they apply to the Control Room Evacuation:: 3.4* 41.5 / 41.10 /

Safety injection setpoint of main steam line pressure 45.6 / 45.13 000074 Inadequate Core Cooling EA2.04 Ability to determine or interpret the following as they apply to a Inadequate Core Cooling:: Relationship4.2 43.5 / 45.13 between RCS temperature and main steam pressure 000076 High Reactor Coolant Activity AA2.02 Ability to determine and interpret the following as they apply to the High Reactor Coolant Activity:: 3.4 43.5 / 45.13 Corrective actions required for high fission product activity in RCS 000076 High Reactor Coolant Activity AK1.02 Knowledge of the operational implications of the following concepts as they apply to High Reactor 2.5 41.8 / 41.10 /

Coolant Activity:: Radiation source term and transport pathway 45.3 CE-A11 RCS Overcooling AA1.02 Ability to operate and / or monitor the following as they apply to the (RCS Overcooling): Operating 3.4 41.7 / 45.5 / 45.6 behavior characteristics of the facility.

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 3 of 13 System/Mode System Title KA Number Title SRO Value 10 CFR 55 CE-E05 Excess Steam Demand 2.4.50  : Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.3.3 45.3 CE-E05 Excess Steam Demand EK3.04 Knowledge of the reasons for the following responses as they apply to the (Excess Steam Demand):3.6 41.5 / 41.10 /

RO or SRO function within the control room team as appropriate to the assigned position, in such a 45.6 / 45.13 way that procedures are adhered to and the limitations in the facilities license and amendments are not violated.

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 4 of 13 System/Mode System Title KA Number Title SRO Value 10 CFR 55 Tier 1 Group 2 000007 Reactor Trip 2.4.50  : Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.3.3 45.3 000007 Reactor Trip EA1.07 Ability to operate and monitor the following as they apply to a reactor trip:: MT/G trip; verification that 4.3 41.7 / 45.5 / 45.6 the MT/G has been tripped 000008 Pressurizer Vapor Space Accident AA1.05 Ability to operate and / or monitor the following as they apply to the Pressurizer Vapor Space 3.3 41.7 / 45.5 / 45.6 Accident:: LPI System 000008 Pressurizer Vapor Space Accident AA2.06 Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident:: 3.6 43.5 / 45.13 PORV logic control under low-pressure conditions 000009 Small Break LOCA EA2.13 Ability to determine or interpret the following as they apply to a small break LOCA:: Charging pump 3.6 43.5 / 45.13 flow indication 000009 Small Break LOCA EK3.10 Knowledge of the reasons for the following responses as the apply to the small break LOCA:: 3.6 41.5 / 41.10 /

Observation of PZR level 45.6 / 45.13 000022 Loss of Reactor Coolant Makeup 2.4.30  : Knowledge of which events related to system operations/status should be reported to outside 3.6 43.5 / 45.11 agencies.

000033 Loss of Intermediate Range Nuclear 2.2.25  : Knowledge of bases in technical specifications for limiting conditions for operations and safety limits. 3.7 43.2 Instrumentation 000037 Steam Generator Tube Leak 2.1.14  : Knowledge of system status criteria which require the notification of plant personnel. 3.3 43.5 / 45.12 000038 Steam Generator Tube Rupture EA2.07 Ability to determine or interpret the following as they apply to a SGTR:: Plant conditions, from survey 4.8 43.5 / 45.13 of control room indications 000058 Loss of DC Power AA2.01 Ability to determine and interpret the following as they apply to the Loss of DC Power:: That a loss of 4.1 43.5 / 45.13 dc power has occurred; verification that substitute power sources have come on line

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 5 of 13 System/Mode System Title KA Number Title SRO Value 10 CFR 55 000060 Accidental Gaseous Radwaste Release AK3.01 Knowledge of the reasons for the following responses as they apply to the Accidental Gaseous 4.2 41.5 / 41.10 /

Radwaste:: Implementation of E-plan 45.6 / 45.13 000061 Area Radiation Monitoring (ARM) System 2.4.04  : Ability to recognize abnormal indications for system operating parameters which are entry-level 4.3 41.10 / 43.2 /

Alarms conditions for emergency and abnormal operating procedures. 45.6 CE-E06 Loss of Feedwater EA1.03 Ability to operate and / or monitor the following as they apply to the (Loss of Feedwater): Desired 4.0 41.7 / 45.5 / 45.6 operating results during abnormal and emergency situations.

