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)
v • d • e


Text

System/Mode System Title K1 K2 K3 A1 A2 G

Points PWR RO Written Examination Outline Summary Page 1 of 1 Sep 16, 2002 8:31 PM EPE/APE Tier 1 / Group 1 Inoperable/Stuck Control Rod 1

000005 1

Reactor Coolant Pump Malfunctions 1

1 000015 2

Emergency Boration 1

1 000024 2

Loss of Nuclear Service Water 1

1 000062 2

Plant Fire on Site 1

1 000067 2

Control Room Evacuation 1

1 000068 2

Inadequate Core Cooling 1

000074 1

High Reactor Coolant Activity 1

000076 1

RCS Overcooling 1

CE-A11 1

Excess Steam Demand 1

1 CE-E05 2

1 1

2 4

3 5

16 EPE/APE Tier 1 / Group 2 Continuous Rod Withdrawal 1

000001 1

Dropped Control Rod 1

1 000003 2

Reactor Trip 1

1 000007 2

Pressurizer Vapor Space Accident 1

1 000008 2

Small Break LOCA 1

000009 1

Large Break LOCA 1

1 000011 2

Anticipated Transient Without Scram (ATWS) 1 000029 1

Loss of Intermediate Range Nuclear Instrumentation 1

000033 1

Steam Generator Tube Leak 1

000037 1

Steam Generator Tube Rupture 1

000038 1

Accidental Liquid Radwaste Release 1

000059 1

Area Radiation Monitoring (ARM) System Alarms 1

000061 1

Loss of Feedwater 1

CE-E06 1

2 1

3 2

4 5

17 EPE/APE Tier 1 / Group 3 Pressurizer Level Control Malfunction 1

000028 1

Fuel Handling Incidents 1

000036 1

Loss of Off-Site Power 1

000056 1

2 1

3 3

2 5

6 9

11 Grand Total of EPE/APE K&A Selection:

36

PWR RO Written Examination Outline Summary System/Mode System Title K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Page 1 of 2 Sep 16, 2002 8:32 PM Points G

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

2 1

015000 Nuclear Instrumentation System 1

2 1

017000 In-Core Temperature Monitor System 1

2 1

022000 Containment Cooling System 1

1 2

059000 Main Feedwater System 1

2 1

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 23 4

Plant System Tier 2 / Group 2 002000 Reactor Coolant System 1

2 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 014000 Rod Position Indication System 1

1 016000 Non-Nuclear Instrumentation System 1

1 026000 Containment Spray System 1

2 1

035000 Steam Generator System 1

1 039000 Main and Reheat Steam System 1

1 062000 A.C. Electrical Distribution 1

2 1

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 20 4

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

2 1

103000 Containment System 1

2 1

PWR RO Written Examination Outline Summary System/Mode System Title K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Page 2 of 2 Sep 16, 2002 8:32 PM Points G

2 2

1 1

8 2

7 2

5 3

3 3

3 5

4 6

Grand Total of Plant System K&A Selection:

51 10

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

3 2

4 13 4

3 2

4 13 4

3 2

4 Grand Total of Generic K&A Selection:

13

PWR RO Written Examination Outline Sep 16, 2002 8:33 PM Page 1 of 13 System/Mode KA Number Title RO Value System Title 10 CFR 55 Tier 1

Group 1

000005 2.1.32

Ability to explain and apply all system limits and precautions.

3.4 Inoperable/Stuck Control Rod 41.10 / 43.2 /

45.12 000015 2.4.49

Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.

4.0 Reactor Coolant Pump Malfunctions 41.10 / 43.2 /

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

45.3 000024 AK2.03 Knowledge of the interrelations between the Emergency Boration and the following:: Controllers and positioners 2.6 Emergency Boration 41.7 / 45.7 000062 2.2.25

Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.2.5 Loss of Nuclear Service Water 43.2 000062 AA1.06 Ability to operate and / or monitor the following as they apply to the Loss of Nuclear Service Water::

Control of flow rates to components cooled by the SWS 2.9 Loss of Nuclear Service Water 41.7 / 45.5 / 45.6 000067 2.1.02

Knowledge of operator responsibilities during all modes of plant operation.

3.0 Plant Fire on Site 41.10 / 45.13 000067 AA2.17 Ability to determine and interpret the following as they apply to the Plant Fire on Site:: Systems that may be affected by the fire 3.5 Plant Fire on Site 43.5 / 45.13 000068 AA1.23 Ability to operate and / or monitor the following as they apply to the Control Room Evacuation:: Manual trip of reactor and turbine 4.3 Control Room Evacuation 41.7 / 45.5 / 45.6 000068 AK3.14 Knowledge of the reasons for the following responses as they apply to the Control Room Evacuation::

Safety injection setpoint of main steam line pressure 3.2*

Control Room Evacuation 41.5 / 41.10 /

45.6 / 45.13

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 2 of 13 System/Mode KA Number Title RO Value System Title 10 CFR 55 000074 EA2.04 Ability to determine or interpret the following as they apply to a Inadequate Core Cooling:: Relationship between RCS temperature and main steam pressure 3.7 Inadequate Core Cooling 43.5 / 45.13 000076 AA2.02 Ability to determine and interpret the following as they apply to the High Reactor Coolant Activity::

Corrective actions required for high fission product activity in RCS 2.8 High Reactor Coolant Activity 43.5 / 45.13 CE-A11 AA1.02 Ability to operate and / or monitor the following as they apply to the (RCS Overcooling): Operating behavior characteristics of the facility.

3.2 RCS Overcooling 41.7 / 45.5 / 45.6 CE-E05 2.4.50

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

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

3.2 Excess Steam Demand 41.5 / 41.10 /

45.6 / 45.13

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 3 of 13 System/Mode KA Number Title RO Value System Title 10 CFR 55 Tier 1

Group 2

000001 2.4.11

Knowledge of abnormal condition procedures.

