ML23012A219
| ML23012A219 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 08/28/2022 |
| From: | Nuclear Management Co, Xcel Energy |
| To: | NRC/RGN-III/DORS/OB |
| Iskierka-Boggs | |
| Shared Package | |
| ML21188A291 | List: |
| References | |
| Download: ML23012A219 (1) | |
Text
Form 4.1-BWR Boiling-Water Reactor Examination Outline Facility: Monticello K/A Catalog Rev. 3 Rev.
0 Date of Exam:
10/17/2022 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
Total A2 G*
Total
- 1.
Emergency and Abnormal Plant Evolutions 1
4 3
4 3
3 3
20 4
3 7
2 1
1 1
1 1
1 6
1 2
3 Tier Totals 5
4 5
4 4
4 26 5
5 10
- 2.
Plant Systems 1
2 2
2 3
3 3
2 3
2 2
2 26 2
3 5
2 1
1 1
1 1
1 2
0 1
1 1
11 0
2 1
3 Tier Totals 3
3 3
4 4
4 4
3 3
3 3
37 4
4 8
- 3.
Generic Knowledge and Abilities Categories CO EC RC EM 6
CO EC RC EM 7
2 2
1 1
2 2
1 2
- 4. Theory Reactor Theory Thermodynamics 6
3 3
Notes: CO =
EM =
Conduct of Operations; EC = Equipment Control; RC = Radiation Control; Emergency Procedures/Plan These systems/evolutions may be eliminated from the sample when Revision 2 of the K/A catalog is used to develop the sample plan.
These systems/evolutions are only included as part of the sample (as applicable to the facility) when Revision 2 of the K/A catalog is used to develop the sample plan.
ES-4.1-BWR BWR Examination Outline (Monticello)
Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)
Item E/APE # / Name /
Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR Q#
1 (295001) (APE 1)
PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION X
(295001AK3.07) Knowledge of the reasons for the following responses or actions as they apply to (APE 1) PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:
(CFR: 41.5 / 41.10 / 45.6 / 45.13) Recirculation pump discharge/suction valve manipulation 3.3 1
2 (295003) (APE 3)
PARTIAL OR COMPLETE LOSS OF AC POWER X
(295003AK2.07) Knowledge of the relationship between the (APE 3) PARTIAL OR COMPLETE LOSS OF AC POWER and the following systems or components: (CFR: 41.8 / 41.10 / 45.3)
DC electrical distribution system 3.7 2
3 (295004) (APE 4)
PARTIAL OR COMPLETE LOSS OF DC POWER X
(295004) (APE 4) PARTIAL OR COMPLETE LOSS OF DC POWER (G2.2.44) EQUIPMENT CONTROL Ability to interpret control room indications to verify the status and operation of a system and understand how operator actions and directives affect plant and system conditions (CFR: 41.5 / 43.5 / 45.12) 4.2 3
4 (295005) (APE 5)
MAIN TURBINE GENERATOR TRIP X
(295005AK1.01) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (APE 5) MAIN TURBINE GENERATOR TRIP: (CFR: 41.5 / 41.7 / 45.7 / 45.8) Reactor pressure control 4.3 4
5 (295006) (APE 6)
SCRAM X
(295006AK3.06) Knowledge of the reasons for the following responses or actions as they apply to (APE 6) SCRAM: (CFR:
41.5 / 41.10 / 45.6 / 45.13) Recirculation pump speed reduction 3.7 5
6 (295016) (APE 16)
CONTROL ROOM ABANDONMENT X
(295016AA2.04) Ability to determine or interpret the following as they apply to (APE 16) CONTROL ROOM ABANDONMENT:
(CFR: 41.10 / 43.5 / 45.13) Suppression pool temperature 4
6 7
(295018) (APE 18)
PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER (CCW)
X (295018AA1.07) Ability to operate or monitor the following as they apply to (APE 18) PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER (CCW): (CFR: 41.5 / 41.7 /
45.5 to 45.8) Fuel pool cooling and cleanup system 3.6 7
8 (295019) (APE 19)
PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR X
