ML030940336
| ML030940336 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/27/2003 |
| From: | NRC Region 4 |
| To: | Energy Northwest |
| References | |
| 50-397/03-301 | |
| Download: ML030940336 (16) | |
Text
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: March 2003 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 1 rev 1 COUNT MATRIX Summarizing Counts by K/A Group for BWR - Reactor Operator K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 SG Total E/APE # - T1 Gp 1 3
2 2
3 2
1 13 E/APE # - T1 Gp 2 3
4 3
3 4
2 19 E/APE # - T1 Gp 3 1
1 1
1 0
0 4
Tier Totals 7
7 6
7 6
3 36 Plant Systems / T2 Gp 1 3
3 3
2 3
3 2
3 2
3 1
28 Plant Systems / T2 Gp 2 2
2 2
2 1
2 2
2 2
1 1
19 Plant Systems / T2 Gp 3 1
0 0
1 0
0 1
1 0
0 0
4 Tier Totals 6
5 5
5 4
5 5
6 4
4 2
51 Generic K/As / T3 CAT 1 - 4 CAT 2 - 3 CAT 3 - 3 CAT 4 - 3 13 Model Total 100
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: March 2003 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 2 rev 1 EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP I BWR - Reactor Operator Target: 13%
Actual: 13%
E/APE # -
NAME/SAFETY FUNCTION K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A TOPICS IMP POINTS 1
295005 - Main Turbine Generator Trip - 3 X
AK2.02 - Knowledge of the interrelations between MAIN TURBINE GENERATOR TRIP and the following: Feedwater Temperature 2.9 1
2 295005 - Main Turbine Generator Trip - 3 X
AK1.01 - Knowledge of the operational implications of the following concepts as they apply to MAIN TURBINE GENERATOR TRIP:
Pressure effects on reactor power 4.0 1
3 295006 - SCRAM - 1 X
AA1.03 - Ability to operate and/or monitor the following as they apply to SCRAM: Reactor Turbine pressure regulating system 3.7 1
4 295009 - Low Reactor Water Level - 2 X
AK2.04 - Knowledge of the interrelations between LOW REACTOR WATER LEVEL and the following: Reactor Water Cleanup 2.6 1
5 295009 - Low Reactor Water Level - 2 X
AA2.02 - Ability to determine and/or interpret the following as they apply to LOW REACTOR WATER LEVEL: Steam flow/feedflow mismatch 3.6 1
6 295015 - Incomplete SCRAM - 1 X
AK1.03 - Knowledge of the operational implications of the following concepts as they apply to INCOMPLETE SCRAM: Reactivity effects 3.8 1
7 295015 - Incomplete SCRAM - 1 X
AA2.02 - Ability to determine and/or interpret the following as they apply to INCOMPLETE SCRAM: Control Rod Position 4.1 1
8 295024 - High Drywell Pressure - 5 X
EK1.01 - Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL PRESSURE: Drywell integrity: Plant specific 4.1 1
9 295025 - High Reactor Pressure - 3 X
EK3.02 - Knowledge of the reasons for the following responses as they apply to HIGH REACTOR PRESSURE: Recirculation pump trip: Plant Secific 3.9 1
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: March 2003 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 3 rev 1 E/APE # -
NAME/SAFETY FUNCTION K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A TOPICS IMP POINTS 10 295031 - Reactor Low Water Level - 2 X
EA1.13 - Ability to operate and/or monitor the following as they apply to REACTOR LOW WATER LEVEL: Reactor Water level control 4.3 1
11 295031 - Reactor Low Water Level - 2 X
2.4.10 - Knowledge of annunciator response procedures 3.0 1
12 295037 - SCRAM Condition Present and reactor power above APRM dow2nscal or unknown - 1 X
EA1.02 - Ability to operate and/or monitor the following as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: RRCS: Plant Specific 3.8 1
13 500000 - High Containment Hydrogen Concentraiton - 5 X
EK3.02 - Knowledge of the reasons for the following responses as they apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS: Operation of drywerll recirculation fans 2.8 1
Category Point Totals:
3 2
2 3
2 1
Group Point Totals: 13 13
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: March 2003 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 4 rev 1 EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP II BWR - Reactor Operator Target: 19%
Actual: 19%
E/APE # -
NAME/SAFETY FUNCTION K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A TOPICS IMP POINTS 1
295001 - Partial or Complete Loss of Forced Core Flow Circulation - 1 X
AA2.04 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: Individual Jet Pump Flows 3.0 1
2 295003 - Partial or Complete Loss of A.C.
