ML23114A146
| ML23114A146 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/23/2023 |
| From: | Heather Gepford NRC/RGN-IV/DORS/OB |
| To: | Entergy Operations |
| References | |
| Download: ML23114A146 (1) | |
Text
Form 4.1-PWR Pressurized-Water Reactor Examination Outline Page 1 of 16 Facility: ANO 2 Revision 1 Date of Exam: 3/15/2023 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
3 3
3 3
3 3
18 3
3 6
2 1
2 1
2 1
1 8
2 2
4 Tier Totals 4
5 4
5 4
4 26 5
5 10
- 2.
Plant Systems 1
3 2
2 4
2 2
2 3
3 2
3 28 3
2 5
2 0
1 1
0 0
2 3
1 0
0 1
9 0
1 2
3 Tier Totals 3
3 3
4 2
4 5
4 3
2 4
37 4
4 8
- 3.
Generic Knowledge and Abilities Categories 6
CO EC RC EM 7
2 2
1 1
2 2
1 2
- 4. Theory Reactor Theory Thermodynamics 6
3 3
Notes: CO = Conduct of Operations; EC = Equipment Control; RC = Radiation Control; EM = 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 CO EC RC EM
Page 2 of 16 ES-4.1-PWR ANO 2 E/APE # / Name /
Safety Function K1 K2 K3 IR Q#
1 (000007) (EPE 7; BW E02 & E10; CE E02) Reactor Trip, Stabilization, Recovery X
(CE02EK3.11) Knowledge of the reasons for the following responses and/or actions as they apply to (CE E02)
STANDARD POST TRIP ACTIONS AND REACTOR TRIP RECOVERY (CFR: 41.5 / 41.10 / 45.6 / 45.13): Actions and/or contingency actions to verify containment isolation during standard post trip actions 4.1 1
2 (000008) (APE 8)
Pressurizer Vapor Space Accident X
(000008AA1.01) Ability to operate and/or monitor the following as they apply to (APE 8) PRESSURIZER VAPOR Space Accident (CFR: 41.5 / 41.7 / 45.5 to 45.8): PZR spray block valve and/or PORV block valve 4.0 2
3 (000009) (EPE 9)
Small Break LOCA X
(000009EK1.03) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (EPE 9) SMALL-Break LOCA (CFR: 41.5 / 41.7 /
45.7 / 45.8): RCS heat removal 4.0 3
4 (000011) (EPE 11)
Large Break LOCA X (000011) (EPE 11) Large Break LOCA (G2.1.6) CONDUCT OF OPERATIONS: Ability to manage the control room crew during plant transients (SRO Only) (CFR: 43.5 / 45.12 /
45.13) 4.8 76 5
(000015) (APE 15)
Reactor Coolant Pump Malfunctions X
(000015AK2.11) Knowledge of the relationship between (APE
- 15) REACTOR COOLANT Pump Malfunctions and the following systems or components (CFR: 41.8 / 41.10 / 45.3): AC electrical distribution (transformer) 3.2 4
6 (000022) (APE 22)
Loss of Reactor Coolant Makeup X
(000022AA2.03) Ability to determine and/or interpret the following as they apply to (APE 22) LOSS OF REACTOR Coolant Makeup (CFR: 41.10 / 43.5 / 45.13): Failures of flow control valve or controller 3.5 5
7 (000025) (APE 25)
Loss of Residual Heat Removal System X
(000025AA2.03) Ability to determine and/or interpret the following as they apply to (APE 25) LOSS OF RESIDUAL Heat Removal System (CFR: 41.10 / 43.5 / 45.13): Increasing reactor building sump level 3.6 6
8 (000025) (APE 25)
Loss of Residual Heat Removal System X (000025) (APE 25) Loss of Residual Heat Removal System (G2.4.23) EMERGENCY PROCEDURES/PLAN: Knowledge of the bases for prioritizing emergency operating procedures implementation (CFR: 41.10 / 43.5 / 45.13) 4.4 77 9
(000026) (APE 26)
Loss of Component Cooling Water X (026)(APE 26) Loss of Component Cooling Water (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.