(295019AK2.14) Knowledge of the relationship between the (APE 19) PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR and the following systems or components: (CFR: 41.8 /
41.10 / 45.3) Plant Air system 3.5 8
9 (295021) (APE 21)
LOSS OF SHUTDOWN COOLING X
(295021AA2.06) Ability to determine or interpret the following as they apply to (APE 21) LOSS OF SHUTDOWN COOLING:
(CFR: 41.10 / 43.5 / 45.13) Reactor pressure 4.2 9
10 (295023) (APE 23)
REFUELING ACCIDENTS X
(295023AK1.04) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (APE 23) REFUELING ACCIDENTS: (CFR:
41.5 / 41.7 / 45.7 / 45.8) Fuel positioning 3.4 10 11 (295024) (EPE 1)
HIGH DRYWELL PRESSURE X
(295024EK2.06) Knowledge of the relationship between the (EPE 1) HIGH DRYWELL PRESSURE and the following systems or components: (CFR: 41.8 / 41.10 / 45.3) Emergency generators 4.2 11
12 (295025) (EPE 2)
HIGH REACTOR PRESSURE X
(295025) (EPE 2) HIGH REACTOR PRESSURE (G2.1.32)
CONDUCT OF OPERATIONS Ability to explain and apply system precautions, limitations, notes, or cautions (CFR: 41.10 /
43.2 / 45.12) 3.8 12 13 (295026) (EPE 3)
SUPPRESSION POOL HIGH WATER TEMPERATURE X
(295026EK1.04) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (EPE 3) SUPPRESSION POOL HIGH WATER TEMPERATURE: (CFR: 41.5 / 41.7 / 45.7 / 45.8)
Suppression pool level 3.5 13 14 (295028) (EPE 5)
HIGH DRYWELL TEMPERATURE (MARK I AND MARK II ONLY)
X (295028EK3.03) Knowledge of the reasons for the following responses or actions as they apply to (EPE 5) HIGH DRYWELL TEMPERATURE (MARK I AND MARK II ONLY): (CFR: 41.5 /
41.10 / 45.6 / 45.13) Drywell spray 3.8 14 15 (295030) (EPE 7)
LOW SUPPRESSION POOL WATER LEVEL X
(295030EA1.02) Ability to operate or monitor the following as they apply to (EPE 7) LOW SUPPRESSION POOL WATER LEVEL: (CFR: 41.5 / 41.7 / 45.5 to 45.8) RCIC 3.8 15 16 (295031) (EPE 8)
REACTOR LOW WATER LEVEL X
(295031EA1.10) Ability to operate or monitor the following as they apply to (EPE 8) REACTOR LOW WATER LEVEL: (CFR:
41.5 / 41.7 / 45.5 to 45.8) Control rod drive hydraulic system 3.6 16 17 (295037) (EPE 14)
SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN X
(295037EA2.03) Ability to determine or interpret the following as they apply to (EPE 14) SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: (CFR: 41.10 / 43.5 / 45.13) Standby liquid control system tank level 3.8 17 18 (295038) (EPE 15)
HIGH OFFSITE RADIOACTIVITY RELEASE RATE X
(295038EK3.05) Knowledge of the reasons for the following responses or actions as they apply to (EPE 15) HIGH OFFSITE RADIOACTIVITY RELEASE RATE: (CFR: 41.5 / 41.10 / 45.6 /
45.13) Reactor shutdown/SCRAM 4.1 18 19 (600000) (APE 24)
PLANT FIRE ON SITE X
(600000AK1.02) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (APE 24) PLANT FIRE ON SITE: (CFR:
41.5 / 41.7 / 45.7 / 45.8) Firefighting methods for each type of fire 3.4 19 20 (700000) (APE 25)
GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES X
(700000) (APE 25) GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES (G2.4.26) EMERGENCY PROCEDURES/PLAN Knowledge of facility protection requirements, including fire brigade and portable firefighting equipment usage (CFR: 41.10 / 43.5 / 45.12) 3.1 20 21 (295001) (APE 1)
PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION X
(295001) (APE 1) PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION (G2.2.18) EQUIPMENT CONTROL Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments and work prioritization (CFR: 41.10 / 43.5 /
45.13) 3.9 76 22 (295016) (APE 16)
CONTROL ROOM ABANDONMENT X