Power - 6 X
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 sand system conditions.
3.5 1
3 295008 - High Reactor Water Level - 2 X
AK2.09 - Knowledge of the interrelations between HIGH REACTOR WATER LEVEL and the following: Reactor Water Cleanup System 3.1 1
4 295012 - High Drywell Temperature - 5 X
AK1.02 - Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL TEMPERATURE:
Reactor Power Level Control 3.1 1
5 295012 - High Drywell Temperature - 5 X
AK2.02 - Knowledge of the interrelations between HIGH DRYWELL TEMPERATURE and the following: Drywell Cooling 3.6 1
6 295019 - Partial or Complete Loss of Instrument Air - 8 X
AA2.02 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR:
Status of safety related instrument air system loads 3.6 1
7 295022 - Loss of CRD Pumps - 1 X
AA1.04 - Ability to operate and or monitor the following as they apply to LOSS OF CRD PUMPS: Reactor water cleanup system 2.5 1
8 295026 - Suppression Pool High Water Temperature -
5 X
EA2.01 - Ability to determine and/or interpret the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:
Suppression Pool Water temperature 4.1 1
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: March 2003 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 5 rev 1 E/APE # -
NAME/SAFETY FUNCTION K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A TOPICS IMP POINTS 9
295028 - High Drywell Temperature - 5 X
EK1.02 - Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL TEMPERATURE:
Equipment environmental qualification 2.9 1
10 295028 - High Drywell Temperature - 5 X
EA1.02 - Ability to operate and/or monitor the following as they apply to HIGH DRYWELL TEMPERATURE: Drywell Ventilation system 3.9 1
11 295029 - High Suppression Pool Water Level - 5 X
EK3.02 - Knowledge of the reasons for the following responses as they apply to HIGH SUPPRESSION POOL WATER LEVEL: Lowering Suppression Pool level 3.6 1
12 295030 - Low Suppression Pool Water Level - 5 X
EK1.01 - Knowledge of the operational implications of the following concepts as they apply to LOW SUPPRESSION POOL WATER LEVEL: Steam Condensation 3.8 1
13 295030 - Low Suppression Pool Water Level - 5 X
EK2.08 - Knowledge of the interrelations between LOW SUPPRESSION POOL WATER LEVEL and the following: SRV discharge submergence 3.5 1
14 295033 - High Secondary Containment Area Radiation Levels - 9 X
EK2.03 - Knowledge of the interrelations between HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS and the following:
Secondary Containment Ventilation 3.7 1
15 295033 - High Secondary Containment Area Radiation Levels - 9 X
2.4.1 - Knowledge of EOP entry conditions and immediate action steps 4.3 1
16 295034 - Secondary Containment Ventilation High Radiation - 9 X
EK3.01 - Knowledge of the reasons for the following responses as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION: Isolating secondary containment ventilation 3.8 1
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: March 2003 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 6 rev 1 E/APE # -
NAME/SAFETY FUNCTION K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A TOPICS IMP POINTS 17 295038 - High Off-Site Release Rate - 9 X
EA1.01 - Ability to operate and/or monitor the following as they apply to HIGH OFF-SITE RELEASE RATE: Stack gas monitoring system 3.9 1
18 600000 - Plant Fire On Site
- 8 X
AK3.04 - Knowledge of the reasons for the following responses as they apply to PLANT FIRE ON SITE: Actions contained in the abnormal procedure for plnat fire on site 2.8 1
19 600000 - Plant Fire On Site
- 8 X
AA2.17 - Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE: Systems that may be affected by the fire 3.1 1
Category Point Totals:
3 4
3 3
4 2
