ML010680294
| ML010680294 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 02/22/2002 |
| From: | NRC Region 4 |
| To: | |
| References | |
| Download: ML010680294 (29) | |
Text
ADMINISTRATIVE TOPICS OUTLINE FORM ES-301-1 Rev 1 Page 1 admnoutr3 Facility: Columbia Generating Station Date of examination:
Examination level: SRO Operating test number:
Administrative Topic/Subject Description Describe the method of evaluation:
- 2. TWO Administrative questions A.1 Security 2 questions 1.
2.1.27 2.8/2.9 - Effect of the loss of IN-4 on Security.
2.
2.1.13 2.1/2.9 - Reportabiliity of unauthorized access to the protected area Plant Parameter Verification JPM 1.
JPM - 2.1.7 3.7/4.4 - Given OSP-RRC-D701, use the procedure and panel indications to do a manual determination of operability of the A Loop Jet Pumps.
A.2 Use of EWDs JPM 1.
JPM - 2.1.24 2.8/3.1 - Use EWDs to explain the start and trip circuits for ROA-FN-1A.
A.3 Radiation Exposure Limits JPM 1.
JPM - 2.3.4 2.5/3.1 - Complete all required paperwork for an Increased Exposure Request.
A.4 Emergency Action Levels and Classifications JPM 1.
JPM - 2.4.41 2.3/4.1 - Given conditions, make correct classification and complete the CNF Form.
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: February 2001 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 1 rooutr1 bold face indicates K/As common to both RO and SRO 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 3
3 2
0 13 E/APE # - T1 Gp 2 3
3 4
4 3
2 19 E/APE # - T1 Gp 3 1
1 2
0 0
0 4
Tier Totals 7
6 9
7 5
2 36 Plant Systems / T2 Gp 1 3
2 3
2 3
3 3
3 2
2 2
28 Plant Systems / T2 Gp 2 2
2 2
2 2
2 2
1 2
2 0
19 Plant Systems / T2 Gp 3 0
0 1
1 0
1 1
0 0
0 0
4 Tier Totals 5
4 6
6 5
5 6
4 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: February 2001 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 2 rooutr1 bold face indicates K/As common to both RO and SRO EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP I BWR - Reactor OperatorTarget: 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
AA1.01 - Recirculation System: Plant Specific COLUMBIA-IPE 3.1/3.3 1
2 295006 / Scram / 1 X
AA1.04 - Recirculation System 3.1/3.2 1
3 295007 / High Reactor Pressure / 3 X
AK2.05 - Shutdown Cooling: Plant Specific 2.9/3.1 1
4 295007 / High Reactor Pressure / 3 X
AK2.01 - Reactor/turbine pressure regulating system 3.5/3.7 1
5 295014 / Inadvertent Reactivity Addition / 1 X
AK1.05 - Fuel Thermal Limits 3.7/4.2 1
6 295015 / Incomplete Scram / 1 X
AA2.01 - Reactor Power COLUMBIA-IPE 4.1/4.3 1
7 295015 / Incomplete Scram / 1 X
AK1.02 - Cooldown effects on reactor power COLUMBIA-IPE 3.9/4.1 1
8 295024 / High Drywell Pressure / 5 X
EA1.16 - Containment/drywell vacuum breakers 3.4/3.4 1
9 295025 / High Reactor Pressure / 3 X
EK1.06 - Pressure effects on reactor water level 3.5/3.6 1
10 295025 / High Reactor Pressure / 3 X
Ek3.01 - Safety/relief valve opening COLUMBIA-IPE 4.2/4.3 1
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: February 2001 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 3 rooutr1 bold face indicates K/As common to both RO and SRO 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 11 295031 / Reactor Low Water Level / 2 X
Ek3.01 - Automatic Depressurization System actuation COLUMBIA-IPE 3.9/4.2 1
12 500000 / High Containment Hydrogen Concentration / 5 X
EK3.04 - Emergency Depressurization 3.1/3.9 1
13 500000 / High Containment Hydrogen Concentration / 5 X
EA2.04 - Combustible limits for wetwell 3.3/3.3 1
Category Point Totals:
3 2
3 3
2 0
Group Point Totals: 13 13