(295016AA2.03) Ability to determine or interpret the following as they apply to (APE 16) CONTROL ROOM ABANDONMENT: (CFR: 41.10 / 43.5 / 45.13) Reactor pressure 4.2 77 23 (295019) (APE 19)
PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR X
(295019AA2.01) Ability to determine or interpret the following as they apply to (APE 19) PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: (CFR: 41.10 / 43.5 /
45.13) Instrument air pressure 3.9 78
24 (295023) (APE 23)
REFUELING ACCIDENTS X
(295023AA2.05) Ability to determine or interpret the following as they apply to (APE 23) REFUELING ACCIDENTS: (CFR: 41.10 / 43.5 / 45.13) Emergency plan implementation 4.4 79 25 (295024) (EPE 1)
HIGH DRYWELL PRESSURE X
(295024) (EPE 1) HIGH DRYWELL PRESSURE (G2.2.36)
EQUIPMENT CONTROL Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operation. (CFR:
41.10 / 43.2 / 45.13) 4.2 80 26 (295025) (EPE 2)
HIGH REACTOR PRESSURE X
(295025EA2.02) Ability to determine or interpret the following as they apply to (EPE 2) HIGH REACTOR PRESSURE: (CFR: 41.10 / 43.5 / 45.13) Reactor power 4.2 81 27 (295030) (EPE 7)
LOW SUPPRESSION POOL WATER LEVEL X
(295030) (EPE 7) LOW SUPPRESSION POOL WATER LEVEL (G2.1.45) CONDUCT OF OPERATIONS Ability to identify and interpret diverse indications to validate the response of another indication (CFR: 41.7 / 43.5 / 45.4) 4.3 82 (295027) (EPE 4)
HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) / 5 K/A Category Totals:
4 3
4 3
3/4 3/3 Group Point Total:
20/7
ES-4.1-BWR BWR Examination Outline (Monticello)
Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)
Item E/APE # / Name /
Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR Q#
28 (295008) (APE 8)
HIGH REACTOR WATER LEVEL X
(295008AK1.01) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to the (APE 8) HIGH REACTOR WATER LEVEL:
(CFR: 41.5 / 41.7 / 45.7 / 45.8) Moisture carryover 3.3 21 29 (295012) (APE 12)
HIGH DRYWELL TEMPERATURE X
(295012AA2.04) Ability to determine or interpret the following as they apply to (APE 12) HIGH DRYWELL TEMPERATURE:
(CFR: 41.10 / 43.5 / 45.13) System/component operating limitations 3.8 22 30 (295014) (APE 14)
INADVERTENT REACTIVITY ADDITION X
(295014) (APE 14) INADVERTENT REACTIVITY ADDITION (G2.4.46) EMERGENCY PROCEDURES/PLAN Ability to verify that the alarms are consistent with the plant conditions (CFR: 41.10 / 43.5 / 45.3 / 45.12) 4.2 23 31 (295017) (APE 17)
ABNORMAL OFFSITE RELEASE RATE X
(295017AK3.01) Knowledge of the reasons for the following responses or actions as they apply to (APE 17) ABNORMAL OFFSITE RELEASE RATE: (CFR: 41.5 / 41.10 / 45.6 / 45.13)
System isolations 4.0 24 32 (295034) (EPE 11)
SECONDARY CONTAINMENT VENTILATION HIGH RADIATION X
(295034EA1.03) Ability to operate or monitor the following as they apply to (EPE 11) SECONDARY CONTAINMENT VENTILATION HIGH RADIATION: (CFR: 41.5 / 41.7 / 45.5 to 45.8) Secondary containment ventilation 3.8 25 33 (295035) (EPE 12)
SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE X
(295035EK2.04) Knowledge of the relationship between the (EPE 12) SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE and the following systems or components: (CFR: 41.8 / 41.10 / 45.3) Blow-out panels 3.5 26 34 (295010) (APE 10)
HIGH DRYWELL PRESSURE X
(295010AA2.03) Ability to determine or interpret the following as they apply to (APE 10) HIGH DRYWELL PRESSURE: (CFR: 41.10 / 43.5 / 45.13) Drywell radiation levels 3.6 83 35 (295029) (EPE 6)
HIGH SUPPRESSION POOL WATER LEVEL X