Group point totals: 19 19
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: March 2003 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 7 rev 1 PLANT SYSTEMS - TIER 1 GROUP III BWR - Reactor Operator Target: 4%
Actual: 4%
E/APE # -
NAME/SAFETY FUNCTION K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A TOPICS IMP POINTS 1
295021 - Loss of Shutdown Cooling - 4 X
AK2.05 - Knowledge of the interrelations between LOSS OF SHUTDOWN COOLING and the following: Fuel Pool Cooling and Cleanup system 2.7 1
2 295032 - High Secondary Containment Area Temperature - 5 X
EK3.02 - Knowledge of the reasons for the following responses as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE: Reactor SCRAM 3.6 1
3 295035 - Secondary Containment High Differential Pressure - 5 X
EA1.01 - Ability to operate and/or monitor the following as they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE:
Secondary containment ventilation system 3.6 1
4 295035 - Secondary Containment High Differential Pressure - 5 X
EK1.01 - Knowledge of the operational implications of the following concepts as they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: Secondary containment integrity.
3.9 1
Category Point Totals:
1 1
1 1
0 4
Group Point Totals: 4 4
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: March 2003 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 8 rev 1 PLANT SYSTEMS - TIER 2 GROUP I BWR - Reactor Operator Target: 28%
Actual: 28%
SYSTEM #/ NAME K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A TOPICS IMP POINTS 1
201001 - Control Rod Drive Hydraulic System X
K2.04 - Knowledge of electrical power supplies to the following:
Scram discharge volume vent and drain valve solenoids 3.2 1
2 201001 - Control Rod Drive Hydraulic System X
K6.03 - Knowledge of the effect that a loss or malfunction of the following will have on the CONTROL ROD DRIVE HYDRAULIC System: Plant air systems 3.0 1
3 202002 - Recirculation Flow Control System X
K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the RECIRCULATION FLOW CONTROL SYSTEM: Feedwater flow inputs 3.5 1
4 202002 - Recirculation Flow Control System X
A3.02 - Ability to monitor automatic operations of the RECIRCULATION FLOW CONTROL SYSTEM including: Lights and alarms 3.4 1
5 209002 - High Pressure Core Spray System (HPCS)
X A4.14 - Ability to manually operate and/or monitor in the control room: Test Return Valve3.0 3.0 1
6 211000 - Standby Liquid Control System X
K3.01 - Knowledge of the effect that a loss or malfunction of the STANDBY LIQUID CONTROL SYSTEM will have on following:
Ability to shutdown the reactor under certain conditions.
4.3 1
7 212000 - Reactor Protection System X
K5.02 - Knowledge of the operational implications of the following concepts as they apply to REACTOR PROTECTION SYSTEM:
Specific logic araingements.
3.3 1
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: March 2003 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 9 rev 1 SYSTEM #/ NAME K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A TOPICS IMP POINTS 8
215003 - Intermediate Range Monitor (IRM)
System X
A2.06 - Ability to (a) predict the impacts of the following on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Faulty Range Switch 3.0 1
9 215003 - Intermediate Range Monitor (IRM)
System X
K1.04 - Knowledge of the physical connections and/or cause-effect relationships between INTERMEDIATE RANGE MONITOR (IRM)
SYSTEM and the following: Process computer/ performance monitoring system (SPDS/ERIS/CRIDS/GDS): Plant-Specific 2.5 1
10 215004 - Source Range Monitor (SRM) System X
A2.02 - Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM) SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: SRM Inop condition.