3.1 Continuous Rod Withdrawal 41.10 / 43.5 /

45.13 000003 AK1.15 Knowledge of the operational implications of the following concepts as they apply to Dropped Control Rod:: Definition and application of power defect 2.8 Dropped Control Rod 41.8 / 41.10 /

45.3 000003 AK2.03 Knowledge of the interrelations between the Dropped Control Rod and the following:: Metroscope 3.1*

Dropped Control Rod 41.7 / 45.7 000007 EA1.07 Ability to operate and monitor the following as they apply to a reactor trip:: MT/G trip; verification that the MT/G has been tripped 4.3 Reactor Trip 41.7 / 45.5 / 45.6 000007 EK3.01 Knowledge of the reasons for the following as the apply to a reactor trip:: Actions contained in EOP for reactor trip 4.0 Reactor Trip 41.5 / 41.10 /

45.6 / 45.13 000008 AA1.05 Ability to operate and / or monitor the following as they apply to the Pressurizer Vapor Space Accident:: LPI System 3.4 Pressurizer Vapor Space Accident 41.7 / 45.5 / 45.6 000008 AA2.12 Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident::

PZR level indicators 3.4 Pressurizer Vapor Space Accident 43.5 / 45.13 000009 EA2.13 Ability to determine or interpret the following as they apply to a small break LOCA:: Charging pump flow indication 3.4 Small Break LOCA 43.5 / 45.13 000011 EA2.03 Ability to determine or interpret the following as they apply to a Large Break LOCA:: Consequences of managing LOCA with loss of CCW 3.7 Large Break LOCA 43.5 / 45.13 000011 EK3.10 Knowledge of the reasons for the following responses as the apply to the Large Break LOCA:: PTS limits on RCS pressure and temperature 3.7 Large Break LOCA 41.5 / 41.10 /

45.6 / 45.13 000029 2.4.50

Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.3 Anticipated Transient Without Scram (ATWS) 45.3

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 4 of 13 System/Mode KA Number Title RO Value System Title 10 CFR 55 000033 2.2.25

Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.2.5 Loss of Intermediate Range Nuclear Instrumentation 43.2 000037 2.1.14
Knowledge of system status criteria which require the notification of plant personnel.

2.5 Steam Generator Tube Leak 43.5 / 45.12 000038 EA2.07 Ability to determine or interpret the following as they apply to a SGTR:: Plant conditions, from survey of control room indications 4.4 Steam Generator Tube Rupture 43.5 / 45.13 000059 AK3.03 Knowledge of the reasons for the following responses as they apply to the Accidental Liquid Radwaste Release:: Declaration that a radioactive-liquid monitor is inoperable 3.0 Accidental Liquid Radwaste Release 41.5 / 41.10 /

45.6 / 45.13 000061 2.4.04

Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

4.0 Area Radiation Monitoring (ARM) System Alarms 41.10 / 43.2 /

45.6 CE-E06 EK1.03 Knowledge of the operational implications of the following concepts as they apply to the (Loss of Feedwater): Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Feedwater).

3.2 Loss of Feedwater 41.8 / 41.10 /

45.3

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 5 of 13 System/Mode KA Number Title RO Value System Title 10 CFR 55 Tier 1

Group 3

000028 AA2.09 Ability to determine and interpret the following as they apply to the Pressurizer Level Control Malfunctions:: Charging and letdown flow capacities 2.9 Pressurizer Level Control Malfunction 43.5 / 45.13 000036 2.4.50

Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.3 Fuel Handling Incidents 43.7/45.3 000056 AA2.24 Ability to determine and interpret the following as they apply to the Loss of Offsite Power:: CCW pump ammeter, flowmeter and run indicator 3.0 Loss of Off-Site Power 43.5 / 45.13

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 6 of 13 System/Mode KA Number Title RO Value System Title 10 CFR 55 Tier 2

Group 1

001000 K4.17 Knowledge of CRDS design feature(s) and/or interlock(s) which provide for the following:: Override (bypass) for rod bank motion when one rod is bottomed 2.9*

Control Rod Drive System 41.7/43.6 001000 K6.11 Knowledge of the effect of a loss or malfunction on the following CRDS components:: Location and operation of CRDS fault detection (trouble alarms) and reset system, including rod control annunciator 2.9 Control Rod Drive System 41.7 / 45.7 003000 A4.03 Ability to manually operate and/or monitor in the control room:: RCP lube oil and lift pump motor controls 2.8 Reactor Coolant Pump System 41.7 / 45.5 to 45.8 003000 K1.12 Knowledge of the physical connections and/or cause-effect relationships between the RCPS and the following systems:: CCWS 3.0 Reactor Coolant Pump System 41.2 to 41.9 /

45.7 to 45.8 004000 A3.04 Ability to monitor automatic operation of the CVCS, including:: VCT pressure control 2.8 Chemical and Volume Control System 41.7 / 45.5 004000 K3.02 Knowledge of the effect that a loss or malfunction of the CVCS will have on the following:: PZR LCS 3.7 Chemical and Volume Control System 41.7 / 45.6 013000 2.1.02

Knowledge of operator responsibilities during all modes of plant operation.

3.0 Engineered Safety Features Actuation System 41.10 / 45.13 013000 K1.13 Knowledge of the physical connections and/or cause effect relationships between the ESFAS and the following systems:: HVAC 2.8 Engineered Safety Features Actuation System 41.2 to 41.9 /

45.7 to 45.8 015000 2.4.50

Ability to verify system alarm setpoints and operate controls identified in the alarm response manual. 3.3 Nuclear Instrumentation System 45.3 015000 A1.01 Ability to predict and/or monitor changes in parameters to prevent exceeding design limits) associated with operating the NIS controls including:: NIS calibration by heat balance 3.5 Nuclear Instrumentation System 41.5 / 45.5 017000 2.1.32
Ability to explain and apply all system limits and precautions.