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: February 2001 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 4 rooutr1 bold face indicates K/As common to both RO and SRO EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP II BWR - Reactor OperatorTarget: 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
295003 / Partial or Complete Loss of AC Power / 6 X
AA1.02 - Emergency Generators COLUMBIA-IPE 4.2/4.3 1
2 295003 / Partial or Complete Loss of AC Power / 6 X
AK3.03 - Load shedding COLUMBIA-IPE 3.5/3.6 1
3 295004 / Partial or complete loss of DC power / 6 X
AK1.04 - Effect of battery discharge rate on capacity COLUMBIA-IPE 2.8/2.9 1
4 295008 / High Reactor Water Level / 2 AA2.02 - Steam flow /Feed flow mismatch 3.4/3.4 1
5 295008 / High Reactor Water Level / 2 X
2.1.8 - Ability to coordinate personnel activities outside the control room 3.8/3.6 1
6 295012 / High Drywell Temperature / 5 X
AK2.02 - Drywell cooling 3.6/3.7 1
7 295013 / High Suppression Pool Temperature / 5 X
AK1.04 - Complete Condensation 2.9/3.2 1
8 295013 / High Suppression Pool Temperature / 5 X
AK2.01 - Suppression Pool Cooling 3.6/3.7 1
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: February 2001 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 5 rooutr1 bold face indicates K/As common to both RO and SRO 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
295016 / Control Room Abandonment / 7 X
AK3.01 - Reactor Scram 4.1/4.2 1
10 295016 / Control Room Abandonment / 7 X
AA1.06 - Reactor Water Level 4.0/4.1 1
11 295018 / Partial or complete loss of Component Cooling Water / 8 X
AK1.01 - Effects on component/systems operations 3.5/3.6 1
12 295018 / Partial or complete loss of Component Cooling Water / 8 X
AA1.02 - System loads 3.3/3.4 1
13 295022 / Loss of CRD Pumps / 1 X
AA1.04 - Reactor Waster Cleanup System: Plant Specific 2.5/2.6 1
14 295022 / Loss of CRD Pumps / 1 X
AA2.01 - Accumulator pressure 3.5/3.6 1
15 295028 / High Drywell Temperature / 5 X
EK3.04 - Increase Drywell Cooling 3.6/3.8 1
16 295029 / High Suppression Pool Water Level / 5 X
2.1.12 - Knowledge of operator responsibilities during all modes of plant operation 3.0/4.0 1
17 295030 / Low Suppression Pool Water Level / 5 X
EK2.05 - HPCS: Plant Specific 3.8/3.9 1
18 295030 / Low Suppression Pool Water Level / 5 X
EA2.04 - Drywell/Suppression Chamber differential pressure: Mark-I&II 3.5/3.7 1
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: February 2001 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 6 rooutr1 bold face indicates K/As common to both RO and SRO 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 19 2985034 / Secondary Containment Ventilation High Radiation X
EK3.02 - Starting SBGT/FRVS: Plant Specific 4.1/4.1 1
Category Point Totals:
3 3
4 4
3 2
Group point totals: 19 19
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: February 2001 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 7 rooutr1 bold face indicates K/As common to both RO and SRO PLANT SYSTEMS - TIER 1 GROUP III BWR - Reactor OperatorTarget: 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
AK3.03 - Increasing drywell cooling 2.9/2.9 1
2 295023 / Refueling Accidents / 8 X
AK2.03 - Radiation monitoring equipment 3.4/3.6 1
3 295035 / Sec Cont High Differential Press / 5 X
EK1.02 - Radiation release 3.7/4.2 1
4 295036 / Sec Cont High Sump/Area Water Level
/ 5 X
EK3.03 - Isolating affected systems COLUMBIA-IPE 3.5/3.6 1
Category Point Totals:
1 1
2 0
0 0
Group Point Totals:
4
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: February 2001 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 8 rooutr1 bold face indicates K/As common to both RO and SRO PLANT SYSTEMS - TIER 2 GROUP I BWR - Reactor OperatorTarget: 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
203000 / RHR/LPCI:
Injection Mode (Plant specific) / 2 X