(295029) (EPE 6) HIGH SUPPRESSION POOL WATER LEVEL (G2.4.16) EMERGENCY PROCEDURES/PLAN Knowledge of emergency and abnormal operating procedures implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, or severe accident management guidelines (CFR:
41.10 / 43.5 / 45.13) 4.4 84 36 (295032) (EPE 9)
HIGH SECONDARY CONTAINMENT AREA TEMPERATURE X
(295032) (EPE 9) HIGH SECONDARY CONTAINMENT AREA TEMPERATURE (G2.2.13) EQUIPMENT CONTROL Knowledge of tagging and clearance procedures (CFR:
41.10 / 43.1 / 45.13) 4.3 85 (295002) (APE 2)
LOSS OF MAIN CONDENSER VACUUM / 3 (295007) (APE 7)
HIGH REACTOR PRESSURE / 3 (295009) (APE 9)
LOW REACTOR WATER LEVEL / 2
(295011) (APE 11)
HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) / 5 (295013) (APE 13)
HIGH SUPPRESSION POOL TEMPERATURE. / 5 (295020) (APE 20)
INADVERTENT CONTAINMENT ISOLATION / 5 & 7 (295022) (APE 22)
LOSS OF CONTROL ROD DRIVE PUMPS / 1 (295033) (EPE 10)
HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS / 9 (295036) (EPE 13)
SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL / 5 (500000) (EPE 16)
HIGH CONTAINMENT HYDROGEN CONCENTRATION /
5 K/A Category Totals:
1 1
1 1
1/1 1/2 Group Point Total:
6/3
ES-4.1-BWR BWR Examination Outline (Monticello)
Emergency and Abnormal Plant EvolutionsTier 2/Group 1 (RO/SRO)
Item System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
37 (203000) (SF2, SF4 RHR/LPCI)
RHR/LPCI:
INJECTION MODE X
(203000A1.01) Ability to predict and/or monitor changes in parameters associated with operation of the (SF2, SF4 RHR/LPCI)
RHR/LPCI: INJECTION MODE including: (CFR:
41.5 / 45.5) Reactor water level 4.4 27 38 (205000) (SF4 SCS)
SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE)
X (205000) (SF4 SCS)
SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) (G2.4.22)
EMERGENCY PROCEDURES/PLAN Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations (CFR: 41.7 / 41.10
/ 43.5 / 45.12) 3.6 28 39 (205000) (SF4 SCS)
SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE)
X (205000K1.08) Knowledge of the physical connections and/or cause and effect relationships between the (SF4 SCS) SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) and the following systems: (CFR: 41.2 to 41.9 /
45.7 to 45.8) RHR/LPCI 3.7 29 40 (206000) (SF2, SF4 HPCI) HIGH PRESSURE COOLANT INJECTION SYSTEM X
(206000K4.19) Knowledge of (SF2, SF4 HPCI) HIGH PRESSURE COOLANT INJECTION SYSTEM design features and/or interlocks that provide for the following:
(CFR: 41.7) Automatic transfer of HPCI pump suction 3.7 30 41 (209001) (SF2, SF4 LPCS) LOW PRESSURE CORE SPRAY SYSTEM X
(209001A4.02) Ability to manually operate and/or monitor the (SF2, SF4 LPCS)
LOW PRESSURE CORE SPRAY SYSTEM in the control room: (CFR: 41.7 /
45.5 to 45.8) Valves 4.2 31 42 (211000) (SF1 SLCS) STANDBY LIQUID CONTROL SYSTEM X
(211000A3.09) Ability to monitor automatic operation of the (SF1 SLCS) STANDBY LIQUID CONTROL SYSTEM including: (CFR: 41.7 / 45.7)
Pump trip 3.8 32 43 (212000) (SF7 RPS)
(212000K5.02) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF7 RPS) REACTOR PROTECTION SYSTEM :
(CFR: 41.5 / 45.3) Logic channel arrangements 4.1 33
44 (215003) (SF7 IRM)
INTERMEDIATE RANGE MONITOR SYSTEM X
(215003A1.05) Ability to predict and/or monitor changes in parameters associated with operation of the (SF7 IRM)
INTERMEDIATE RANGE MONITOR SYSTEM including: (CFR: 41.5 / 45.5)
SCRAM and rod block trip setpoints 3.9 34 45 (215004) (SF7 SRMS) SOURCE RANGE MONITOR SYSTEM X
(215004K6.01) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF7 SRMS) SOURCE RANGE MONITOR SYSTEM : (CFR:
41.7 / 45.7) RPS 3.3 35 46 (215005) (SF7 PRMS) AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR X
(215005A2.02) Ability to (a) predict the impacts of the following on the (SF7 PRMS)
AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR:
41.5 / 45.6) Upscale or downscale trips 4.1 36 47 (217000) (SF2, SF4 RCIC) REACTOR CORE ISOLATION COOLING SYSTEM X
(217000A3.07) Ability to monitor automatic operation of the (SF2, SF4 RCIC)
REACTOR CORE ISOLATION COOLING SYSTEM including: (CFR:
41.7 / 45.7) Trips and isolations 4.2 37 48 (217000) (SF2, SF4 RCIC) REACTOR CORE ISOLATION COOLING SYSTEM X
(217000K6.13) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF2, SF4 RCIC) REACTOR CORE ISOLATION COOLING SYSTEM : (CFR: 41.7 / 45.7)
Low pump suction pressure 3.7 38 49 (218000) (SF3 ADS)
AUTOMATIC DEPRESSURIZATI ON SYSTEM X
(218000K2.01) (SF3 ADS)
AUTOMATIC DEPRESSURIZATION SYSTEM Knowledge of electrical power supplies to the following: (CFR: 41.7)
ADS logic 4.0 39 50 (223002) (SF5 PCIS) PRIMARY CONTAINMENT ISOLATION SYSTEM /
NUCLEAR STEAM SUPPLY SHUTOFF X
(223002A2.07) Ability to (a) predict the impacts of the following on the (SF5 PCIS)
PRIMARY CONTAINMENT ISOLATION SYSTEM /
NUCLEAR STEAM SUPPLY SHUTOFF and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR:
41.5 / 45.6) Various process instrumentation failures 3.6 40
51 (239002) (SF3 SRV)
(239002A4.01) Ability to manually operate and/or monitor the (SF3 SRV)
SAFETY RELIEF VALVES in the control room: (CFR: 41.7 /
45.5 to 45.8) SRVs 4.4 41 52 (259002) (SF2 RWLCS) REACTOR WATER LEVEL CONTROL SYSTEM X
(259002K5.06) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF2 RWLCS) REACTOR WATER LEVEL CONTROL SYSTEM: (CFR: 41.5 / 45.3)
Pump runout 3.2 42 53 (261000) (SF9 SGTS) STANDBY GAS TREATMENT SYSTEM X
(261000K6.01) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF9 SGTS) STANDBY GAS TREATMENT SYSTEM :
(CFR: 41.7 / 45.7) AC electrical distribution 3.5 43 54 (262001) (SF6 AC)
AC ELECTRICAL DISTRIBUTION X
(262001A2.12) Ability to (a) predict the impacts of the following on the (SF6 AC) AC ELECTRICAL DISTRIBUTION and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR:
41.5 / 45.6) Station blackout 4.6 44 55 (262001) (SF6 AC)
AC ELECTRICAL DISTRIBUTION X
(262001K4.04) Knowledge of (SF6 AC) AC ELECTRICAL DISTRIBUTION design features and/or interlocks that provide for the following:
(CFR: 41.7) Protective relaying 3.5 45 56 (262002) (SF6 UPS)
UNINTERRUPTABL E POWER SUPPLY (AC/DC)
X (262002K4.01) Knowledge of (SF6 UPS)
UNINTERRUPTABLE POWER SUPPLY (AC/DC) design features and/or interlocks that provide for the following: (CFR: 41.7)
Transfer of power supplies 3.5 46 57 (218000) (SF3 ADS)
AUTOMATIC DEPRESSURIZATI ON SYSTEM X
(218000K5.01) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF3 ADS) AUTOMATIC DEPRESSURIZATION SYSTEM: (CFR: 41.5 / 45.3)
ADS logic operation 4.3 47 58 (263000) (SF6 DC)
DC ELECTRICAL DISTRIBUTION X
(263000K2.01) (SF6 DC) DC ELECTRICAL DISTRIBUTION Knowledge of electrical power supplies to the following: (CFR: 41.7)
Operationally significant DC loads 4.0 48
59 (264000) (SF6 EGE)
EMERGENCY GENERATORS (DIESEL/JET)
X (264000K3.02) Knowledge of the effect that a loss or malfunction of the (SF6 EGE)
EMERGENCY GENERATORS (DIESEL/JET) will have on the following systems or system parameters: (CFR:
41.7 / 45.4) AC electrical distribution 4.4 49 60 (300000) (SF8 IA)
INSTRUMENT AIR SYSTEM X