CE-E06 Loss of Feedwater EK1.03 Knowledge of the operational implications of the following concepts as they apply to the (Loss of 3.7 41.8 / 41.10 /

Feedwater): Annunciators and conditions indicating signals, and remedial actions associated with the 45.3 (Loss of Feedwater).

CE-E09 Functional Recovery EK2.02 Knowledge of the interrelations between the (Functional Recovery) and the following:: Facility's heat 4.2 41.7 / 45.7 removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 6 of 13 System/Mode System Title KA Number Title SRO Value 10 CFR 55 Tier 1 Group 3 000028 Pressurizer Level Control Malfunction AA2.09 Ability to determine and interpret the following as they apply to the Pressurizer Level Control 3.2 43.5 / 45.13 Malfunctions:: Charging and letdown flow capacities 000036 Fuel Handling Incidents 2.4.50  : Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.3.3 43.7/45.3 000056 Loss of Off-Site Power AA2.24 Ability to determine and interpret the following as they apply to the Loss of Offsite Power:: CCW pump3.1 43.5 / 45.13 ammeter, flowmeter and run indicator

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 7 of 13 System/Mode System Title KA Number Title SRO Value 10 CFR 55 Tier 2 Group 1 001000 Control Rod Drive System 2.1.33  : Ability to recognize indications for system operating parameters which are entry-level conditions for4.0 43.2 / 43.3 / 45.3 technical specifications.

001000 Control Rod Drive System K4.17 Knowledge of CRDS design feature(s) and/or interlock(s) which provide for the following:: Override 3.1* 41.7/43.6 (bypass) for rod bank motion when one rod is bottomed 003000 Reactor Coolant Pump System A4.03 Ability to manually operate and/or monitor in the control room:: RCP lube oil and lift pump motor 2.5 41.7 / 45.5 to controls 45.8 003000 Reactor Coolant Pump System K1.12 Knowledge of the physical connections and/or cause-effect relationships between the RCPS and the3.3 41.2 to 41.9 /

following systems:: CCWS 45.7 to 45.8 004000 Chemical and Volume Control System A3.04 Ability to monitor automatic operation of the CVCS, including:: VCT pressure control 2.9 41.7 / 45.5 004000 Chemical and Volume Control System K3.02 Knowledge of the effect that a loss or malfunction of the CVCS will have on the following:: PZR LCS 4.1 41.7 / 45.6 013000 Engineered Safety Features Actuation 2.1.02  : Knowledge of operator responsibilities during all modes of plant operation. 4.0 41.10 / 45.13 System 013000 Engineered Safety Features Actuation K1.13 Knowledge of the physical connections and/or cause effect relationships between the ESFAS and the 3.1 41.2 to 41.9 /

System following systems:: HVAC 45.7 to 45.8 014000 Rod Position Indication System A4.01 Ability to manually operate and/or monitor in the control room:: Rod selection control 3.1 41.7 / 45.5 to 45.8 015000 Nuclear Instrumentation System 2.4.50  : Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.3.3 45.3 015000 Nuclear Instrumentation System K6.05 Knowledge of the effect of a loss or malfunction on the following will have on the NIS:: Audio 2.6 41.7 / 45.7 indication, including deaf spots in control room and containment

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 8 of 13 System/Mode System Title KA Number Title SRO Value 10 CFR 55 017000 In-Core Temperature Monitor System K3.01 Knowledge of the effect that a loss or malfunction of the ITM system will have on the following:: 3.7* 41.7 / 45.6 Natural circulation indications 022000 Containment Cooling System K1.01 Knowledge of the physical connections and/or cause-effect relationships between the CCS and the 3.7 41.2 to 41.9 /

following systems:: SWS/cooling system 45.7 to 45.8 026000 Containment Spray System 2.1.23  : Ability to perform specific system and integrated plant procedures during all modes of plant operation.