K4.02 - Prevention of piping overpressurization 3.2/3.4 1
2 203000 / RHR/LPCI:
Injection Mode (Plant specific) / 2 X
K6.08 - ECCS room cooling 2.9/3.1 1
3 209001 / Low Pressure Core Spray X
K1.12 - Eccs room coolers 2.9/3.1 1
4 209001 / Low Pressure Core Spray X
K5.04 - Heat removal (transfer) mechanisms 2.8/2.9 1
5 211000 / Standby Liquid Control X
K1.09 - Core spray system: Plant specific 3.2/3.4 1
6 212000 / Reactor Protection System X
K2.02 - Analog trip system logic cabinets 2.7/2.9 1
7 212000 / Reactor Protection System X
K2.01 - RPS motor generator sets 3.2/3.3 1
8 215003 / Intermediate Range Monitor X
A1.05 - SCRAM and rod block setpoints 3.9/3.9 1
9 215003 / Intermediate Range Monitor X
A4.03 - IRM range switches 3.6/3.4 1
10 215004 / Source Range Monitor (SRM) System / 7 X
K3.04 - Reactor power and indication 3.7/3.7 1
SYSTEM #/
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: February 2001 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 9 rooutr1 bold face indicates K/As common to both RO and SRO NAME/SAFETY FUNCTION 1
2 3
4 5
6 1
2 3
4 11 215004 / Source Range Monitor (SRM) System / 7 X
A3.03 - RPS status 3.6/3.5 1
12 215005 / Average Power Range Monitor/Local Power Range Monitor / 7 X
K4.06 - Effects of detector aging on LPRM/APRM readings 2.6/2.8 1
13 215005 / Average Power Range Monitor/Local Power Range Monitor / 7 X
A4.06 - Verification of proper function/operability 3.6/3.8 1
14 216000 / Nuclear Boiler Instrumentation / 7 X
K3.11 - MSIV Leakage control system: Plant Specific 2.8/2.8 1
15 216000 / Nuclear Boiler Instrumentation / 7 X
K5.08 - Steam flow effect on reactor water level 3.1/3.2 1
16 217000 / Reactor Core Isolation Cooling X
K6.01 - Electrical power 3.4/3.5 1
17 218000 / Automatic Depressurization Sys.
X K5.01 - ADS logic operation 3.8/3.8 1
18 223001 / Primary Containment System and Auxiliaries / 5 X
A2.10 - High Drywell temperature 3.6/3.8 1
19 223002 / Pri Cont Isolation Sys/ Nuclear Steam Supply Shutoff x
K3.10 - Reactor water cleanup 2.9/3.1 1
20 239002 / Relief/Safety Valves X
A2.04 - ADS actuation 4.1/4.2 1
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: February 2001 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 10 rooutr1 bold face indicates K/As common to both RO and SRO SYSTEM #/
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 21 239002 / Relief/Safety Valves X
K6.03 - AC power: Plant Specific 2.7/2.9 1
22 241000 / Reactor/Turbine Pressure Regulating System
/ 3 X
K1.19 - Turbine acceleration 2.6/2.6 1
23 259001 / Reactor Feedwater System / 2 X
2.4.12 - Knowledge of general operating crew responsibilities during emergency operations.
3.4/3.9 1
24 259002 / Reactor Water Level Control System / 2 X
2.2.11 - Knowledge of the process for controlling temporary changes 2.5/3.4 1
25 261000 / Standby Gas Treatment X
A1.03 - Offsite release levels 3.2/3.8 1
26 261000 / Standby Gas Treatment X
A3.02 - Fan start 3.2/3.1 1
27 264000 / Emergency generators (Diesel/Jet)
X A1.04 0 Crank case temperature and pressure 2.6/2.7 1
28 264000 / Emergency generators (Diesel/Jet)
X A2.10 - LOCA 3.9/4.2 1
Category Point Totals:
3 2
3 2
3 3
3 3
2 2
2 Group Point Total: 28 28
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: February 2001 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 11 rooutr1 bold face indicates K/As common to both RO and SRO PLANT SYSTEMS - TIER 2 GROUP II BWR - Reactor OperatorTarget: 19%Actual: 19%
SYSTEM #/
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
201004 / Rod Sequence Control System (Plant Specific)
X K5.02 - Sequence and groups: BWR-4, 5 3.1/3.3 1
2 201003 / Control Rod and Drive Mechanism A
A4.02 - CRD mechanism position: Plant Specific 3.5/3.5 1