3.4 1
11 215004 - Source Range Monitor (SRM) System X
K2.01 - Knowledge of electrical power supplies to the following:
SRM channels/detectors 2.6 1
12 215005 - Average Power Range Monitor/Local Power Range Monitor System X
K1.01 - Knowledge of the physical connections and/or cause-effect relationships between APRM/LPRM and the following: RPS 4.0 1
13 215005 - Average Power Range Monitor/Local Power Range Monitor System X
K5.06 - Knowledge of the operational implications of the following concepts as they apply to APRM/LPRM: Assignment of LPRM's to specific APRM channels 2.5 1
14 216000 - Nuclear Boiler Instrumentation X
A3.01 - Ability to monitor automatic operations of the NUCLEAR BOILER Instrumentation including: Relationship between meter/recorder readings and actual parameter values: Plant-Specific 3.4 1
SYSTEM #/ NAME K
K K
K K
K A
A A
A G
K/A TOPICS IMP POINTS
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: March 2003 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 10 rev 1 1
2 3
4 5
6 1
2 3
4 15 217000 - Reactor Core Isolation Cooling System (RCIC)
X K1.08 - Knowledge of the physical connections and/or cause-effect relationships between REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) and the following: Line fill pump: Plant-Specific 3.3 1
16 217000 - Reactor Core Isolation Cooling System (RCIC)
X A1.06 - Ability to predict and/or monitor changes in parameters associated with operating the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) controls including: Condensate Storage tank level 3.2 1
17 218000 - Automatic Depressurization System X
K4.02 - Knowledge of AUTOMATIC DEPRESSURIZATION SYSTEM design feature(s) and/or interlocks which provide for the following: Allows manual initiation of ADS logic.
3.8 1
18 218000 - Automatic Depressurization System X
A4.12 - Ability to manually operate and/or monitor in the control room: Reactor vessel water level.
4.2 1
19 223001 - Primary Containment System and Auxiliaries X
K2.08 - Knowledge of electrical power supplies to the following:
Containment cooling air handling units: Plant-Specific 2.7 1
20 223001 - Primary Containment System and Auxiliaries X
K4.04 - Knowledge of PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES design feature(s) and/or interlocks which provide for the following: Prevents hydrogen from reaching an explosive mixture 3.5 1
21 239002 - Relief/Safety Valves X
K6.03 - Knowledge of the effect that a loss or malfunction of the following will have on the RELIEF/SAFETY VALVES: AC power.
2.7 1
22 239002 - Relief/Safety Valves X
A4.06 - Ability to manually operate and/or monitor in the control room: Reactor Water level.
3.9 1
23 241000 - Reactor/Turbine Pressure Regulating System X
K3.03 - Knowledge of the effect that a loss or malfunction of the REACTOR/TURBINE PRESSURE REGULATING SYSTEM will have on following: Reactor Water level 3.7 1
SYSTEM #/ NAME K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A TOPICS IMP POINTS 24 259002 - Reactor Water X
A1.03 - Ability to predict and/or monitor changes in parameters associated with operating the REACTOR WATER LEVEL 3.8 1
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: March 2003 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 11 rev 1 Level Control System CONTROL SYSTEM controls including: Reactor Power 25 259002 - Reactor Water Level Control System X
2.1.8 - Ability to coordinate personnel activities outside the control room.
3.8 1
26 261000 - Standby Gas Treatment System X
K3.06 - Knowledge of the physical connections and/or cause-effect relationships between STANDBY GAS TREATMENT SYSTEM and the following: Primary containment oxygen content: Mark-I&II 3.0 1
27 261000 - Standby Gas Treatment System X
A2.06 - Ability to (a) predict the impacts of the following on the STANDBY GAS TREATMENT SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Valve closures.