3.4 In-Core Temperature Monitor System 41.10 / 43.2 /

45.12

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 7 of 13 System/Mode KA Number Title RO Value System Title 10 CFR 55 017000 K3.01 Knowledge of the effect that a loss or malfunction of the ITM system will have on the following::

Natural circulation indications 3.5*

In-Core Temperature Monitor System 41.7 / 45.6 022000 A3.01 Ability to monitor automatic operation of the CCS, including:: Initiation of safeguards mode of operation 4.1 Containment Cooling System 41.7 / 45.5 022000 K1.01 Knowledge of the physical connections and/or cause-effect relationships between the CCS and the following systems:: SWS/cooling system 3.5 Containment Cooling System 41.2 to 41.9 /

45.7 to 45.8 059000 2.2.22

Knowledge of limiting conditions for operations and safety limits.

3.4 Main Feedwater System 43.2 / 45.2 059000 K1.05 Knowledge of the physical connections and/or cause-effect relationships between the MFW and the following systems:: RCS 3.1*

Main Feedwater System 41.2 to 41.9 /

45.7 to 45.8 061000 A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:: Loss of air to steam supply valve 3.2*

Auxiliary / Emergency Feedwater System 41.5 / 43.5 /

45.3 / 45.13 061000 K2.03 Knowledge of bus power supplies to the following:: AFW diesel driven pump 4.0*

Auxiliary / Emergency Feedwater System 41.7 068000 A4.02 Ability to manually operate and/or monitor in the control room:: Remote radwaste release 3.2*

Liquid Radwaste System 41.7 / 45.5 to 45.8 068000 K6.10 Knowledge of the effect of a loss or malfunction on the following will have on the Liquid Radwaste System :: Radiation monitors 2.5 Liquid Radwaste System 41.7 / 45.7 071000 A4.27 Ability to manually operate and/or monitor in the control room:: Opening and closing of the decay tank discharge control valve 3.0*

Waste Gas Disposal System 41.7 / 45.5 to 45.8 071000 K5.04 Knowledge of the operational implication of the following concepts as they apply to the Waste Gas Disposal System:: Relationship of hydrogen/oxygen concentrations to flammability 2.5 Waste Gas Disposal System 41.5 / 45.7

PWR RO Written Examination Outline (Continued)

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

Area Radiation Monitoring System 41.7

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 9 of 13 System/Mode KA Number Title RO Value System Title 10 CFR 55 Tier 2

Group 2

002000 2.1.32

Ability to explain and apply all system limits and precautions.

3.4 Reactor Coolant System 41.10 / 43.2 /

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

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

45.3 / 45.13 011000 K2.01 Knowledge of bus power supplies to the following:: Charging pumps 3.1 Pressurizer Level Control System 41.7 012000 K1.04 Knowledge of the physical connections and/or cause effect relationships between the RPS and the following systems:: RPIS 3.2*

Reactor Protection System 41.2 to 41.9 /

45.7 to 45.8 014000 A4.01 Ability to manually operate and/or monitor in the control room:: Rod selection control 3.3 Rod Position Indication System 41.7 / 45.5 to 45.8 016000 K5.01 Knowledge of the operational implication of the following concepts as they apply to the NNIS::

Separation of control and protection circuits 2.7*

Non-Nuclear Instrumentation System 41.5 / 45.7 026000 2.1.23

Ability to perform specific system and integrated plant procedures during all modes of plant operation.3.9 Containment Spray System 45.2 / 45.6

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 10 of 13 System/Mode KA Number Title RO Value System Title 10 CFR 55 026000 A1.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including:: Containment temperature 3.6*

Containment Spray System 41.5 / 45.5 035000 A4.02 Ability to manually operate and/or monitor in the control room:: Fill of dry S/G 2.7 Steam Generator System 41.7 / 45.5 to 45.8 039000 A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:: Indications and alarms for main steam and area radiation monitors (during SGTR) 3.4 Main and Reheat Steam System 41.5 / 43.5 /

45.3 / 45.13 062000 2.1.02

Knowledge of operator responsibilities during all modes of plant operation.

3.0 A.C. Electrical Distribution 41.10 / 45.13 062000 A2.06 Ability to (a) predict the impacts of the following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:: Keeping the safeguards buses electrically separate 3.4*

A.C. Electrical Distribution 41.5 / 43.5 /

45.3 / 45.13 064000 A3.13 Ability to monitor automatic operation of the ED/G system, including:: Rpm controller/megawatt load control (breaker-open/breaker-closed effects) 3.0*

Emergency Diesel Generators 41.7 / 45.5 064000 K3.03 Knowledge of the effect that a loss or malfunction of the ED/G system will have on the following::

ED/G (manual loads) 3.6 Emergency Diesel Generators 41.7 / 45.6 075000 A4.01 Ability to manually operate and/or monitor in the control room:: Emergency/essential SWS pumps 3.2*

Circulating Water System 41.7 / 45.5 to 45.8 079000 2.4.31

Knowledge of annunciators alarms and indications, and use of the response instructions.

3.3 Station Air System 41.10 / 45.3

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 11 of 13 System/Mode KA Number Title RO Value System Title 10 CFR 55 Tier 2

Group 3

005000 K1.11 Knowledge of the physical connections and/or cause-effect relationships between the RHRS and the following systems:: RWST 3.5 Residual Heat Removal System 41.2 to 41.9 /

45.7 to 45.8 005000 K5.01 Knowledge of the operational implications of the following concepts as they apply the RHRS:: Nil ductility transition temperature (brittle fracture) 2.6 Residual Heat Removal System 41.5 / 45.7 008000 K3.01 Knowledge of the effect that a loss or malfunction of the CCWS will have on the following:: Loads cooled by CCWS 3.4 Component Cooling Water System 41.7 / 45.6 041000 A3.05 Ability to monitor automatic operation of the SDS, including:: Main steam pressure 2.9*

Steam Dump System and Turbine Bypass Control 41.7 / 45.5 076000 2.1.27

Knowledge of system purpose and or function.