3 215002 / Rod Block Monitor X
K2.01 - RBM channels: BWR 3, 4, and 5 2.5/2.8 1
4 219000 / RHR/LPCI:
Torus/Suppression Pool Cooling Mode X
K1.01 - Suppression Pool 3.8/3.9 1
5 219000 / RHR/LPCI:
Torus/Suppression Pool Cooling Mode X
A1.01 - Suppression Pool Temperature 4.0/4.0 1
6 226001 / RHR/LPCI:
Containment Spray System Mode X
K2.02 - Pumps 2.9/2.9 1
7 226001 / RHR/LPCI:
Containment Spray System Mode X
K3.03 - Containment/Drywell/Suppression Chamber components, continued operation with elevated pressure and/or temperature and/or level 2.9/3.2 1
8 230000 / RHR/LPCI:
Torus/Suppression Pool Spray Mode X
K4.03 - Unintentional reduction in vessel injection flow during accident conditions 3.5/3.6 1
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: February 2001 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 12 rooutr1 bold face indicates K/As common to both RO and SRO SYSTEM #/
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
239001 / Main and Reheat Steam X
K6.02 - Plant air systems 3.2/3.2 1
10 262001 / AC Electrical Distribution X
A4.01 - All breakers and disconnects (including available switch yard):
Plant specific 3.4/3.4 1
11 262002 / Uninterruptable Power Supply (AC/DC) x K3.15 - Main turbine operation: Plant specific 2.6/2.7 1
12 262002 / Uninterruptable Power Supply (AC/DC)
X A3.01 - Transfer from preferred to alternate source 2.8/3.1 1
13 263000 / DC Electrical Distribution X
A3.01 - Meters, dials, recorders, alarms, and indicating lights 3.2/3.3 1
14 263000 / DC Electrical Distribution X
K4.02 - Breaker interlocks, permissives, bypasses and cross ties: Plant Specific 3.1/3.5 1
15 272000 / Radiation Monitoring System X
K6.01 - Reactor protection system 3.0/3.2 1
16 290003 / Control Room HVAC X
A1.04 - Control room pressure 2.5/2.8 1
17 300000 / Instrument Air System X
K1.05 - Main Steam isolation valve air 3.1/3.2 1
18 300000 / Instrument Air System X
K5.01 - Air Compressors 2.5/2.5 1
19 400000 / Component Cooling Water System X
A2.03 - High/Low CCW temperature 2.9/3.0 1
Category Point Totals:
2 2
2 2
2 2
2 2
2 1
0 Group point totals: 19 19
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: February 2001 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 13 rooutr1 bold face indicates K/As common to both RO and SRO PLANT SYSTEMS - TIER 2 GROUP III BWR - Reactor OperatorTarget: 4%Actual: 4%
SYSTEM #/
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
233000 / Fuel Pool Cooling and Cleanup X
A1.01 - Surge tank level 2.6/2.9 1
2 234000 / Fuel Handling Equipment X
K6.04 - Refueling platform air system: Plant specific 2.9/3.7 1
3 288000 / Plant Ventilation X
K4.02 - Secondary containment isolation 3.7/3.8 1
4 290002 / Reactor Vessel Internals X
K3.07 - Nuclear boiler instrumentation 3.1/3.1 1
Category Point Totals:
0 0
1 1
0 1
1 0
0 0
0 Group point totals:
4
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: February 2001 ref: NUREG - 1021 rev 8 BWR RO EXAM OUTLINE ES-401-2 page 14 rooutr1 bold face indicates K/As common to both RO and SRO PLANT-WIDE GENERIC RESPONSIBILITIES TIER 3 BWR - Reactor OperatorTarget: 13%Actual: 13%
Category K/A TOPICS IMP POINTS 1
2.1.11 Knowledge of less than one hour technical specification action statements for systems 3.0/3.8 1
2 Conduct of 2.1.3 Knowledge of shift turnover practices 3.0/3.4 1
3 Operations 2.1.18 Ability to make accurate, clear and concise logs, records, status boards, and reports 2.9/3.0 1
4 2.1.10 Knowledge of conditions and limitations in the facility license 2.7/3.9 1
5 2.2.22 Knowledge of limiting conditions for operations and safety limits 3.4/4.1 1
6 Equipment 2.2.34 Knowledge of the process for determining the internal and external effects on core reactivity 2.8/3.2 1