(300000K1.26) Knowledge of the physical connections and/or cause and effect relationships between the (SF8 IA) INSTRUMENT AIR SYSTEM and the following systems: (CFR: 41.4 to 41.9 /
45.6 to 45.8) Reactor water cleanup system 3.2 50 61 (400000) (SF8 CCS)
COMPONENT COOLING WATER SYSTEM X
(400000) (SF8 CCS)
COMPONENT COOLING WATER SYSTEM (G2.4.12)
EMERGENCY PROCEDURES/PLAN Knowledge of operating crew responsibilities during emergency and abnormal operations (CFR: 41.10 /
45.12) 4 51 62 (510000) (SF4 SWS*) SERVICE WATER SYSTEM X
(510000K3.10) Knowledge of the effect that a loss or malfunction of the (SF4 SWS*) SERVICE WATER SYSTEM will have on the following systems or system parameters: (CFR: 41.7 /
45.4) Radiation monitoring system 2.5 52 63 (203000) (SF2, SF4 RHR/LPCI)
RHR/LPCI:
INJECTION MODE X
(203000A2.16) Ability to (a) predict the impacts of the following on the (SF2, SF4 RHR/LPCI) RHR/LPCI:
INJECTION MODE and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR:
41.5 / 43.5 / 45.6) Loss of coolant accident 4.4 86 64 (212000) (SF7 RPS)
(212000) (SF7 RPS)
REACTOR PROTECTION SYSTEM (G2.4.30)
EMERGENCY PROCEDURES/PLAN Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator (CFR: 41.10 / 43.5 /
45.11) 4.1 87
65 (218000) (SF3 ADS)
AUTOMATIC DEPRESSURIZATI ON SYSTEM X
(218000) (SF3 ADS)
AUTOMATIC DEPRESSURIZATION SYSTEM (G2.1.9)
CONDUCT OF OPERATIONS Ability to direct licensed personnel activities inside the control room (SRO only) (CFR: 43.1
/ 45.5 / 45.12 / 45.13) 4.5 88 66 (239002) (SF3 SRV)
(239002) (SF3 SRV)
SAFETY RELIEF VALVES (G2.2.45) EQUIPMENT CONTROL Ability to determine or interpret technical specifications with action statements of greater than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (SRO Only) (CFR: 43.2 / 43.5 /
45.3) 4.7 89 67 (264000) (SF6 EGE)
EMERGENCY GENERATORS (DIESEL/JET)
X (264000A2.09) Ability to (a) predict the impacts of the following on the (SF6 EGE)
EMERGENCY GENERATORS (DIESEL/JET) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR:
41.5 / 43.5 / 45.6) Loss of safety bus 4.3 90 (207000) (SF4 IC)
ISOLATION (EMERGENCY)
CONDENSER (209002) (SF2, SF4 HPCS) HIGH PRESSURE CORE SPRAY SYSTEM K/A Category Totals:
2 2
2 3
3 3
2 3/2 2
2 2/3 Group Point Total:
26/5
ES-4.1-BWR BWR Examination Outline (Monticello)
Emergency and Abnormal Plant EvolutionsTier 2/Group 2 (RO/SRO)
Item System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR Q#
68 (290003) (SF9 CRV)
CONTROL ROOM VENTILATION X
(290003K1.01) Knowledge of the physical connections and/or cause and effect relationships between the (SF9 CRV) CONTROL ROOM VENTILATION SYSTEM and the following systems: (CFR: 41.2 to 41.9 /
45.7 to 45.8) Radiation Monitoring System 3.5 53 69 (214000) (SF7 RPIS) ROD POSITION INFORMATION SYSTEM X
(214000K4.04) Knowledge of (SF7 RPIS) ROD POSITION INFORMATION SYSTEM design features and/or interlocks that provide for the following: (CFR: 41.7)
Detection of a drifting control rod 3.9 54 70 (215001) (SF7 TIP)
TRAVERSING IN CORE PROBE X
(215001K2.01) (SF7 TIP)
TRAVERSING IN CORE PROBE Knowledge of electrical power supplies to the following: (CFR: 41.7)
Shear valves (BWR 2, 3, 4, 5) 3.1 55 71 (230000) (SF5 RHR SPS) RHR/LPCI:
TORUS/SUPPRESS ION POOL SPRAY MODE X
(230000K6.12) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF5 RHR SPS) RHR/LPCI:
TORUS/SUPPRESSION POOL SPRAY MODE: (CFR:
41.7 / 45.7) Low suppression pool level 3.7 56 72 (233000) (SF9 FPCCU) FUEL POOL COOLING/CLEANU P
X (233000A1.02) Ability to predict and/or monitor changes in parameters associated with operation of the (SF9 FPCCU) FUEL POOL COOLING/CLEANUP including: (CFR: 41.5 / 45.5)