2.8 Service Water System 41.7 076000 K3.05 Knowledge of the effect that a loss or malfunction of the SWS will have on the following:: RHR components, controls, sensors, indicators, and alarms, including rad monitors 3.0*

Service Water System 41.7 / 45.6 103000 2.2.25

Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.2.5 Containment System 43.2 103000 K1.05 Knowledge of the physical connections and/or cause-effect relationships between the containment system and the following systems:: Personnel access hatch and emergency access hatch 2.8*

Containment System 41.2 to 41.9 /

45.7 to 45.8

PWR RO Written Examination Outline (Continued)

Sep 16, 2002 8:33 PM Page 12 of 13 System/Mode KA Number Title RO Value System Title 10 CFR 55 Tier 3

Group 4

000000 2.1.11

Knowledge of less than one hour technical specification action statements for systems.

3.0 Generic Knowledges and Abilities 43.2 / 45.13 000000 2.1.23

Ability to perform specific system and integrated plant procedures during all modes of plant operation.3.9 Generic Knowledges and Abilities 45.2 / 45.6 000000 2.1.24
Ability to obtain and interpret station electrical and mechanical drawings.

2.8 Generic Knowledges and Abilities 45.12 / 45.13 000000 2.1.33

Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.

3.4 Generic Knowledges and Abilities 43.2 / 43.3 / 45.3 000000 2.2.01

Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

3.7 Generic Knowledges and Abilities 45.1 000000 2.2.13

Knowledge of tagging and clearance procedures.

3.6 Generic Knowledges and Abilities 41.10 / 45.13 000000 2.2.23

Ability to track limiting conditions for operations.

2.6 Generic Knowledges and Abilities 43.2 / 45.13 000000 2.3.01

Knowledge of 10CFR20 and related facility radiation control requirements.

2.6 Generic Knowledges and Abilities 41.12 / 43.4 /

45.9 / 45.10 000000 2.3.09

Knowledge of the process for performing a containment purge.

2.5 Generic Knowledges and Abilities 43.4 / 45.10 000000 2.4.26

Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.

2.9 Generic Knowledges and Abilities 43.5 / 45.12 000000 2.4.37

Knowledge of the lines of authority during an emergency.

2.0 Generic Knowledges and Abilities 45.13

PWR RO Written Examination Outline (Last Page)

Sep 16, 2002 8:33 PM Page 13 of 13 System/Mode KA Number Title RO Value System Title 10 CFR 55 000000 2.4.46

Ability to verify that the alarms are consistent with the plant conditions.

3.5 Generic Knowledges and Abilities 43.5 / 45.3 /

45.12 000000 2.4.48

Ability to interpret control room indications to verify the status and operation of system, and understand how operator actions and directives affect plant and system conditions.

3.5 Generic Knowledges and Abilities 43.5 / 45.12

System/Mode System Title K1 K2 K3 A1 A2 G

Points PWR SRO Written Examination Outline Summary Page 1 of 2 Sep 16, 2002 8:36 PM EPE/APE Tier 1 / Group 1 Continuous Rod Withdrawal 1

1 000001 2

Dropped Control Rod 1

000003 1

Inoperable/Stuck Control Rod 2

000005 2

Large Break LOCA 1

1 000011 2

Reactor Coolant Pump Malfunctions (Loss of RC Flow) 1 000017 1

Emergency Boration 1

000024 1

Anticipated Transient Without Scram (ATWS) 1 000029 1

Loss of Vital AC Electrical Instrument Bus 1

000057 1

Accidental Liquid Radwaste Release 1

000059 1

Loss of Nuclear Service Water 1

1 000062 2

Plant Fire on Site 1

1 000067 2

Control Room Evacuation 1

1 000068 2

Inadequate Core Cooling 1

000074 1

High Reactor Coolant Activity 1

1 000076 2

RCS Overcooling 1

CE-A11 1

Excess Steam Demand 1

1 CE-E05 2

3 2

5 4

4 6

24 EPE/APE Tier 1 / Group 2 Reactor Trip 1

1 000007 2

Pressurizer Vapor Space Accident 1

1 000008 2

Small Break LOCA 1

1 000009 2

Loss of Reactor Coolant Makeup 1

000022 1

Loss of Intermediate Range Nuclear Instrumentation 1

000033 1

Steam Generator Tube Leak 1

000037 1

Steam Generator Tube Rupture 1

000038 1

Loss of DC Power 1

000058 1

Accidental Gaseous Radwaste Release 1

000060 1

Area Radiation Monitoring (ARM) System Alarms 1

000061 1

Loss of Feedwater 1

1 CE-E06 2

Functional Recovery 1

CE-E09 1

1 1

2 3

4 5

16 EPE/APE Tier 1 / Group 3 Pressurizer Level Control Malfunction 1

000028 1

Fuel Handling Incidents 1

000036 1

Loss of Off-Site Power 1

000056 1

System/Mode System Title K1 K2 K3 A1 A2 G

Points PWR SRO Written Examination Outline Summary Page 2 of 2 Sep 16, 2002 8:36 PM 2

1 3

4 3

7 7

10 12 Grand Total of EPE/APE K&A Selection:

43

PWR SRO Written Examination Outline Summary System/Mode System Title K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 Page 1 of 1 Sep 16, 2002 8:37 PM Points G

Plant System Tier 2 / Group 1 001000 Control Rod Drive System 1

2 1

003000 Reactor Coolant Pump System 1

1 2

004000 Chemical and Volume Control System 1

1 2

013000 Engineered Safety Features Actuation System 1

2 1

014000 Rod Position Indication System 1

1 015000 Nuclear Instrumentation System 1

2 1

017000 In-Core Temperature Monitor System 1

1 022000 Containment Cooling System 1

1 026000 Containment Spray System 1

2 1

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

19 4

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 17 4

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

4 2

4 3

3 2

2 4

3 5

Grand Total of Plant System K&A Selection:

40 8

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

4 3

5 17 5

4 3

5 17 5

4 3

5 Grand Total of Generic K&A Selection:

17

PWR SRO Written Examination Outline Sep 16, 2002 8:38 PM Page 1 of 13 System/Mode KA Number Title SRO Value System Title 10 CFR 55 Tier 1

Group 1

000001 2.4.11

Knowledge of abnormal condition procedures.