7 Control 2.2.26 Knowledge of refueling administrative requirements 2.5/3.7 1
8 2.3.11 Ability to control radiation releases 2.7/3.2 1
9 Radiation 2.3.1 Knowledge of 10CFR20 and related facility radiation control requirements 2.6/3.0 1
10 Control 2.3.2 Knowledge of the facility ALARA Program 2.5/2.9 1
11 2.4.17 Knowledge of EOP terms and conditions 3.5/3.6 1
12 Emergency Proc.
2.4.24 Knowledge of loss of cooling water procedures 3.3/3.7 1
13 Plan 2.4.11 Knowledge of abnormal condition procedures 3.4/3.6 1
Group point totals: 13 13
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: Feb. 22, 2001 ref: NUREG - 1021 rev 8 BWR SRO EXAM OUTLINE ES-401-1 page 1 bold face indicates K/As common to both RO and SRO COUNT MATRIX Summarizing Counts by K/A Group for BWR - Senior Reactor Operator K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G
Total E/APE # - T1 Gp 1 4
3 5
4 7
3 26 E/APE # - T1 Gp 2 3
1 3
3 6
1 17 Tier Totals 7
4 8
7 13 4
43 Plant Systems / T2 Gp 1 2
1 2
3 2
1 2
2 1
2 5
23 Plant Systems / T2 Gp 2 2
1 1
1 1
1 2
1 1
0 2
13 Plant Systems / T2 Gp 3 0
0 0
1 0
1 1
0 0
0 1
4 Tier Totals 4
2 3
5 3
3 5
3 2
2 8
40 Generic K/As / T3 CAT 1 - 7 CAT 2 - 3 CAT 3 - 3 CAT 4 - 4 17 Model Total 100
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: Feb. 22, 2001 ref: NUREG - 1021 rev 8 BWR SRO EXAM OUTLINE ES-401-1 page 2 bold face indicates K/As common to both RO and SRO EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP I BWR - Senior Reactor OperatorTarget: 26%Actual: 26%
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 RO/SRO POINTS 1
295003 / Partial or Complete Loss of AC Power / 6 X
AK3.03 - Load shedding COLUMBIA-IPE 3.5/3.6 1
2 295003 / Partial or Complete Loss of AC Power / 6 X
AA1.02 - Emergency Generators COLUMBIA-IPE 4.2/4.3 1
3 295006 / Scram / 1 X
AA1.04 - Recirculation System 3.1/3.2 1
4 295006 / Scram / 1 X
AA2.02 - Control Rod Position 10CFR55.43.5 4.3/4.4 1
5 295007 / High Reactor Pressure / 3 X
AK2.05 - Shutdown Cooling: Plant Specific 2.9/3.1 1
6 295007 / High Reactor Pressure / 3 X
2.4.1 - Knowledge of EOP Entry Conditions and immediate action steps.
10CFR55.43.5 COLUMBIA-IPE 4.3/4.6 1
7 295010 / High Drywell Pressure / 5 X
2.4.10 - Knowledge of Annunciator Response Procedures 10CFR55.43.5 3.0/3.1 1
8 295013 / High Suppression Pool Temperature / 5 X
AK1.04 - Complete Condensation 2.9/3.2 1
9 295013 / High Suppression Pool Temperature / 5 X
AK2.01 - Suppression Pool Cooling 3.6/3.7 1
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: Feb. 22, 2001 ref: NUREG - 1021 rev 8 BWR SRO EXAM OUTLINE ES-401-1 page 3 bold face indicates K/As common to both RO and SRO 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 295014 / Inadvertent Reactivity Addition / 1 X
AA2.02 - Reactor Period 10CFR55.43.5 3.9/3.9 1
11 295014 / Inadvertent Reactivity Addition / 1 X
AK1.05 - Fuel Thermal Limits COLUMBIA-IPE 3.7/4.2 1
12 295015 / Incomplete Scram / 1 X
AA2.01 - Reactor Power 4.1/4.3 1
13 295015 / Incomplete Scram / 1 X
AK1.02 - Cooldown effects on reactor power COLUMBIA-IPE 3.9/4.1 1
14 295016 / Control Room Abandonment / 7 X
AK3.01 - Reactor Scram 4.1/4.2 1
15 295016 / Control Room Abandonment / 7 X
AA1.06 - Reactor Water Level 4.0/4.1 1
16 295023 / Refueling Accidents / 8 X
2.1.11 - Knowledge of less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Tech Spec action statements for systems 10CFR55.43.2 3.0/3.8 1
17 295024 / High Drywell Pressure / 5 X
EA1.16 - Containment/drywell vacuum breakers 3.4/3.4 1
18 295025 / High Reactor Pressure / 3 X
EK1.06 - Pressure effects on reactor water level 3.5/3.6 1
19 295025 / High Reactor Pressure / 3 X
Ek3.01 - Safety/relief valve opening COLUMBIA-IPE 4.2/4.3 1
20 295030 / Low Suppression Pool Water Level / 5 X
EK2.05 - HPCS: Plant Specific 3.8/3.9 1
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: Feb. 22, 2001 ref: NUREG - 1021 rev 8 BWR SRO EXAM OUTLINE ES-401-1 page 4 bold face indicates K/As common to both RO and SRO 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 21 295031 / Reactor Low Water Level / 2 X
Ek3.01 - Automatic Depressurization System actuation COLUMBIA-IPE 3.9/4.2 1
22 295031 / Reactor Low Water Level / 2 X
EA2.01 - Reactor Water Level 10CFR55.43.5 4.6/4.6 1
23 295037 / SCRAM Condition present and reactor power above APRM downscale or unknown / 1 X
EA2.06 - Reactor Pressure 10CFR55.43.5 COLUMBIA-IPE 4.0/4.1 1
