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 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 page 1 rev 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 EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP I BWR - Reactor Operator Target: 13% Actual: 13%
E/APE # - K K K K K K A A A A G K/A TOPICS IMP POINTS NAME/SAFETY 1 2 3 4 5 6 1 2 3 4 FUNCTION 1 295005 - Main Turbine X AK2.02 - Knowledge of the interrelations between MAIN TURBINE 2.9 1 Generator Trip - 3 GENERATOR TRIP and the following: Feedwater Temperature 2 295005 - Main Turbine X AK1.01 - Knowledge of the operational implications of the following 4.0 1 Generator Trip - 3 concepts as they apply to MAIN TURBINE GENERATOR TRIP:
Pressure effects on reactor power 3 295006 - SCRAM - 1 X AA1.03 - Ability to operate and/or monitor the following as they apply to 3.7 1 SCRAM: Reactor Turbine pressure regulating system 4 295009 - Low Reactor X AK2.04 - Knowledge of the interrelations between LOW REACTOR 2.6 1 Water Level - 2 WATER LEVEL and the following: Reactor Water Cleanup 5 295009 - Low Reactor X AA2.02 - Ability to determine and/or interpret the following as they apply 3.6 1 Water Level - 2 to LOW REACTOR WATER LEVEL: Steam flow/feedflow mismatch 6 295015 - Incomplete X AK1.03 - Knowledge of the operational implications of the following 3.8 1 SCRAM - 1 concepts as they apply to INCOMPLETE SCRAM: Reactivity effects 7 295015 - Incomplete X AA2.02 - Ability to determine and/or interpret the following as they apply 4.1 1 SCRAM - 1 to INCOMPLETE SCRAM: Control Rod Position 8 295024 - High Drywell X EK1.01 - Knowledge of the operational implications of the following 4.1 1 Pressure - 5 concepts as they apply to HIGH DRYWELL PRESSURE: Drywell integrity: Plant specific 9 295025 - High Reactor X EK3.02 - Knowledge of the reasons for the following responses as they 3.9 1 Pressure - 3 apply to HIGH REACTOR PRESSURE: Recirculation pump trip: Plant Secific page 2 rev 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 E/APE # - K K K K K K A A A A G K/A TOPICS IMP POINTS NAME/SAFETY 1 2 3 4 5 6 1 2 3 4 FUNCTION 10 295031 - Reactor Low X EA1.13 - Ability to operate and/or monitor the following as they apply to 4.3 1 Water Level - 2 REACTOR LOW WATER LEVEL: Reactor Water level control 11 295031 - Reactor Low X 2.4.10 - Knowledge of annunciator response procedures 3.0 1 Water Level - 2 12 295037 - SCRAM X EA1.02 - Ability to operate and/or monitor the following as they apply to 3.8 1 Condition Present and SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE reactor power above APRM APRM DOWNSCALE OR UNKNOWN: RRCS: Plant Specific dow2nscal or unknown - 1 13 500000 - High Containment X EK3.02 - Knowledge of the reasons for the following responses as they 2.8 1 Hydrogen Concentraiton - 5 apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS: Operation of drywerll recirculation fans Category Point Totals: 3 2 2 3 2 1 Group Point Totals: 13 13 page 3 rev 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 EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP II BWR - Reactor Operator Target: 19% Actual: 19%
E/APE # - K K K K K K A A A A G K/A TOPICS IMP POINTS NAME/SAFETY 1 2 3 4 5 6 1 2 3 4 FUNCTION 1 295001 - Partial or X AA2.04 - Ability to determine and/or interpret the following as they 3.0 1 Complete Loss of Forced apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE Core Flow Circulation - 1 FLOW CIRCULATION: Individual Jet Pump Flows 2 295003 - Partial or X 2.4.48 - Ability to interpret control room indications to verify the status 3.5 1 Complete Loss of A.C. and operation of system, and understand how operator actions and Power - 6 directives affect plant sand system conditions.