4.0 Continuous Rod Withdrawal 41.10 / 43.5 /

45.13 000001 AK2.03 Knowledge of the interrelations between the Continuous Rod Withdrawal and the following:: Sensors and detectors 2.6 Continuous Rod Withdrawal 41.7 / 45.7 000003 AK2.03 Knowledge of the interrelations between the Dropped Control Rod and the following:: Metroscope 3.2*

Dropped Control Rod 41.7 / 45.7 000005 2.1.14

Knowledge of system status criteria which require the notification of plant personnel.

3.3 Inoperable/Stuck Control Rod 43.5 / 45.12 000005 2.1.32

Ability to explain and apply all system limits and precautions.

3.8 Inoperable/Stuck Control Rod 41.10 / 43.2 /

45.12 000011 EA2.03 Ability to determine or interpret the following as they apply to a Large Break LOCA:: Consequences of managing LOCA with loss of CCW 4.2 Large Break LOCA 43.5 / 45.13 000011 EK3.10 Knowledge of the reasons for the following responses as the apply to the Large Break LOCA:: PTS limits on RCS pressure and temperature 3.9 Large Break LOCA 41.5 / 41.10 /

45.6 / 45.13 000017 AK3.06 Knowledge of the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow) :: Performance of a core power map, calculations of quadrant power tilt, monitoring of core imbalance 3.1*

Reactor Coolant Pump Malfunctions (Loss of RC Flow) 41.5 / 41.10 /

45.6 / 45.13 000024 AK1.04 Knowledge of the operational implications of the following concepts as they apply to Emergency Boration:: Low temperature limits for boron concentration 3.6 Emergency Boration 41.8 / 41.10 /

45.3 000029 2.4.50

Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.3.3 Anticipated Transient Without Scram (ATWS) 45.3 000057 AA2.10 Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus::

Turbine load limiter control 2.5 Loss of Vital AC Electrical Instrument Bus 43.5 / 45.13

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 2 of 13 System/Mode KA Number Title SRO Value System Title 10 CFR 55 000059 AK1.03 Knowledge of the operational implications of the following concepts as they apply to Accidental Liquid Radwaste Release:: Effects of placing a radioactive source near a radiation monitor; in particular, near a radioactive-liquid radiation monitor 2.9*

Accidental Liquid Radwaste Release 41.8 / 41.10 /

45.3 000062 2.2.25

Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.3.7 Loss of Nuclear Service Water 43.2 000062 AA1.06 Ability to operate and / or monitor the following as they apply to the Loss of Nuclear Service Water::

Control of flow rates to components cooled by the SWS 2.9 Loss of Nuclear Service Water 41.7 / 45.5 / 45.6 000067 AA1.02 Ability to operate and / or monitor the following as they apply to the Plant Fire on Site:: Re-installation of a fire detector 2.5*

Plant Fire on Site 41.7 / 45.5 / 45.6 000067 AK3.03 Knowledge of the reasons for the following responses as they apply to the Plant Fire on Site:: Fire detector surveillance test 2.5*

Plant Fire on Site 41.5 / 41.10 /

45.6 / 45.13 000068 AA1.23 Ability to operate and / or monitor the following as they apply to the Control Room Evacuation:: Manual trip of reactor and turbine 4.4 Control Room Evacuation 41.7 / 45.5 / 45.6 000068 AK3.14 Knowledge of the reasons for the following responses as they apply to the Control Room Evacuation::

Safety injection setpoint of main steam line pressure 3.4*

Control Room Evacuation 41.5 / 41.10 /

45.6 / 45.13 000074 EA2.04 Ability to determine or interpret the following as they apply to a Inadequate Core Cooling:: Relationship between RCS temperature and main steam pressure 4.2 Inadequate Core Cooling 43.5 / 45.13 000076 AA2.02 Ability to determine and interpret the following as they apply to the High Reactor Coolant Activity::

Corrective actions required for high fission product activity in RCS 3.4 High Reactor Coolant Activity 43.5 / 45.13 000076 AK1.02 Knowledge of the operational implications of the following concepts as they apply to High Reactor Coolant Activity:: Radiation source term and transport pathway 2.5 High Reactor Coolant Activity 41.8 / 41.10 /

45.3 CE-A11 AA1.02 Ability to operate and / or monitor the following as they apply to the (RCS Overcooling): Operating behavior characteristics of the facility.

3.4 RCS Overcooling 41.7 / 45.5 / 45.6

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 3 of 13 System/Mode KA Number Title SRO Value System Title 10 CFR 55 CE-E05 2.4.50

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

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

3.6 Excess Steam Demand 41.5 / 41.10 /

45.6 / 45.13

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 4 of 13 System/Mode KA Number Title SRO Value System Title 10 CFR 55 Tier 1

Group 2

000007 2.4.50

Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.3.3 Reactor Trip 45.3 000007 EA1.07 Ability to operate and monitor the following as they apply to a reactor trip:: MT/G trip; verification that the MT/G has been tripped 4.3 Reactor Trip 41.7 / 45.5 / 45.6 000008 AA1.05 Ability to operate and / or monitor the following as they apply to the Pressurizer Vapor Space Accident:: LPI System 3.3 Pressurizer Vapor Space Accident 41.7 / 45.5 / 45.6 000008 AA2.06 Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident::

PORV logic control under low-pressure conditions 3.6 Pressurizer Vapor Space Accident 43.5 / 45.13 000009 EA2.13 Ability to determine or interpret the following as they apply to a small break LOCA:: Charging pump flow indication 3.6 Small Break LOCA 43.5 / 45.13 000009 EK3.10 Knowledge of the reasons for the following responses as the apply to the small break LOCA::

Observation of PZR level 3.6 Small Break LOCA 41.5 / 41.10 /

45.6 / 45.13 000022 2.4.30

Knowledge of which events related to system operations/status should be reported to outside agencies.