Fuel pool level 3.6 57 73 (234000) (SF8 FH)
FUEL HANDLING X
(234000A4.03) Ability to manually operate and/or monitor the (SF8 FH) FUEL HANDLING in the control room: (CFR: 41.7 / 45.5 to 45.8) Mode switch 3.7 58 74 (239001) (SF3, SF4 MRSS) MAIN AND REHEAT STEAM SYSTEM X
(239001A1.09) Ability to predict and/or monitor changes in parameters associated with operation of the (SF3, SF4 MRSS) MAIN AND REHEAT STEAM SYSTEM including: (CFR:
41.5 / 45.5) Main steam flow 3.7 59 75 (245000) (SF4 MTGEN) MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS X
(245000) (SF4 MTGEN)
MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS (G2.4.25) EMERGENCY PROCEDURES/PLAN Knowledge of fire protection procedures (CFR: 41.10 /
43.5 / 45.13) 3.3 60
76 (256000) (SF2 CDS)
CONDENSATE SYSTEM X
(256000K3.14) Knowledge of the effect that a loss or malfunction of the (SF2 CDS)
CONDENSATE SYSTEM will have on the following systems or system parameters: (CFR: 41.7 /
45.4) Exhaust hood spray system 2.5 61 77 (286000) (SF8 FPS)
FIRE PROTECTION SYSTEM X
(286000A3.06) Ability to monitor automatic operation of the (SF8 FPS) FIRE PROTECTION SYSTEM including: (CFR: 41.7 / 45.7)
Fire dampers 2.8 62 78 (510001) (SF8 CWS*)
(510001K5.03) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF8 CWS*) CIRCULATING WATER SYSTEM: (CFR:
41.5 / 45.3) Pipe rupture 3.3 63 79 (202001) (SF1, SF4 RS)
RECIRCULATION SYSTEM X
(202001A2.22) Ability to (a) predict the impacts of the following on the (SF1, SF4 RS) RECIRCULATION SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR:
41.5 / 43.5 / 45.6) Loss of component cooling water 3.2 91 80 (290001) (SF5 SC)
(290001A2.01) Ability to (a) predict the impacts of the following on the (SF5 SC)
SECONDARY CONTAINMENT and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations: (CFR:
41.5 / 43.5 / 45.6) Personnel airlock failure 3.3 92 81 (290002) (SF4 RVI)
REACTOR VESSEL INTERNALS X
(290002) (SF4 RVI)
REACTOR VESSEL INTERNALS (G2.4.4)
EMERGENCY PROCEDURES/PLAN Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures (CFR: 41.10 / 43.2 / 45.6) 4.7 93 (201001) (SF1 CRDH) CRD HYDRAULIC SYSTEM (201002) (SF1 RMCS) REACTOR MANUAL CONTROL SYSTEM
(201003) (SF1 CRDM) CONTROL ROD AND DRIVE MECHANISM (290003) (SF9 CRV)
CONTROL ROOM VENTILATION (201005) (SF1, SF7 RCIS) ROD CONTROL AND INFORMATION SYSTEM (201006) (SF7 RWMS) ROD WORTH MINIMIZER SYSTEM (202002) (SF1 RSCTL)
RECIRCULATION FLOW CONTROL SYSTEM (204000) (SF2 RWCU) REACTOR WATER CLEANUP SYSTEM (215002) (SF7 RBMS) ROD BLOCK MONITOR SYSTEM (216000) (SF7 NBI)
NUCLEAR BOILER INSTRUMENTATIO N
(219000) (SF5 RHR SPC) RHR/LPCI:
TORUS/SUPPRESS ION POOL COOLING MODE (223001) (SF5 PCS)
PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES (226001) (SF5 RHR CSS) RHR/LPCI:
CONTAINMENT SPRAY MODE SYSTEM MODE (239003) (SF9 MSVLCS) MAIN STEAM ISOLATION VALVE LEAKAGE CONTROL SYSTEM (241000) (SF3 RTPRS)
REACTOR/TURBIN E PRESSURE REGULATING SYSTEM (259001) (SF2 FWS)
FEEDWATER SYSTEM (268000) (SF9 RW)
RADWASTE SYSTEM
(271000) (SF9 OG)
OFFGAS SYSTEM (272000) (SF7, SF9 RMS) RADIATION MONITORING SYSTEM (288000) (SF9 PVS)
PLANT VENTILATION SYSTEMS K/A Category Totals:
1 1
1 1
1 1
2 0/2 1
1 1/1 Group Point Total:
11/3
Form 4.1-COMMON Common Examination Outline ES-4.1-COMMON COMMON Examination Outline (Monticello)
Facility:
Monticello Date of Exam:
10/28/2022 Generic Knowledge and Abilities Outline (Tier 3) (RO/SRO)
Category K/A #
Topic RO SRO-Only Item #
IR Q#
IR Q#
- 1.