4.0 45.2 / 45.6 026000 Containment Spray System A1.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated3.9 41.5 / 45.5 with operating the CSS controls including:: Containment temperature 061000 Auxiliary / Emergency Feedwater System A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) 3.6* 41.5 / 43.5 /

based on those predictions, use procedures to correct, control, or mitigate the consequences of those 45.3 / 45.13 malfunctions or operations:: Loss of air to steam supply valve 061000 Auxiliary / Emergency Feedwater System K2.03 Knowledge of bus power supplies to the following:: AFW diesel driven pump 3.8* 41.7 071000 Waste Gas Disposal System A4.27 Ability to manually operate and/or monitor in the control room:: Opening and closing of the decay tank 2.7* 41.7 / 45.5 to discharge control valve 45.8 071000 Waste Gas Disposal System K5.04 Knowledge of the operational implication of the following concepts as they apply to the Waste Gas 3.1 41.5 / 45.7 Disposal System:: Relationship of hydrogen/oxygen concentrations to flammability

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 9 of 13 System/Mode System Title KA Number Title SRO Value 10 CFR 55 Tier 2 Group 2 002000 Reactor Coolant System 2.1.32  : Ability to explain and apply all system limits and precautions. 3.8 41.10 / 43.2 /

45.12 006000 Emergency Core Cooling System A1.16 Ability to predict and/or monitor changes in parameters: RCS temperature, including superheat, 4.2 41.5 / 45.5 saturation, and subcooled 006000 Emergency Core Cooling System K6.04 Knowledge of the effect of a loss or malfunction on the following will have on the ECCS:: Breakers, 2.5 41.7 / 45.7 relays and disconnects 010000 Pressurizer Pressure Control System A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) 3.9 41.5 / 43.5 /

based on those predictions, use procedures to correct, control, or mitigate the consequences of those 45.3 / 45.13 malfunctions or operations:: Spray valve failures 011000 Pressurizer Level Control System A2.10 Ability to (a) predict the impacts of the following malfunctions or operations on the PZR LCS; and (b) 3.6 41.5 / 43.5 /

based on those predictions, use procedures to correct, control, or mitigate the consequences of those 45.3 / 45.13 malfunctions or operations:: Failure of PZR level instrument - high 011000 Pressurizer Level Control System K2.01 Knowledge of bus power supplies to the following:: Charging pumps 3.2 41.7 012000 Reactor Protection System K1.04 Knowledge of the physical connections and/or cause effect relationships between the RPS and the 3.3* 41.2 to 41.9 /

following systems:: RPIS 45.7 to 45.8 016000 Non-Nuclear Instrumentation System K5.01 Knowledge of the operational implication of the following concepts as they apply to the NNIS:: 2.8* 41.5 / 45.7 Separation of control and protection circuits 033000 Spent Fuel Pool Cooling System K4.02 Knowledge of design feature(s) and/or interlock(s) which provide for the following:: Maintenance of2.7 41.7 spent fuel cleanliness 035000 Steam Generator System A4.02 Ability to manually operate and/or monitor in the control room:: Fill of dry S/G 2.8 41.7 / 45.5 to 45.8 039000 Main and Reheat Steam System A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) 3.7 41.5 / 43.5 /

based on predictions, use procedures to correct, control, or mitigate the consequences of those 45.3 / 45.13 malfunctions or operations:: Indications and alarms for main steam and area radiation monitors (during SGTR)