3.6 Loss of Reactor Coolant Makeup 43.5 / 45.11 000033 2.2.25

Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.3.7 Loss of Intermediate Range Nuclear Instrumentation 43.2 000037 2.1.14
Knowledge of system status criteria which require the notification of plant personnel.

3.3 Steam Generator Tube Leak 43.5 / 45.12 000038 EA2.07 Ability to determine or interpret the following as they apply to a SGTR:: Plant conditions, from survey of control room indications 4.8 Steam Generator Tube Rupture 43.5 / 45.13 000058 AA2.01 Ability to determine and interpret the following as they apply to the Loss of DC Power:: That a loss of dc power has occurred; verification that substitute power sources have come on line 4.1 Loss of DC Power 43.5 / 45.13

PWR SRO Written Examination Outline (Continued)

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

45.6 / 45.13 000061 2.4.04

Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.

4.3 Area Radiation Monitoring (ARM) System Alarms 41.10 / 43.2 /

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

4.0 Loss of Feedwater 41.7 / 45.5 / 45.6 CE-E06 EK1.03 Knowledge of the operational implications of the following concepts as they apply to the (Loss of Feedwater): Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Feedwater).

3.7 Loss of Feedwater 41.8 / 41.10 /

45.3 CE-E09 EK2.02 Knowledge of the interrelations between the (Functional Recovery) and the following:: Facility's heat 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.

4.2 Functional Recovery 41.7 / 45.7

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 6 of 13 System/Mode KA Number Title SRO Value System Title 10 CFR 55 Tier 1

Group 3

000028 AA2.09 Ability to determine and interpret the following as they apply to the Pressurizer Level Control Malfunctions:: Charging and letdown flow capacities 3.2 Pressurizer Level Control Malfunction 43.5 / 45.13 000036 2.4.50

Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.3.3 Fuel Handling Incidents 43.7/45.3 000056 AA2.24 Ability to determine and interpret the following as they apply to the Loss of Offsite Power:: CCW pump ammeter, flowmeter and run indicator 3.1 Loss of Off-Site Power 43.5 / 45.13

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 7 of 13 System/Mode KA Number Title SRO Value System Title 10 CFR 55 Tier 2

Group 1

001000 2.1.33

Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.

4.0 Control Rod Drive System 43.2 / 43.3 / 45.3 001000 K4.17 Knowledge of CRDS design feature(s) and/or interlock(s) which provide for the following:: Override (bypass) for rod bank motion when one rod is bottomed 3.1*

Control Rod Drive System 41.7/43.6 003000 A4.03 Ability to manually operate and/or monitor in the control room:: RCP lube oil and lift pump motor controls 2.5 Reactor Coolant Pump System 41.7 / 45.5 to 45.8 003000 K1.12 Knowledge of the physical connections and/or cause-effect relationships between the RCPS and the following systems:: CCWS 3.3 Reactor Coolant Pump System 41.2 to 41.9 /

45.7 to 45.8 004000 A3.04 Ability to monitor automatic operation of the CVCS, including:: VCT pressure control 2.9 Chemical and Volume Control System 41.7 / 45.5 004000 K3.02 Knowledge of the effect that a loss or malfunction of the CVCS will have on the following:: PZR LCS 4.1 Chemical and Volume Control System 41.7 / 45.6 013000 2.1.02

Knowledge of operator responsibilities during all modes of plant operation.

4.0 Engineered Safety Features Actuation System 41.10 / 45.13 013000 K1.13 Knowledge of the physical connections and/or cause effect relationships between the ESFAS and the following systems:: HVAC 3.1 Engineered Safety Features Actuation System 41.2 to 41.9 /

45.7 to 45.8 014000 A4.01 Ability to manually operate and/or monitor in the control room:: Rod selection control 3.1 Rod Position Indication System 41.7 / 45.5 to 45.8 015000 2.4.50

Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.3.3 Nuclear Instrumentation System 45.3 015000 K6.05 Knowledge of the effect of a loss or malfunction on the following will have on the NIS:: Audio indication, including deaf spots in control room and containment 2.6 Nuclear Instrumentation System 41.7 / 45.7

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 8 of 13 System/Mode KA Number Title SRO Value System Title 10 CFR 55 017000 K3.01 Knowledge of the effect that a loss or malfunction of the ITM system will have on the following::

Natural circulation indications 3.7*

In-Core Temperature Monitor System 41.7 / 45.6 022000 K1.01 Knowledge of the physical connections and/or cause-effect relationships between the CCS and the following systems:: SWS/cooling system 3.7 Containment Cooling System 41.2 to 41.9 /

45.7 to 45.8 026000 2.1.23

Ability to perform specific system and integrated plant procedures during all modes of plant operation.4.0 Containment Spray System 45.2 / 45.6 026000 A1.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including:: Containment temperature 3.9 Containment Spray System 41.5 / 45.5 061000 A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:: Loss of air to steam supply valve 3.6*

Auxiliary / Emergency Feedwater System 41.5 / 43.5 /

45.3 / 45.13 061000 K2.03 Knowledge of bus power supplies to the following:: AFW diesel driven pump 3.8*

Auxiliary / Emergency Feedwater System 41.7 071000 A4.27 Ability to manually operate and/or monitor in the control room:: Opening and closing of the decay tank discharge control valve 2.7*

Waste Gas Disposal System 41.7 / 45.5 to 45.8 071000 K5.04 Knowledge of the operational implication of the following concepts as they apply to the Waste Gas Disposal System:: Relationship of hydrogen/oxygen concentrations to flammability 3.1 Waste Gas Disposal System 41.5 / 45.7

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 9 of 13 System/Mode KA Number Title SRO Value System Title 10 CFR 55 Tier 2

Group 2

002000 2.1.32

Ability to explain and apply all system limits and precautions.