24 295038 / High Offsite Release Rate / 9 X
EA2.04 - Source of offsite release 10CFR55.43.5 4.1/4.5 1
25 500000 / High Containment Hydrogen Concentration / 5 X
EK3.04 - Emergency Depressurization 3.1/3.9 1
26 500000 / High Containment Hydrogen Concentration / 5 X
EA2.04 - Combustible limits for wetwell 3.3/3.3 1
Category Point Totals:
4 3
5 4
7 3
Group Point Totals: 26 26
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: Feb. 22, 2001 ref: NUREG - 1021 rev 8 BWR SRO EXAM OUTLINE ES-401-1 page 5 bold face indicates K/As common to both RO and SRO EMERGENCY & ABNORMAL PLANT EVOLUTIONS - TIER 1 GROUP II BWR - Senior Reactor OperatorTarget: 17%Actual: 17%
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
295004 / Partial or complete loss of DC power / 6 X
AK1.04 - Effect of battery discharge rate on capacity COLUMBIA-IPE 2.8/2.9 1
2 295005 / Main Turbine Generator Trip / 3 X
AA2.01 - Turbine Speed 10CFR55.43.5 2.6/2.7 1
3 295005 / Main Turbine Generator Trip / 3 X
AA1.01 - Recirculation System: Plant Specific COLUMBIA-IPE 3.1/3.3 1
4 295002 / Loss of Main Condenser Vacuum / 3 X
AA2.04 - Offgas System flow - 10CFR55.43.5 2.8/2.9 5
295012 / High Drywell Temperature / 5 X
2.1.12 - Ability to apply Tech Specs for a system 10CFR55.43.2/43.5 2.9/4.0 1
6 295012 / High Drywell Temperature / 5 X
AK2.02 - Drywell cooling 3.6/3.7 1
7 295018 / Partial or complete loss of Component Cooling Water / 8 X
AK1.01 - Effects on component/systems operations 3.5/3.6 1
8 295018 / Partial or complete loss of Component Cooling Water / 8 X
AA1.02 - System loads 3.3/3.4 1
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: Feb. 22, 2001 ref: NUREG - 1021 rev 8 BWR SRO EXAM OUTLINE ES-401-1 page 6 bold face indicates K/As common to both RO and SRO 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
295021 / Loss of Shutdown Cooling / 4 X
AK3.03 - Increasing drywell cooling 2.9/2.9 1
10 295022 / Loss of CRD Pumps / 1 X
AA1.04 - Reactor Waster Cleanup System: Plant Specific 2.5/2.6 1
11 295028 / High Drywell Temperature / 5 X
EK3.04 - Increase Drywell Cooling 3.6/3.8 1
12 295032 / High Sec Cont Area Temp / 5 X
EA2.01 - Area temperature 10CFR55.43.5 3.8/3.8 1
13 295033 / High Sec Cont Area Rad Levels / 9 X
EA2.02 - Equipment operability 10CFR55.43.5 3.1/3.2 1
14 295034 / Sec Cont Ventilation High Rad / 9 X
EA2.01 - Ventilation radiation levels 10CFR55.43.5 3.8/4.2 1
15 295035 / Sec Cont High Differential Press / 5 X
EK1.02 - Radiation release 3.7/4.2 1
16 295036 / Sec Cont High Sump/Area Water Level
/ 5 X
EK3.03 - Isolating affected systems COLUMBIA-IPE 3.5/3.6 1
17 295036 / Sec Cont High Sump/Area Water Level /
5 X
EA2.03 - Cause of the high water level 10CFR55.43.5 3.4/3.8 1
Category Point Totals:
3 1
3 3
6 1
Group point totals: 17 17
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: Feb. 22, 2001 ref: NUREG - 1021 rev 8 BWR SRO EXAM OUTLINE ES-401-1 page 7 bold face indicates K/As common to both RO and SRO PLANT SYSTEMS - TIER 2 GROUP I BWR - Senior Reactor OperatorTarget: 23%Actual: 23%
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
209001 / Low Pressure Core Spray X
K1.12 - Eccs room coolers 2.9/3.1 1
2 209001 / Low Pressure Core Spray X
K5.04 - Heat removal (transfer) mechanisms 2.8/2.9 1
3 209002 / High Pressure Core Spray X
A4.01 - HPCS pump: BWR 5 and 6 3.7/3.7 1
4 218000 / Automatic Depressurization Sys X
2.4.1 - Knowledge of EOP entry conditions and immediate action steps 10CFR55.43.5 4.3/4.6 1
5 211000 / Standby Liquid Control X
K1.09 - Core spray system: Plant specific 3.2/3.4 1
6 212000 / Reactor Protection System X
K2.02 - Analog trip system logic cabinets 2.7/2.9 1
7 215005 / Average Power Range Monitor/Local Power Range Monitor / 7 X
K4.06 - Effects of detector aging on LPRM/APRM readings 2.6/2.8 1
8 216000 / Nuclear Boiler Instrumentation / 7 X
K3.11 - MSIV Leakage control system: Plant Specific 2.8/2.8 1
9 216000 / Nuclear Boiler Instrumentation / 7 X
2.4.38 - Ability to take actions called for in the Emergency Plan including supporting or acting as the Emergency Director 2.2/4.0 1
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: Feb. 22, 2001 ref: NUREG - 1021 rev 8 BWR SRO EXAM OUTLINE ES-401-1 page 8 bold face indicates K/As common to both RO and SRO 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 10 217000 / Reactor Core Isolation Cooling X
K6.01 - Electrical power 3.4/3.5 1
11 218000 / Automatic Depressurization Sys.