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 10 of 13 System/Mode System Title KA Number Title SRO Value 10 CFR 55 062000 A.C. Electrical Distribution 2.1.02  : Knowledge of operator responsibilities during all modes of plant operation. 4.0 41.10 / 45.13 064000 Emergency Diesel Generators A3.13 Ability to monitor automatic operation of the ED/G system, including:: Rpm controller/megawatt load 2.9 41.7 / 45.5 control (breaker-open/breaker-closed effects) 064000 Emergency Diesel Generators K3.03 Knowledge of the effect that a loss or malfunction of the ED/G system will have on the following:: 3.9* 41.7 / 45.6 ED/G (manual loads) 075000 Circulating Water System A4.01 Ability to manually operate and/or monitor in the control room:: Emergency/essential SWS pumps 3.2* 41.7 / 45.5 to 45.8 079000 Station Air System 2.4.31  : Knowledge of annunciators alarms and indications, and use of the response instructions. 3.4 41.10 / 45.3 103000 Containment System 2.2.25  : Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.

3.7 43.2

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 11 of 13 System/Mode System Title KA Number Title SRO Value 10 CFR 55 Tier 2 Group 3 005000 Residual Heat Removal System K5.01 Knowledge of the operational implications of the following concepts as they apply the RHRS:: Nil 2.9 41.5 / 45.7 ductility transition temperature (brittle fracture) 008000 Component Cooling Water System K3.01 Knowledge of the effect that a loss or malfunction of the CCWS will have on the following:: Loads 3.5 41.7 / 45.6 cooled by CCWS 041000 Steam Dump System and Turbine A3.05 Ability to monitor automatic operation of the SDS, including:: Main steam pressure 2.9 41.7 / 45.5 Bypass Control 076000 Service Water System K4.05 Knowledge of SWS design feature(s) and/or interlock(s) which provide for the following:: Service 2.6* 41.7 water train flow and discharge pressure when service water flow to heat exchanger for closed cooling water is throttled

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 12 of 13 System/Mode System Title KA Number Title SRO Value 10 CFR 55 Tier 3 Group 4 000000 Generic Knowledges and Abilities 2.1.10  : Knowledge of conditions and limitations in the facility license. 3.9 43.1 / 45.13 000000 Generic Knowledges and Abilities 2.1.15  : Ability to manage short-term information such as night and standing orders. 3.0 45.12 000000 Generic Knowledges and Abilities 2.1.23  : Ability to perform specific system and integrated plant procedures during all modes of plant operation.

4.0 45.2 / 45.6 000000 Generic Knowledges and Abilities 2.1.24  : Ability to obtain and interpret station electrical and mechanical drawings. 3.1 45.12 / 45.13 000000 Generic Knowledges and Abilities 2.1.33  : Ability to recognize indications for system operating parameters which are entry-level conditions for4.0 43.2 / 43.3 / 45.3 technical specifications.

000000 Generic Knowledges and Abilities 2.2.07  : Knowledge of the process for conducting tests or experiments not described in the safety analysis 3.2 43.3 / 45.13 report.

000000 Generic Knowledges and Abilities 2.2.11  : Knowledge of the process for controlling temporary changes. 3.4* 41.10 / 43.3 /

45.13 000000 Generic Knowledges and Abilities 2.2.23  : Ability to track limiting conditions for operations. 3.8 43.2 / 45.13 000000 Generic Knowledges and Abilities 2.2.24  : Ability to analyze the affect of maintenance activities on LCO status. 3.8 43.2 / 45.13 000000 Generic Knowledges and Abilities 2.3.01  : Knowledge of 10CFR20 and related facility radiation control requirements. 3.0 41.12 / 43.4 /

45.9 / 45.10 000000 Generic Knowledges and Abilities 2.3.08  : Knowledge of the process for performing a planned gaseous radioactive release. 3.2 43.4 / 45.10

PWR SRO Written Examination Outline (Last Page)

Sep 16, 2002 8:38 PM Page 13 of 13 System/Mode System Title KA Number Title SRO Value 10 CFR 55 000000 Generic Knowledges and Abilities 2.3.09  : Knowledge of the process for performing a containment purge. 3.4 43.4 / 45.10 000000 Generic Knowledges and Abilities 2.4.26  : Knowledge of facility protection requirements including fire brigade and portable fire fighting 3.3 43.5 / 45.12 equipment usage.