3.8 Reactor Coolant System 41.10 / 43.2 /

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

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

45.3 / 45.13 011000 K2.01 Knowledge of bus power supplies to the following:: Charging pumps 3.2 Pressurizer Level Control System 41.7 012000 K1.04 Knowledge of the physical connections and/or cause effect relationships between the RPS and the following systems:: RPIS 3.3*

Reactor Protection System 41.2 to 41.9 /

45.7 to 45.8 016000 K5.01 Knowledge of the operational implication of the following concepts as they apply to the NNIS::

Separation of control and protection circuits 2.8*

Non-Nuclear Instrumentation System 41.5 / 45.7 033000 K4.02 Knowledge of design feature(s) and/or interlock(s) which provide for the following:: Maintenance of spent fuel cleanliness 2.7 Spent Fuel Pool Cooling System 41.7 035000 A4.02 Ability to manually operate and/or monitor in the control room:: Fill of dry S/G 2.8 Steam Generator System 41.7 / 45.5 to 45.8 039000 A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the MRSS; and (b) based on predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:: Indications and alarms for main steam and area radiation monitors (during SGTR) 3.7 Main and Reheat Steam System 41.5 / 43.5 /

45.3 / 45.13

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 10 of 13 System/Mode KA Number Title SRO Value System Title 10 CFR 55 062000 2.1.02

Knowledge of operator responsibilities during all modes of plant operation.

4.0 A.C. Electrical Distribution 41.10 / 45.13 064000 A3.13 Ability to monitor automatic operation of the ED/G system, including:: Rpm controller/megawatt load control (breaker-open/breaker-closed effects) 2.9 Emergency Diesel Generators 41.7 / 45.5 064000 K3.03 Knowledge of the effect that a loss or malfunction of the ED/G system will have on the following::

ED/G (manual loads) 3.9*

Emergency Diesel Generators 41.7 / 45.6 075000 A4.01 Ability to manually operate and/or monitor in the control room:: Emergency/essential SWS pumps 3.2*

Circulating Water System 41.7 / 45.5 to 45.8 079000 2.4.31

Knowledge of annunciators alarms and indications, and use of the response instructions.

3.4 Station Air System 41.10 / 45.3 103000 2.2.25

Knowledge of bases in technical specifications for limiting conditions for operations and safety limits.3.7 Containment System 43.2

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 11 of 13 System/Mode KA Number Title SRO Value System Title 10 CFR 55 Tier 2

Group 3

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

Service Water System 41.7

PWR SRO Written Examination Outline (Continued)

Sep 16, 2002 8:38 PM Page 12 of 13 System/Mode KA Number Title SRO Value System Title 10 CFR 55 Tier 3

Group 4

000000 2.1.10

Knowledge of conditions and limitations in the facility license.

3.9 Generic Knowledges and Abilities 43.1 / 45.13 000000 2.1.15

Ability to manage short-term information such as night and standing orders.

3.0 Generic Knowledges and Abilities 45.12 000000 2.1.23

Ability to perform specific system and integrated plant procedures during all modes of plant operation.4.0 Generic Knowledges and Abilities 45.2 / 45.6 000000 2.1.24
Ability to obtain and interpret station electrical and mechanical drawings.

3.1 Generic Knowledges and Abilities 45.12 / 45.13 000000 2.1.33

Ability to recognize indications for system operating parameters which are entry-level conditions for technical specifications.

4.0 Generic Knowledges and Abilities 43.2 / 43.3 / 45.3 000000 2.2.07

Knowledge of the process for conducting tests or experiments not described in the safety analysis report.

3.2 Generic Knowledges and Abilities 43.3 / 45.13 000000 2.2.11

Knowledge of the process for controlling temporary changes.

3.4*

Generic Knowledges and Abilities 41.10 / 43.3 /

45.13 000000 2.2.23

Ability to track limiting conditions for operations.

3.8 Generic Knowledges and Abilities 43.2 / 45.13 000000 2.2.24

Ability to analyze the affect of maintenance activities on LCO status.

3.8 Generic Knowledges and Abilities 43.2 / 45.13 000000 2.3.01

Knowledge of 10CFR20 and related facility radiation control requirements.

3.0 Generic Knowledges and Abilities 41.12 / 43.4 /

45.9 / 45.10 000000 2.3.08

Knowledge of the process for performing a planned gaseous radioactive release.

3.2 Generic Knowledges and Abilities 43.4 / 45.10

PWR SRO Written Examination Outline (Last Page)

Sep 16, 2002 8:38 PM Page 13 of 13 System/Mode KA Number Title SRO Value System Title 10 CFR 55 000000 2.3.09

Knowledge of the process for performing a containment purge.

3.4 Generic Knowledges and Abilities 43.4 / 45.10 000000 2.4.26

Knowledge of facility protection requirements including fire brigade and portable fire fighting equipment usage.

3.3 Generic Knowledges and Abilities 43.5 / 45.12 000000 2.4.37

Knowledge of the lines of authority during an emergency.

3.5 Generic Knowledges and Abilities 45.13 000000 2.4.42

Knowledge of emergency response facilities.

3.7 Generic Knowledges and Abilities 45.11 000000 2.4.46

Ability to verify that the alarms are consistent with the plant conditions.