X K5.01 - ADS logic operation 3.8/3.8 1
12 223002 / Pri Cont Isolation Sys/ Nuclear Steam Supply Shutoff x
K3.10 - Reactor water cleanup 2.9/3.1 1
13 223002 / Pri Cont Isolation Sys/ Nuclear Steam Supply Shutoff X
2.2.22 - Knowledge of limiting condition for operations and safety limits 10CFR55.43.2 2.3/3.5 1
14 226001 / RHR/LPCI:
Containment Spray Mode X
A2.17 - High containment/drywell temperature 3.2/3.2 1
15 262001 / AC Electrical Distribution X
2.4.35 - Knowledge of local operator actions during emergency operations including geography and system implications 10CFR55.43.5 3.3/3.5 1
16 239002 / Relief/Safety Valves X
A2.04 - ADS actuation 4.1/4.2 1
17 241000 / Reactor/Turbine Pressure Regulating Sys X
K4.19 - Steam Bypass valve control 3.6/3.7 1
18 259002 / Reactor Water Level Control X
A4.07 - All individual component controllers when transferring from automatic to manual mode 3.8/3.6 1
19 261000 / Standby Gas Treatment X
A1.03 - Offsite release levels 3.2/3.8 1
20 261000 / Standby Gas Treatment X
A3.02 - Fan start 3.2/3.1 1
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: Feb. 22, 2001 ref: NUREG - 1021 rev 8 BWR SRO EXAM OUTLINE ES-401-1 page 9 bold face indicates K/As common to both RO and SRO 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 21 262001 / AC Electrical Distribution X
K4.01 - Bus lockouts 3.0/3.4 1
22 264000 / Emergency generators (Diesel/Jet)
X A1.04 0 Crank case temperature and pressure 2.6/2.7 1
23 290001 / Secondary Containment X
2.4.11 - Knowledge of abnormal condition procedures 10CFR55.43.5 COLUMBIA-IPE 3.4/3.6 1
Category Point Totals:
2 1
2 3
2 1
2 2
1 2
5 Group Point Total:
23
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: Feb. 22, 2001 ref: NUREG - 1021 rev 8 BWR SRO EXAM OUTLINE ES-401-1 page 10 bold face indicates K/As common to both RO and SRO PLANT SYSTEMS - TIER 2 GROUP II BWR - Senior Reactor OperatorTarget: 13%Actual: 13%
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
215002 / Rod Block Monitor X
K2.01 - RBM channels: BWR 3, 4, and 5 2.5/2.8 1
2 215003 / Intermediate Range Monitor X
A1.05 - SCRAM and rod block setpoints 3.9/3.9 1
3 219000 / RHR/LPCI:
Torus/Suppression Pool Cooling Mode X
K1.01 - Suppression Pool 3.8/3.9 1
4 219000 / RHR/LPCI:
Torus/Suppression Pool Cooling Mode X
A1.01 - Suppression Pool Temperature 4.0/4.0 1
5 230000 / RHR/LPCI:
Torus/Suppression Pool Spray Mode X
K4.03 - Unintentional reduction in vessel injection flow during accident conditions 3.5/3.6 1
6 234000 / Fuel Handling Equipment X
2.4.46 - Ability to verify that the alarms are consistent with the plant conditions 10CFR55.43.5 3.5/3.6 1
7 234000 / Fuel Handling Equipment x
K6.04 - Refueling platform air system: Plant specific 2.9/3.7 1
8 239003 / MSIV Leakage Control X
2.4.33 - Knowledge of the process to track inoperable alarms 10CFR55.43.5 2.4/2.8 1
9 262002 / Uninterruptable Power Supply (AC/DC) x K3.15 - Main turbine operation: Plant specific 2.6/2.7 1
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: Feb. 22, 2001 ref: NUREG - 1021 rev 8 BWR SRO EXAM OUTLINE ES-401-1 page 11 bold face indicates K/As common to both RO and SRO 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 10 263000 / DC Electrical Distribution X