3 295008 - High Reactor X AK2.09 - Knowledge of the interrelations between HIGH REACTOR 3.1 1 Water Level - 2 WATER LEVEL and the following: Reactor Water Cleanup System 4 295012 - High Drywell X AK1.02 - Knowledge of the operational implications of the following 3.1 1 Temperature - 5 concepts as they apply to HIGH DRYWELL TEMPERATURE:
Reactor Power Level Control 5 295012 - High Drywell X AK2.02 - Knowledge of the interrelations between HIGH DRYWELL 3.6 1 Temperature - 5 TEMPERATURE and the following: Drywell Cooling 6 295019 - Partial or X AA2.02 - Ability to determine and/or interpret the following as they 3.6 1 Complete Loss of apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR:
Instrument Air - 8 Status of safety related instrument air system loads 7 295022 - Loss of CRD X AA1.04 - Ability to operate and or monitor the following as they apply 2.5 1 Pumps - 1 to LOSS OF CRD PUMPS: Reactor water cleanup system 8 295026 - Suppression Pool X EA2.01 - Ability to determine and/or interpret the following as they 4.1 1 High Water Temperature - apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:
5 Suppression Pool Water temperature page 4 rev 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 E/APE # - K K K K K K A A A A G K/A TOPICS IMP POINTS NAME/SAFETY 1 2 3 4 5 6 1 2 3 4 FUNCTION 9 295028 - High Drywell X EK1.02 - Knowledge of the operational implications of the following 2.9 1 Temperature - 5 concepts as they apply to HIGH DRYWELL TEMPERATURE:
Equipment environmental qualification 10 295028 - High Drywell X EA1.02 - Ability to operate and/or monitor the following as they apply to 3.9 1 Temperature - 5 HIGH DRYWELL TEMPERATURE: Drywell Ventilation system 11 295029 - High Suppression X EK3.02 - Knowledge of the reasons for the following responses as they 3.6 1 Pool Water Level - 5 apply to HIGH SUPPRESSION POOL WATER LEVEL: Lowering Suppression Pool level 12 295030 - Low Suppression X EK1.01 - Knowledge of the operational implications of the following 3.8 1 Pool Water Level - 5 concepts as they apply to LOW SUPPRESSION POOL WATER LEVEL: Steam Condensation 13 295030 - Low Suppression X EK2.08 - Knowledge of the interrelations between LOW SUPPRESSION 3.5 1 Pool Water Level - 5 POOL WATER LEVEL and the following: SRV discharge submergence 14 295033 - High Secondary X EK2.03 - Knowledge of the interrelations between HIGH SECONDARY 3.7 1 Containment Area CONTAINMENT AREA RADIATION LEVELS and the following:
Radiation Levels - 9 Secondary Containment Ventilation 15 295033 - High Secondary X 2.4.1 - Knowledge of EOP entry conditions and immediate action steps 4.3 1 Containment Area Radiation Levels - 9 16 295034 - Secondary X EK3.01 - Knowledge of the reasons for the following responses as they 3.8 1 Containment Ventilation apply to SECONDARY CONTAINMENT VENTILATION HIGH High Radiation - 9 RADIATION: Isolating secondary containment ventilation page 5 rev 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 E/APE # - K K K K K K A A A A G K/A TOPICS IMP POINTS NAME/SAFETY 1 2 3 4 5 6 1 2 3 4 FUNCTION 17 295038 - High Off-Site X EA1.01 - Ability to operate and/or monitor the following as they apply to 3.9 1 Release Rate - 9 HIGH OFF-SITE RELEASE RATE: Stack gas monitoring system 18 600000 - Plant Fire On Site X AK3.04 - Knowledge of the reasons for the following responses as they 2.8 1
-8 apply to PLANT FIRE ON SITE: Actions contained in the abnormal procedure for plnat fire on site 19 600000 - Plant Fire On Site X AA2.17 - Ability to determine and interpret the following as they apply to 3.1 1
-8 PLANT FIRE ON SITE: Systems that may be affected by the fire Category Point Totals: 3 4 3 3 4 2 Group point totals: 19 19 page 6 rev 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 PLANT SYSTEMS - TIER 1 GROUP III BWR - Reactor Operator Target: 4% Actual: 4%
E/APE # - K K K K K K A A A A G K/A TOPICS IMP POINTS NAME/SAFETY 1 2 3 4 5 6 1 2 3 4 FUNCTION 1 295021 - Loss of Shutdown X AK2.05 - Knowledge of the interrelations between LOSS OF 2.7 1 Cooling - 4 SHUTDOWN COOLING and the following: Fuel Pool Cooling and Cleanup system 2 295032 - High Secondary X EK3.02 - Knowledge of the reasons for the following responses as they 3.6 1 Containment Area apply to HIGH SECONDARY CONTAINMENT AREA Temperature - 5 TEMPERATURE: Reactor SCRAM 3 295035 - Secondary X EA1.01 - Ability to operate and/or monitor the following as they apply to 3.6 1 Containment High SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE:
Differential Pressure - 5 Secondary containment ventilation system 4 295035 - Secondary X EK1.01 - Knowledge of the operational implications of the following 3.9 1 Containment High concepts as they apply to SECONDARY CONTAINMENT HIGH Differential Pressure - 5 DIFFERENTIAL PRESSURE: Secondary containment integrity.