000000 Generic Knowledges and Abilities 2.4.37  : Knowledge of the lines of authority during an emergency. 3.5 45.13 000000 Generic Knowledges and Abilities 2.4.42  : Knowledge of emergency response facilities. 3.7 45.11 000000 Generic Knowledges and Abilities 2.4.46  : Ability to verify that the alarms are consistent with the plant conditions. 3.6 43.5 / 45.3 /

45.12 000000 Generic Knowledges and Abilities 2.4.48  : Ability to interpret control room indications to verify the status and operation of system, and 3.8 43.5 / 45.12 understand how operator actions and directives affect plant and system conditions.

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Fort Calhoun Date of Examination:

Examination Level: RO Operating Test Number: _____________

Administrative Topic/ Describe method of evaluation:

Subject Description 1. ONE Administrative JPM OR

2. TWO Administrative Questions A.1 Plant parameter Administrative JPM - Calculate critical boron concentration for startup verification Mode changes Administrative JPM - Verify conditions are met for changing modes A.2 Maintenance - Administrative JPM - Time to boil determination shutdown condition A.3 Radiation Control Administrative JPM - RCA Entry and exit with personnel contamination A.4 Emergency Plan Question: Control room operator response to accountability determination Question: Escort response to declaration of an emergency event

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Fort Calhoun Date of Examination:

Examination Level: SRO Operating Test Number: _____________

Administrative Topic/ Describe method of evaluation:

Subject Description 1. ONE Administrative JPM OR

2. TWO Administrative Questions A.1 Plant parameter Administrative JPM - Review Estimated Critical Condition calculation verification Fuel Handling Administrative JPM - Approve Movement of spent fuel assemblies A.2 Tagging and Administrative JPM - Equipment Clearance clearances A.3 Control of Administrative JPM - Authorize containment pressure reduction radiation releases A.4 Emergency Plan Administrative JPM - Emergency Plan classification and Protective Action Recommendations (Security Event)

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: Fort Calhoun Date of Examination:

Exam Level: RO Operating Test No. _____________

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

a. Emergency Boration from the control room E, D, A, S I (004000 A2.14 - RO 3.8/SRO 3.9)
b. Perform monthly Recirculation Actuation Signal Surveillance Test. D, S II (013000 K4.06 - RO 4.0/SRO 4.3)
c. Transfer pressurizer pressure control from manual to automatic D, A, S III (010000 A1.07 - RO 3.7/SRO 3.7)
d. Initiate Shutdown cooling D, L,A, S IV-P (005000 K1.09 - RO 3.6/SRO 3.9) e.Shift 4160V busses between unit auxiliary transformer and house D, S VI service transformer (062000 K1.04 - RO 3.7 /SRO 4.2)
f. Diverse Scram System Surveillance test N, S VII (012000 A4.04 RO 3.3/SRO 3.3)
g. Operate AFW System from AI-179 (aux shutdown panel) D, E IV-S (000068 AA1.03 - RO 4.1/SRO 4.3)

B.2 Facility Walk-Through

a. Align condenser evacuation to AB stack N, E IV-S (000037 AA2.07 - RO 3.1/SRO 3.6)
b. Startup hydrogen purge system D, R, L, E V (028000 A2.02 - RO 3.5/SRO 3.9)
c. Switch Inverter supply from bypass to normal D, A VI (000057 AA1.01 - RO 3.7/SRO 3.7)
  • 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, (E)mergency or abnormal condition

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: Fort Calhoun Date of Examination:

Exam Level: SRO(I) / Operating Test No. _____________

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

a. Emergency Boration from the control room E, D, A, S I (004000 A2.14 - RO 3.8/SRO 3.9)
b. Perform monthly Recirculation Actuation Signal Surveillance Test. D, S II (013000 K4.06 - RO 4.0/SRO 4.3)
c. Fuel handling Incident D, E VIII (000036 AA2.02 - RO 3.4/SRO 4.1)
d. Initiate Shutdown cooling D, L,A, S IV-P (005000 K1.09 - RO 3.6/SRO 3.9) e.Shift 4160V busses between unit auxiliary transformer and house D, S VI service transformer (062000 K1.04 - RO 3.7 /SRO 4.2)
f. Diverse Scram System Surveillance test N, S VII (012000 A4.04 RO 3.3/SRO 3.3)
g. Operate AFW System from AI-179 (aux shutdown panel) D, E IV-S (000068 AA1.03 - RO 4.1/SRO 4.3)

B.2 Facility Walk-Through

a. Align condenser evacuation to AB stack N, E IV-S (000037 AA2.07 - RO 3.1/SRO 3.6)
b. Transfer waste gas from vent header to in service decay tank D, A, R IX (071000 A4.05 - RO 2.6/SRO 2.6)
c. Switch Inverter supply from bypass to normal D, A VI (000057 AA1.01 - RO 3.7/SRO 3.7)
  • 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, (E)mergency or abnormal condition

ES-301 Control Room Systems and Facility Walk-Through Test Outline Form ES-301-2 Facility: Fort Calhoun Date of Examination:

Exam Level: SRO(U) Operating Test No. _____________

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

b.

c.

d. Initiate Shutdown cooling D, L,A, S IV-P (005000 K1.09 - RO 3.6/SRO 3.9) e.
f. Diverse Scram System Surveillance test N, S VII (012000 A4.04 RO 3.3/SRO 3.3) g.

B.2 Facility Walk-Through

a. Align condenser evacuation to AB stack N, E IV-S (000037 AA2.07 - RO 3.1/SRO 3.6)
b. Transfer waste gas from vent header to in service decay tank D, A, R IX (071000 A4.05 - RO 2.6/SRO 2.6)
c. Switch Inverter supply from bypass to normal D, A VI (000057 AA1.01 - RO 3.7/SRO 3.7)
  • 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, (E)mergency or abnormal condition

Appendix D Scenario Outline Form ES-D-2 Facility: Fort Calhoun Scenario No: 2002-1 Op-Test No. ___________

Examiners: _________________________ Operators: _________________________

Initial Conditions: [IC#124] 50% Reactor Power. 940 ppm boron D/G-1 is tagged out of service for generator brush replacement. Waste Monitor Tank, WD-22A, release is in progress.

[Take off CH-1B, Take RM-052 out of service]

[MFP ESF05A] [MFP ESF05B]

Turnover: Return RM-052 to service on the stack. It was taken out of service to install a new tape drive motor for RM-051. The maintenance is now complete. OI-RM-1-CL-B has been completed.

The local ratemeter keyswitch is on.

Event Malf No. Event Event No. Type* Description 1 N Return RM-052 to service 2 [+10] NIS02D I WR NI channel D power supply failure

[MFP NIS02D]

3 [+20] NBWPAC C Running Bearing water pump trips (must start backup) 9A [RFP BCW10A OPEN]

4 [+25] RCP09B C Lower and middle seals on RCP, RC-3B fails RCP10B [MFP RCP09B 100%] [MFP RCP10B 100%]

5 R, N Plant shutdown due to two failed RCS seals 6 [+40] T:L903X I Steam Generator level channel fails low

[COP T:L903X 0%]

7 [+45] GEN01A I Main Generator voltage regulator fails

[MFP GEN01A full 120 sec ramp]

8 [+50] RCS01E M 300 gpm LOCA caused by third seal failure on RC-3B

[MFP RCS01E 0.5%]

9 Preset: C PPLS fails to actuate ESF05A ESF05B

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

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2002-2 Op-Test No. ___________

Examiners: _________________________ Operators: _________________________

Initial Conditions: [IC# 122] 100% Reactor Power. 517 ppm boron D/G-1 is tagged out of service for generator brush replacement.