A3.01 - Meters, dials, recorders, alarms, and indicating lights 3.2/3.3 1
11 300000 / Instrument Air System X
K1.05 - Main Steam isolation valve air 3.1/3.2 1
12 300000 / Instrument Air System X
K5.01 - Air Compressors 2.5/2.5 1
13 400000 / Component Cooling Water System X
A2.03 - High/Low CCW temperature 2.9/3.0 1
Category Point Totals:
2 1
1 1
1 1
2 1
1 0
2 Group point totals: 13 13
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: Feb. 22, 2001 ref: NUREG - 1021 rev 8 BWR SRO EXAM OUTLINE ES-401-1 page 12 bold face indicates K/As common to both RO and SRO PLANT SYSTEMS - TIER 2 GROUP III BWR - Senior Reactor OperatorTarget: 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
233000 / Fuel Pool Cooling and Cleanup X
A1.01 - Surge tank level 2.6/2.9 1
2 239001 / Main and Reheat Steam X
K6.02 - Plant air systems 3.2/3.2 1
3 268000 / Radwaste X
2.1.20 - Ability to execute procedure steps 10CFR55.43.5 4.3/4.2 1
4 288000 / Plant Ventilation X
K4.02 - Secondary containment isolation 3.7/3.8 1
Category Point Totals:
0 0
0 1
0 1
1 0
0 0
1 Group Point Total: 4 4
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: Feb. 22, 2001 ref: NUREG - 1021 rev 8 BWR SRO EXAM OUTLINE ES-401-1 page 13 bold face indicates K/As common to both RO and SRO PLANT-WIDE GENERIC RESPONSIBILITIES TIER 3 BWR - Senior Reactor OperatorTarget: 17%Actual: 17%
Category K/A TOPICS IMP POINTS 1
2.1.7 Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation 10CFR55.43.5 3.7/4.4 1
2 2.1.6 Ability to supervise and assume a management role during plant transients and upset conditions 10CFR55.43.5 2.1/4.3 1
3 Conduct 2.1.11 Knowledge of less than one hour technical specification action statements for systems 3.0/3.8 1
4 of 2.1.3 Knowledge of shift turnover practices 3.0/3.4 1
5 Operations 2.1.14 Knowledge of system status criteria which require the notification of plant personnel 10CFR55.43.5 2.5/3.3 1
6 2.1.32 Ability to explain and apply system limits and precautions 10CFR55.43.2 3.4/3.8 1
7 2.1.12 Ability to apply technical specifications for a system 10CFR55.43.2/43.5 2.9/4.0 1
8 Equipment 2.2.14 Knowledge of the process for making configuration changes 10CFR55.43.3 2.1/3.0 1
9 Control 2.2.20 Knowledge of the process for managing troubleshooting activities 10CFR55.43.5 2.2/3.3 1
10 2.2.22 Knowledge of limiting conditions for operations and safety limits 3.4/4.1 1
11 2.3.6 Knowledge of the requirements for reviewing and approving release permits 10CFR55.43.4 2.1/3.1 1
12 Radiation Control 2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized 10CFR55.43.4 2.5/3.1 1
13 2.3.1 Knowledge of 10CFR20 and related facility radiation control requirements 2.6/3.0 1
Facility: Columbia Generating Station Knowledge and Ability Record Form Exam date: Feb. 22, 2001 ref: NUREG - 1021 rev 8 BWR SRO EXAM OUTLINE ES-401-1 page 14 bold face indicates K/As common to both RO and SRO Category K/A TOPICS IMP POINTS 14 Emergency 2.4.17 Knowledge of EOP terms and conditions 3.5/3.6 1
15 Procedures 2.4.24 Knowledge of loss of cooling water procedures 3.3/3.7 1
16 Plan 2.4.11 Knowledge of abnormal condition procedures 3.4/3.6 1
17 2.4.47 Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material 10CFR55.43.5 3.4/3.7 1
Group point totals: 17 17