Category Point Totals: 1 1 1 1 0 4 Group Point Totals: 4 4 page 7 rev 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 PLANT SYSTEMS - TIER 2 GROUP I BWR - Reactor Operator Target: 28% Actual: 28%
SYSTEM #/ NAME K K K K K K A A A A G K/A TOPICS IMP POINTS 1 2 3 4 5 6 1 2 3 4 1 201001 - Control Rod X K2.04 - Knowledge of electrical power supplies to the following: 3.2 1 Drive Hydraulic System Scram discharge volume vent and drain valve solenoids 2 201001 - Control Rod X K6.03 - Knowledge of the effect that a loss or malfunction of the 3.0 1 Drive Hydraulic System following will have on the CONTROL ROD DRIVE HYDRAULIC System: Plant air systems 3 202002 - Recirculation X K6.04 - Knowledge of the effect that a loss or malfunction of the 3.5 1 Flow Control System following will have on the RECIRCULATION FLOW CONTROL SYSTEM: Feedwater flow inputs 4 202002 - Recirculation X A3.02 - Ability to monitor automatic operations of the 3.4 1 Flow Control System RECIRCULATION FLOW CONTROL SYSTEM including: Lights and alarms 5 209002 - High Pressure X A4.14 - Ability to manually operate and/or monitor in the control 3.0 1 Core Spray System room: Test Return Valve3.0 (HPCS) 6 211000 - Standby Liquid X K3.01 - Knowledge of the effect that a loss or malfunction of the 4.3 1 Control System STANDBY LIQUID CONTROL SYSTEM will have on following:
Ability to shutdown the reactor under certain conditions.
7 212000 - Reactor X K5.02 - Knowledge of the operational implications of the following 3.3 1 Protection System concepts as they apply to REACTOR PROTECTION SYSTEM:
Specific logic araingements.
page 8 rev 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 SYSTEM #/ NAME K K K K K K A A A A G K/A TOPICS IMP POINTS 1 2 3 4 5 6 1 2 3 4 8 215003 - Intermediate X A2.06 - Ability to (a) predict the impacts of the following on the 3.0 1 Range Monitor (IRM) INTERMEDIATE RANGE MONITOR (IRM) SYSTEM; and (b)
System based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Faulty Range Switch 9 215003 - Intermediate X K1.04 - Knowledge of the physical connections and/or cause- effect 2.5 1 Range Monitor (IRM) relationships between INTERMEDIATE RANGE MONITOR (IRM)
System SYSTEM and the following: Process computer/ performance monitoring system (SPDS/ERIS/CRIDS/GDS): Plant-Specific 10 215004 - Source Range X A2.02 - Ability to (a) predict the impacts of the following on the 3.4 1 Monitor (SRM) System 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.
11 215004 - Source Range X K2.01 - Knowledge of electrical power supplies to the following: 2.6 1 Monitor (SRM) System SRM channels/detectors 12 215005 - Average Power X K1.01 - Knowledge of the physical connections and/or cause- effect 4.0 1 Range Monitor/Local relationships between APRM/LPRM and the following: RPS Power Range Monitor System 13 215005 - Average Power X K5.06 - Knowledge of the operational implications of the following 2.5 1 Range Monitor/Local concepts as they apply to APRM/LPRM: Assignment of LPRM's to Power Range Monitor specific APRM channels System 14 216000 - Nuclear Boiler X A3.01 - Ability to monitor automatic operations of the NUCLEAR 3.4 1 Instrumentation BOILER Instrumentation including: Relationship between meter/recorder readings and actual parameter values: Plant-Specific SYSTEM #/ NAME K K K K K K A A A A G K/A TOPICS IMP POINTS page 9 rev 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 1 2 3 4 5 6 1 2 3 4 15 217000 - Reactor Core X K1.08 - Knowledge of the physical connections and/or cause- effect 3.3 1 Isolation Cooling System relationships between REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM (RCIC) and the following: Line fill pump: Plant-Specific 16 217000 - Reactor Core X A1.06 - Ability to predict and/or monitor changes in parameters 3.2 1 Isolation Cooling System associated with operating the REACTOR CORE ISOLATION (RCIC) COOLING SYSTEM (RCIC) controls including: Condensate Storage tank level 17 218000 - Automatic X K4.02 - Knowledge of AUTOMATIC DEPRESSURIZATION 3.8 1 Depressurization System SYSTEM design feature(s) and/or interlocks which provide for the following: Allows manual initiation of ADS logic.