2.9 1
28 264000 - Emergency Generators (Diesel/Jet)
X K5.06 - Knowledge of the operational implications of the following concepts as they apply to EMERGENCY GENERATORS (DIESEL/JET): Load sequencing 3.4 1
Category Point Totals:
3 3
3 2
3 3
2 3
2 3
1 Group Point Total: 28 28
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: March 2003 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 12 rev 1 PLANT SYSTEMS - TIER 2 GROUP II BWR - Reactor Operator Target: 19%
Actual: 19%
SYSTEM #/ NAME K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A TOPICS IMP POINTS 1
201004 - Rod Sequence Control System (Plant Specific)
X K4.06 - nowledge of ROD SEQUENCE CONTROL SYSTEM design feature(s) and/or interlocks which provide for the following: Group notch control 3.3 1
2 201006 - Rod Worth Minimizer System (RWM)
(Plant Specific)
X K4.01 - Knowledge of ROD WORTH MINIMIZER SYSTEM (RWM) design feature(s) and/or interlocks which provide for the following:
Insert blocks/errors: P-Spec 3.4 1
3 205000 - Shutdown Cooling System (RHR Shutdown Cooling Mode)
X K1.14 - Knowledge of the physical connections and/or cause-effect relationships between SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) and the following:Reactor temperatures (moderator, vessel, flange) 3.6 1
4 205000 - Shutdown Cooling System (RHR Shutdown Cooling Mode)
X K6.03 - Knowledge of the effect that a loss or malfunction of the following will have on the SHUTDOWN COOLING SYSTEM/MODE:
Recirculation system 3.1 1
5 215002 - Rod Block Monitor System X
K2.03 - Knowledge of electrical power supplies to the following: APRM Channels 2.8 1
6 219000 - RHR/LPCI:
Torus/Suppression Pool Cooling Mode X
K1.09 - Knowledge of the physical connections and/or cause-effect relationships between RHR/LPCI: TORUS/SUPPRESSION POOL COOLING MODE and the following: Nuclear boiler instrumentation 3.3 1
7 219000 - RHR/LPCI:
Torus/Suppression Pool Cooling Mode X
K2.02 - Knowledge of electrical power supplies to the following: Pumps 3.1 1
8 230000 - RHR/LPCI:
Torus/Suppression Pool Spray Mode X
A1.06 - Ability to predict and/or monitor changes in parameters associated with operating the RHR/LPCI: TORUS/SUPPRESSION POOL SPRAY MODE controls including: Suppression pool level 3.3 1
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: March 2003 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 13 rev 1 SYSTEM #/ NAME K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A TOPICS IMP POINTS 9
239001 - Main and Reheat Steam System X
A2.09 - Ability to (a) predict the impacts of the following on the MAIN AND REHEAT STEAM SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Opening of head vent to drywell equipment sump with pressure in the reactor vessel 3.4 1
10 245000 - Main Turbine Generator and Auxiliary Systems X
K3.02 - Knowledge of the effect that a loss or malfunction of the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS will have on following: Reactor pressure 3.9 1
11 262001 - A.C. Electrical Distribution X
K5.01 - Knowledge of the operational implications of the following concepts as they apply to A.C. ELECTRICAL DISTRIBUTION:
Principle involved with paralleling two A.C. sources 3.1 1
12 262001 - A.C. Electrical Distribution X
A1.04 - Ability to predict and/or monitor changes in parameters associated with operating the A.C. ELECTRICAL DISTRIBUTION controls including: Load currents 2.7 1
13 262002 - Uninterruptable Power Supply (A.C./D.C.)
X A4.01 - Ability to manually operate and/or monitor in the control room:
Transfer from altenative source to preferred source 2.8 1
14 286000 - Fire Protection System X
K3.01 - Knowledge of the effect that a loss or malfunction of the FIRE PROTECTION SYSTEM will have on following: The ability to detect fires 3.2 1
15 290001 - Secondary Containment X
A2.05 - Ability to (a) predict the impacts of the following on the SECONDARY CONTAINMENT; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: High area temperature 3.1 1
16 290001 - Secondary Containment X
2.1.16 - Ability to operate plant phone, paging system, and two-way radio.