[Make AC-3A running CCW pump] [MFP ESF06A OFF] [MFP ESF06B OFF]

[COP RSGH042A 100%] [ovr A9 B1U turb diff exp alarm off]

Turnover: Place CCW Pump, AC-3C in service and remove AC-3A from service.

Event Malf No. Event Event No. Type* Description 1 N Rotate CCW pumps

[ will need RFP CCW12A ]

2 [+8] T:P910 I PIC-910 fails high causing turbine bypass valve to open

[ COP T:P910 1000 psi]

3 T:T2897 I Letdown HX CCW outlet temperature transmitter, T-2897, fails

[+13] low. (results in high letdown temperature)

[COP T:T2897 50 ]

4 CRD06 C Dropped Control rod

[+20] [MFP CRD06 rod 1 grp 4 deenergized]

5 R, N Reduce power to 70% due to dropped rod 6 T:P103Y I Controlling pressurizer pressure channel fails high

[+35] [COP T:P103Y]

7 MSS03B M Main steam line break in turbine building

[+40] [MFP MSS03B 20% 60 sec ramp]

8 Preset C SGIS fails to actuate RSGH042A 9 Preset C S/G B MSIV will not close ESF06A,B

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

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2002-3 (spare) Op-Test No. ___________

Examiners: _________________________ Operators: _________________________

Initial Conditions: [IC#2] 100% Power. FW-54 tagged out to replace fuel pump. Power Range NI channel A is out of service due to failed power supply. A Trip units 1,9 and 12 have been bypassed. FIA-236 is failed. In T.S.2.14

[RFP RCP12B close] [File ATWAS PLUS] [RFP AFW25A STOP] [RFP AFW26A local]

[COP T:F236 0%] [MFP NIS07A] [MFP AFW01] [ bypass keys in A TUs 1,9,12]

[A RPS to delta T power]

Turnover: Place CH-1A in service remove CH-1C from service CH-1A packing cooling pump has been operating for 45 minutes.

Event Malf No. Event Event No. Type* Description 1 N Place CH-1A in service remove CH-1C from service 2 [+5] JLB218LL I VCT level fails low causing charging pump suction to realign to SIRWT. [COP JLB218LL fail set]

3 NIS07D I Power Range NI Channel D Fails

[+12] [MFP NIS07D]

4 R, N Power reduction to 70% power.

5 SWD02A,B M Loss of offsite power (both 161KV and 345 KV)

[+40] [MFP SWD02A] [MFP SWD 02B]

6 preset C, M Auto Reactor trip fails (ATWS) 7 preset C Turbine driven AFW pump, FW-10 fails to start.

8 preset C RC-3C breaker does not open. (D/G-1 output breaker does not close)

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

Appendix D Scenario Outline Form ES-D-1 Facility: Fort Calhoun Scenario No: 2002-4 (spare) Op-Test No. ___________

Examiners: _________________________ Operators: _________________________

Initial Conditions: [IC#2]100% Power. FW-54 tagged out to replace fuel pump. Safety Injection Tank SI-6B has a low level alarm.

[Lower level in SI-6B] [Disable autostart of CCW pumps]

Turnover: Raise level in Safety Injection Tank SI-6B Event Malf No. Event Event No. Type* Description 1 N Raise level in Safety Injection tank SI-6B 2 NCCPAC3B C CCW pump trips

[COP NCCPAC3B]

3 SGN01B C Tube leak on steam generator RC-2B

[MFP SGN01B 1%]

4 R, N AOP-5 plant shutdown 5 T:P907 I Steam generator pressure transmitter on RC-2A fails low

[COP T:P907 45.1 psi]

6 CND01 M Loss of condenser vacuum - Reactor Trip

[MFP CND01 100% 300 sec ramp]

7 SGN01A M Steam Generator Tube Rupture - RC-2A

[MFP SGN01A 40%]

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