18 218000 - Automatic X A4.12 - Ability to manually operate and/or monitor in the control 4.2 1 Depressurization System room: Reactor vessel water level.
19 223001 - Primary X K2.08 - Knowledge of electrical power supplies to the following: 2.7 1 Containment System and Containment cooling air handling units: Plant-Specific Auxiliaries 20 223001 - Primary X K4.04 - Knowledge of PRIMARY CONTAINMENT SYSTEM AND 3.5 1 Containment System and AUXILIARIES design feature(s) and/or interlocks which provide for Auxiliaries the following: Prevents hydrogen from reaching an explosive mixture 21 239002 - Relief/Safety X K6.03 - Knowledge of the effect that a loss or malfunction of the 2.7 1 Valves following will have on the RELIEF/SAFETY VALVES: AC power.
22 239002 - Relief/Safety X A4.06 - Ability to manually operate and/or monitor in the control 3.9 1 Valves room: Reactor Water level.
23 241000 - Reactor/Turbine X K3.03 - Knowledge of the effect that a loss or malfunction of the 3.7 1 Pressure Regulating REACTOR/TURBINE PRESSURE REGULATING SYSTEM will System have on following: Reactor Water level SYSTEM #/ NAME K K K K K K A A A A G K/A TOPICS IMP POINTS 1 2 3 4 5 6 1 2 3 4 24 259002 - Reactor Water X A1.03 - Ability to predict and/or monitor changes in parameters 3.8 1 associated with operating the REACTOR WATER LEVEL page 10 rev 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 Level Control System CONTROL SYSTEM controls including: Reactor Power 25 259002 - Reactor Water X 2.1.8 - Ability to coordinate personnel activities outside the control 3.8 1 Level Control System room.
26 261000 - Standby Gas X K3.06 - Knowledge of the physical connections and/or cause- effect 3.0 1 Treatment System relationships between STANDBY GAS TREATMENT SYSTEM and the following: Primary containment oxygen content: Mark-I&II 27 261000 - Standby Gas X A2.06 - Ability to (a) predict the impacts of the following on the 2.9 1 Treatment System 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.
28 264000 - Emergency X K5.06 - Knowledge of the operational implications of the following 3.4 1 Generators (Diesel/Jet) concepts as they apply to EMERGENCY GENERATORS (DIESEL/JET): Load sequencing Category Point Totals: 3 3 3 2 3 3 2 3 2 3 1 Group Point Total: 28 28 page 11 rev 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 PLANT SYSTEMS - TIER 2 GROUP II BWR - Reactor Operator Target: 19% Actual: 19%
SYSTEM #/ NAME K K K K K K A A A A G K/A TOPICS IMP POINTS 1 2 3 4 5 6 1 2 3 4 1 201004 - Rod Sequence X K4.06 - nowledge of ROD SEQUENCE CONTROL SYSTEM design 3.3 1 Control System (Plant feature(s) and/or interlocks which provide for the following: Group Specific) notch control 2 201006 - Rod Worth X K4.01 - Knowledge of ROD WORTH MINIMIZER SYSTEM (RWM) 3.4 1 Minimizer System (RWM) design feature(s) and/or interlocks which provide for the following:
(Plant Specific) Insert blocks/errors: P-Spec 3 205000 - Shutdown X K1.14 - Knowledge of the physical connections and/or cause- effect 3.6 1 Cooling System (RHR relationships between SHUTDOWN COOLING SYSTEM (RHR Shutdown Cooling Mode) SHUTDOWN COOLING MODE) and the following:Reactor temperatures (moderator, vessel, flange) 4 205000 - Shutdown X K6.03 - Knowledge of the effect that a loss or malfunction of the 3.1 1 Cooling System (RHR following will have on the SHUTDOWN COOLING SYSTEM/MODE:
Shutdown Cooling Mode) Recirculation system 5 215002 - Rod Block X K2.03 - Knowledge of electrical power supplies to the following: APRM 2.8 1 Monitor System Channels 6 219000 - RHR/LPCI: X K1.09 - Knowledge of the physical connections and/or cause- effect 3.3 1 Torus/Suppression Pool relationships between RHR/LPCI: TORUS/SUPPRESSION POOL Cooling Mode COOLING MODE and the following: Nuclear boiler instrumentation 7 219000 - RHR/LPCI: X K2.02 - Knowledge of electrical power supplies to the following: Pumps 3.1 1 Torus/Suppression Pool Cooling Mode 8 230000 - RHR/LPCI: X A1.06 - Ability to predict and/or monitor changes in parameters 3.3 1 Torus/Suppression Pool associated with operating the RHR/LPCI: TORUS/SUPPRESSION Spray Mode POOL SPRAY MODE controls