3.6 Generic Knowledges and Abilities 43.5 / 45.3 /

45.12 000000 2.4.48

Ability to interpret control room indications to verify the status and operation of system, and understand how operator actions and directives affect plant and system conditions.

3.8 Generic Knowledges and Abilities 43.5 / 45.12

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

Examination Level: RO Operating Test Number: _____________

Administrative Topic/

Subject Description Describe method of evaluation:

1. ONE Administrative JPM OR
2. TWO Administrative Questions Administrative JPM - Calculate critical boron concentration for startup Plant parameter verification Administrative JPM - Verify conditions are met for changing modes A.1 Mode changes Administrative JPM - Time to boil determination A.2 Maintenance -

shutdown condition Administrative JPM - RCA Entry and exit with personnel contamination A.3 Radiation Control Question: Control room operator response to accountability determination A.4 Emergency Plan 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/

Subject Description Describe method of evaluation:

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

A.4 Emergency Plan

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 (004000 A2.14 - RO 3.8/SRO 3.9)

E, D, A, S I

b. Perform monthly Recirculation Actuation Signal Surveillance Test.

(013000 K4.06 - RO 4.0/SRO 4.3)

D, S II

c. Transfer pressurizer pressure control from manual to automatic (010000 A1.07 - RO 3.7/SRO 3.7)

D, A, S III

d. Initiate Shutdown cooling (005000 K1.09 - RO 3.6/SRO 3.9)

D, L,A, S IV-P e.Shift 4160V busses between unit auxiliary transformer and house service transformer (062000 K1.04 - RO 3.7 /SRO 4.2)

D, S VI

f. Diverse Scram System Surveillance test (012000 A4.04 RO 3.3/SRO 3.3)

N, S VII

g. Operate AFW System from AI-179 (aux shutdown panel)

(000068 AA1.03 - RO 4.1/SRO 4.3)

D, E IV-S B.2 Facility Walk-Through

a. Align condenser evacuation to AB stack (000037 AA2.07 - RO 3.1/SRO 3.6)

N, E IV-S

b. Startup hydrogen purge system (028000 A2.02 - RO 3.5/SRO 3.9)

D, R, L, E V

c. Switch Inverter supply from bypass to normal (000057 AA1.01 - RO 3.7/SRO 3.7)

D, A VI

  • 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 (004000 A2.14 - RO 3.8/SRO 3.9)

E, D, A, S I

b. Perform monthly Recirculation Actuation Signal Surveillance Test.

(013000 K4.06 - RO 4.0/SRO 4.3)

D, S II

c. Fuel handling Incident (000036 AA2.02 - RO 3.4/SRO 4.1)

D, E VIII

d. Initiate Shutdown cooling (005000 K1.09 - RO 3.6/SRO 3.9)

D, L,A, S IV-P e.Shift 4160V busses between unit auxiliary transformer and house service transformer (062000 K1.04 - RO 3.7 /SRO 4.2)

D, S VI

f. Diverse Scram System Surveillance test (012000 A4.04 RO 3.3/SRO 3.3)

N, S VII

g. Operate AFW System from AI-179 (aux shutdown panel)

(000068 AA1.03 - RO 4.1/SRO 4.3)

D, E IV-S B.2 Facility Walk-Through

a. Align condenser evacuation to AB stack (000037 AA2.07 - RO 3.1/SRO 3.6)

N, E IV-S

b. Transfer waste gas from vent header to in service decay tank (071000 A4.05 - RO 2.6/SRO 2.6)

D, A, R IX

c. Switch Inverter supply from bypass to normal (000057 AA1.01 - RO 3.7/SRO 3.7)

D, A VI

  • 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 (005000 K1.09 - RO 3.6/SRO 3.9)

D, L,A, S IV-P

e.
f. Diverse Scram System Surveillance test (012000 A4.04 RO 3.3/SRO 3.3)

N, S VII

g.

B.2 Facility Walk-Through

a. Align condenser evacuation to AB stack (000037 AA2.07 - RO 3.1/SRO 3.6)

N, E IV-S

b. Transfer waste gas from vent header to in service decay tank (071000 A4.05 - RO 2.6/SRO 2.6)

D, A, R IX

c. Switch Inverter supply from bypass to normal (000057 AA1.01 - RO 3.7/SRO 3.7)

D, A VI

  • 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 No.

Malf No.

Event Type*

Event Description 1

N Return RM-052 to service 2 [+10]

NIS02D I

WR NI channel D power supply failure

[MFP NIS02D]

3 [+20]

NBWPAC 9A C

Running Bearing water pump trips (must start backup)

[RFP BCW10A OPEN]

4 [+25]

RCP09B RCP10B C

Lower and middle seals on RCP, RC-3B fails

[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:

ESF05A ESF05B C

PPLS fails to actuate

  • (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 No.

Malf No.

Event Type*

Event 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

[+13]

T:T2897 I

Letdown HX CCW outlet temperature transmitter, T-2897, fails low. (results in high letdown temperature)

[COP T:T2897 50 ]

4

[+20]

CRD06 C

Dropped Control rod

[MFP CRD06 rod 1 grp 4 deenergized]

5 R, N Reduce power to 70% due to dropped rod 6

[+35]

T:P103Y I

Controlling pressurizer pressure channel fails high

[COP T:P103Y]

7

[+40]

MSS03B M

Main steam line break in turbine building

[MFP MSS03B 20% 60 sec ramp]

8 Preset RSGH042A C

SGIS fails to actuate 9

Preset ESF06A,B C

S/G B MSIV will 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: 2002-3 (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 No.

Malf No.

Event Type*

Event 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

[+12]

NIS07D I

Power Range NI Channel D Fails

[MFP NIS07D]

4 R, N Power reduction to 70% power.

5

[+40]

SWD02A,B M

Loss of offsite power (both 161KV and 345 KV)

[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 No.

Malf No.

Event Type*

Event 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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