Conduct of Operations G2.1.2 (G2.1.2) CONDUCT OF OPERATIONS Knowledge of operator responsibilities during any mode of plant operation (CFR: 41.10 / 43.1 / 45.13) 82 4.1 64 G2.1.19 (G2.1.19) CONDUCT OF OPERATIONS Ability to use available indications to evaluate system or component status (CFR: 41.10 / 45.12) 83 3.9 65 G2.1.5 (G2.1.5) CONDUCT OF OPERATIONS Ability to use procedures related to shift staffing, such as minimum crew complement or overtime limitations (reference potential) (CFR: 41.10 / 43.5 / 45.12) 84 3.9 94 G2.1.36 (G2.1.36) CONDUCT OF OPERATIONS Knowledge of procedures and limitations involved in core alterations (CFR: 41.10 / 43.6 / 45.7) 85 4.1 95 Subtotal N/A 2
N/A 2
- 2.
Equipment Control G2.2.22 (G2.2.22) EQUIPMENT CONTROL Knowledge of limiting conditions for operation and safety limits (CFR: 41.5 / 43.2 / 45.2) 86 3.1 66 G2.2.42 (G2.2.42) EQUIPMENT CONTROL Ability to recognize system parameters that are entry-level conditions for technical specifications (CFR: 41.7 / 41.10 / 43.2 / 43.3 /
45.3) 87 3.9 67 G2.2.7 (G2.2.7) EQUIPMENT CONTROL Knowledge of the process for conducting infrequently performed tests or evolutions (CFR: 41.10 / 43.3 / 45.13) 88 3.6 96 G2.2.36 (G2.2.5) EQUIPMENT Knowledge of the process for making design or operating changes to the facility, such as 10 CFR 50.59, Changes, Tests and Experiments, screening and evaluation processes, administrative processes for temporary modifications, disabling annunciators, or installation of temporary equipment. (CFR: 41.10 / 43.3 / 45.13) 89 3.2 97 Subtotal N/A 2
N/A 2
- 3.
Radiation Control G2.3.5 (G2.3.5) RADIATION CONTROL Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms or personnel monitoring equipment (CFR:
41.11 / 41.12 / 43.4 / 45.9) 90 2.9 68 G2.3.11 (G2.3.11) RADIATION CONTROL Ability to control radiation releases (CFR:
41.11 / 43.4 / 45.10) 91 4.3 98 Subtotal N/A 1
N/A 1
- 4.
Emergency Procedures /
Plan G2.4.42 (G2.4.42) EMERGENCY PROCEDURES/PLAN Knowledge of emergency response facilities (CFR: 41.10 / 45.11) 92 2.6 69 G2.4.40 (G2.4.40) EMERGENCY PROCEDURES/PLAN Knowledge of SRO responsibilities in emergency plan implementing procedures (CFR: 43.5 /
45.11) 93 4.5 99 G2.4.23 (G2.4.23) EMERGENCY PROCEDURES/PLAN Knowledge of the bases for prioritizing emergency operating procedures implementation (CFR: 41.10 /
43.5 / 45.13) 94 4.4 100 Subtotal N/A 1
N/A 2
Tier 3 Point Total N/A 6
N/A 7
Form 4.1-COMMON Common Examination Outline ES-4.1-COMMON COMMON Examination Outline (Monticello)
Facility:
Monticello Date of Exam:
10/28/2022 Theory (Tier 4) (RO)
Category K/A #
Topic RO Item #
IR Q#
Reactor Theory 292001 (292001K1.08) NEUTRONS (CFR: 41.1) Describe fast flux, thermal flux, and flux distribution 95 2.4 70 292002 (292002K1.09) NEUTRON LIFE CYCLE (CFR: 41.1) Define K-excess (excess reactivity) 96 2.6 71 292006 (292006K1.04) FISSION PRODUCT POISONS (CFR: 41.1) Describe the removal of xenon-135 97 2.9 72 Subtotal 3
Thermodynamics 293003 (293003K1.23) STEAM (CFR: 41.14) Use saturated and superheated steam tables 98 3.1 73 293004 (293004K1.14) THERMODYNAMIC PROCESS (CFR: 41.14) (CONDENSERS)
Explain the condensing process 99 2.7 74 293008 (293008K1.08) THERMAL HYDRAULICS (CFR: 41.14) (POOL BOILING CURVE (TEMPERATURE VS. HEAT FLUX)) Describe departure from nucleate boiling 100 3.1 75 Subtotal 3
Tier 3 Point Total N/A 6