including: Suppression pool level page 12 rev 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 SYSTEM #/ NAME K K K K K K A A A A G K/A TOPICS IMP POINTS 1 2 3 4 5 6 1 2 3 4 9 239001 - Main and Reheat X A2.09 - Ability to (a) predict the impacts of the following on the MAIN 3.4 1 Steam System 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 10 245000 - Main Turbine X K3.02 - Knowledge of the effect that a loss or malfunction of the MAIN 3.9 1 Generator and Auxiliary TURBINE GENERATOR AND AUXILIARY SYSTEMS will have on Systems following: Reactor pressure 11 262001 - A.C. Electrical X K5.01 - Knowledge of the operational implications of the following 3.1 1 Distribution concepts as they apply to A.C. ELECTRICAL DISTRIBUTION:
Principle involved with paralleling two A.C. sources 12 262001 - A.C. Electrical X A1.04 - Ability to predict and/or monitor changes in parameters 2.7 1 Distribution associated with operating the A.C. ELECTRICAL DISTRIBUTION controls including: Load currents 13 262002 - Uninterruptable X A4.01 - Ability to manually operate and/or monitor in the control room: 2.8 1 Power Supply (A.C./D.C.) Transfer from altenative source to preferred source 14 286000 - Fire Protection X K3.01 - Knowledge of the effect that a loss or malfunction of the FIRE 3.2 1 System PROTECTION SYSTEM will have on following: The ability to detect fires 15 290001 - Secondary X A2.05 - Ability to (a) predict the impacts of the following on the 3.1 1 Containment 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 16 290001 - Secondary X 2.1.16 - Ability to operate plant phone, paging system, and two-way 2.9 1 Containment radio.
page 13 rev 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 SYSTEM #/ NAME K K K K K K A A A A G K/A TOPICS IMP POINTS 1 2 3 4 5 6 1 2 3 4 17 290003 - Control Room X A3.01 - Ability to monitor automatic operations of the CONTROL 3.3 1 HVAC ROOM HVAC including: Initiation/reconfiguration.
18 300000 - Instrument Air X K6.12 - Knowledge of the effect that a loss or malfunction of the 2.9 1 System (IAS) following will have on the INSTRUMENT AIR SYSTEM: Breakers, relays, and disconnects.
19 400000 - Component X A3.01 - Ability to monitor automatic operations of the CCWS including: 3.0 1 Cooling Water System Setpoints on instrument signal levels for normal operations, warnings, and (CCWS) trips that are applicable to the CCWS Category Point Totals: 2 2 2 2 1 2 2 2 2 1 1 Group point totals: 19 19 page 14 rev 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 PLANT SYSTEMS - TIER 2 GROUP III BWR - Reactor Operator Target: 4% Actual: 4%
SYSTEM #/ NAME K K K K K K A A A A G K/A TOPICS IMP POINTS 1 2 3 4 5 6 1 2 3 4 1 215001 - Traversing In- X K4.01 - Knowledge of TRAVERSING IN-CORE PROBE design 3.4 1 Core Probe feature(s) and/or interlocks which provide for the following: Primary containment isolation: Mark-I&II(Not-BWR1) 2 268000 - Radwaste X A1.02 - Ability to predict and/or monitor changes in parameters 2.6 1 associated with operating the RADWASTE controls including: Offsite release 3 288000 - Plant Ventilation X K1.03 - Knowledge of the physical connections and/or cause- effect 3.7 1 Systems relationships between PLANT VENTILATION SYSTEMS and the following: Standby gas treatment 4 288000 - Plant Ventilation X A2.03 - Ability to (a) predict the impacts of the following on the PLANT 3.5 1 Systems 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 Category Point Totals: 1 0 0 1 0 0 1 1 0 0 0 Group point totals: 4 4 page 15 rev 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 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 2.8 1 performance data.
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 / 3.5 1 communication with fuel storage facility / systems operated from the control room in support of fueling operations / and supporting instrumentation.
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 2.5 1 authorized.
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 4.0 1 emergency and abnormal operating procedures.
13 2.4.24 Knowledge of loss of cooling water procedures. 3.3 1 Group point totals: 13 13 page 16 rev 1