2.9 1
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: March 2003 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 14 rev 1 SYSTEM #/ NAME K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A TOPICS IMP POINTS 17 290003 - Control Room HVAC X
A3.01 - Ability to monitor automatic operations of the CONTROL ROOM HVAC including: Initiation/reconfiguration.
3.3 1
18 300000 - Instrument Air System (IAS)
X K6.12 - Knowledge of the effect that a loss or malfunction of the following will have on the INSTRUMENT AIR SYSTEM: Breakers, relays, and disconnects.
2.9 1
19 400000 - Component Cooling Water System (CCWS)
X A3.01 - Ability to monitor automatic operations of the CCWS including:
Setpoints on instrument signal levels for normal operations, warnings, and trips that are applicable to the CCWS 3.0 1
Category Point Totals:
2 2
2 2
1 2
2 2
2 1
1 Group point totals: 19 19
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: March 2003 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 15 rev 1 PLANT SYSTEMS - TIER 2 GROUP III BWR - Reactor Operator Target: 4%
Actual: 4%
SYSTEM #/ NAME K
1 K
2 K
3 K
4 K
5 K
6 A
1 A
2 A
3 A
4 G
K/A TOPICS IMP POINTS 1
215001 - Traversing In-Core Probe X
K4.01 - Knowledge of TRAVERSING IN-CORE PROBE design feature(s) and/or interlocks which provide for the following: Primary containment isolation: Mark-I&II(Not-BWR1) 3.4 1
2 268000 - Radwaste X
A1.02 - Ability to predict and/or monitor changes in parameters associated with operating the RADWASTE controls including: Offsite release 2.6 1
3 288000 - Plant Ventilation Systems X
K1.03 - Knowledge of the physical connections and/or cause-effect relationships between PLANT VENTILATION SYSTEMS and the following: Standby gas treatment 3.7 1
4 288000 - Plant Ventilation Systems X
A2.03 - Ability to (a) predict the impacts of the following on the PLANT VENTILATION SYSTEMS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of coolant accident: Plant specific 3.5 1
Category Point Totals:
1 0
0 1
0 0
1 1
0 0
0 Group point totals: 4 4
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: March 2003 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 16 rev 1 PLANT-WIDE GENERIC RESPONSIBILITIES TIER 3 BWR - Reactor Operator Target: 13%
Actual: 13%
Category K/A TOPICS IMP POINTS 1
2.1.25 Ability to obtain and interpret station reference materials such as graphs, monographs, and tables which contain performance data.
2.8 1
2 Conduct 2.1.17 Ability to make accurate, clear and concise verbal reports.
3.5 1
3 of 2.1.14 Knowledge of system status criteria which require the notification of plant personnel.
2.5 1
4 Operations 2.1.1 Knowledge of conduct of operations requirements.
3.7 1
5 Equipment 2.2.30 Knowledge of RO duties in the control room during fuel handling such as alarms from fuel handling area /
communication with fuel storage facility / systems operated from the control room in support of fueling operations / and supporting instrumentation.
3.5 1
6 Control 2.2.13 Knowledge of tagging and clearance procedures.
3.6 1
7 2.2.22 Knowledge of limiting conditions for operations and safety limits.
3.4 1
8 Radiation 2.3.11 Ability to control radiation releases 2.7 1
9 Control 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
2.5 1
10 2.3.1 Knowledge of 10 CFR 20 and related facility radiation control requirements.
2.6 1
11 Emergency Proc.
2.4.18 Knowledge of the specific bases for EOPs.
2.7 1
12 Plan 2.4.4 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures.
4.0 1
13 2.4.24 Knowledge of loss of cooling water procedures.
3.3 1
Group point totals: 13 13