4.2 7
10 (000027) (APE 27)
Pressurizer Pressure Control System Malfunction X
(000027AK3.05) Knowledge of the reasons for the following responses and/or actions as they apply to (APE 27)
PRESSURIZER PRESSURE Control System Malfunction (CFR:
41.5 / 41.10 / 45.6 / 45.13): Actions to be taken if the PZR pressure instrument fails high 4.0 8
11 (000029) (EPE 29)
Anticipated Transient Without Scram X
(000029EK2.09) Knowledge of the relationship between (EPE
- 29) ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS) and the following systems or components (CFR: 41.8 / 41.10 /
45.3): ESFAS 3.9 9
12 (000038) (EPE 38)
Steam Generator Tube Rupture X (000038) (EPE 38) Steam Generator Tube Rupture (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) 3.5 10 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)
Item #
A1 A2 G*
K/A Topic(s)
Page 3 of 16 13 (000040) (APE 40; BW E05; CE E05; W E12) Steam Line Rupture -
Excessive Heat Transfer X (040)(APE 40/CE E05) Steam Line Rupture-Excessive Heat Transfer (G2.1.32( CONDUCT OF OPERATIONS: Ability to explain and apply systems precautions, limitations, notes, or cautions (CFR: 41.10/43.2/45.12) 4.0 78 14 (000054) (APE 54; CE E06) Loss of Main Feedwater X
(CE06EA1.12) Ability to operate and/or monitor the following as they apply to (CE E06) LOSS OF FEEDWATER (CFR: 41.5 /
41.7 / 45.5 to 45.8): MFW and AFW systems 4.0 11 15 (000055) (EPE 55)
Station Blackout X
(000055EA1.04) Ability to operate and/or monitor the following as they apply to (EPE 55) Station Blackout (CFR: 41.5 / 41.7 /
45.5 to 45.8): Load shedding 4.0 12 16 (000055) (EPE 55)
Station Blackout X
000055EA2.07) Ability to determine and/or interpret the following as they apply to (EPE 55) Station Blackout (CFR:
41.10 / 43.5 / 45.13): AFW flow 4.2 79 17 (000056) (APE 56)
(000056AK3.01) Knowledge of the reasons for the following responses and/or actions as they apply to (APE 56) Loss of Offsite Power (CFR: 41.5 / 41.10 / 45.6 / 45.13): Order and time to initiation of power for the load sequencer 3.6 13 18 (000056) (APE 56)
(000056AA2.81) Ability to determine and/or interpret the following as they apply to (APE 56) Loss of Offsite Power (CFR: 41.10 / 43.5 / 45.13): S/G level and pressure 3.7 80 19 (000057) (APE 57)
Loss of Vital AC Instrument Bus X
(000057AK1.01) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (APE 57) LOSS OF VITAL AC ELECTRICALINSTRUMENT BUS (CFR: 41.5 / 41.7 / 45.7 /
45.8): Effect of a loss of power to instruments powered by a vital instrument bus on plant operations 4.3 14 20 (000058) (APE 58)
Loss of DC Power X (000058) (APE 58) Loss of DC Power (G2.4.32) EMERGENCY PROCEDURES/PLAN: Knowledge of operator response to loss of annunciators (CFR: 41.10 / 43.5 / 45.13) 3.6 15 21 (000062) (APE 62)
Loss of Nuclear Service Water X
(062AK1.01) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (APE 62) LOSS OF SERVICE WATER (CFR: 41.5 / 41.7 / 45.7 / 45.8): Effects of loads cooled by service water 3.8 16 22 (000065) (APE 65)
Loss of Instrument Air X
(065AA2.10) Ability to determine and/or interpret the following as they apply to (APE 65) LOSS OF Instrument Air (CFR: 41.10/43.5/45.13): Instrument air pressure 3.8 17 23 (000077) (APE 77)
Generator Voltage and Electric Grid Disturbances X
(000077AK2.08) Knowledge of the relationship between (APE
- 77) GENERATOR VOLTAGE AND ELECTRIC Grid Disturbances and the following systems or components (CFR:
41.8 / 41.10 / 45.3): RCPs 3.5 18 24 (000077) (APE 77)
Generator Voltage and Electric Grid Disturbances X
(000077AA2.05) Ability to determine and/or interpret the following as they apply to (APE 77) GENERATOR VOLTAGE AND ELECTRIC Grid Disturbances (CFR: 41.10 / 43.5 /
45.13): Status of grid 3.6 81 (W E04) LOCA Outside Containment / 3 (W E11) Loss of Emergency Coolant Recirculation / 4 (BW E04; W E05)
Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 K/A Category Totals:
3 3
3 3
3/3 3/3 Group Point Total:
18/6
Page 4 of 16 ES-4.1-PWR ANO 2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)
Item #
A2 G*
K/A Topic(s)
IR Q#
000003 (APE 3)
Dropped Control Rod / 1 000005 (APE 5)
Inoperable/Stuck Control Rod / 1 25 (000024) (APE 24)
Emergency Boration X
(000024AA2.12) Ability to determine and/or interpret the following as they apply to (APE 24) EMERGENCY Boration (CFR: 41.10 / 43.5 / 45.13): Emergency boron flow 4.0 82 26 (000028) (APE 28)
Pressurizer (PZR)
Level Control Malfunction X
(000028AK1.02) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (APE 28) PRESSURIZER (PZR) Level Control Malfunction (CFR: 41.5 / 41.7 / 45.7 / 45.8): Cause for PZR level deviation alarm: controller malfunction or other instrument 3.6 19 000032 (APE 32)
Loss of Source Range Nuclear Instrumentation / 7 000033 (APE 33)
Loss of Intermediate Range Nuclear Instrumentation / 7 27 (000036) (APE 36; BW/A08) Fuel-Handling Incidents X (000036) (APE 36; BW/A08) Fuel-Handling Incidents (G2.1.47) CONDUCT OF OPERATIONS: Ability to direct nonlicensed personnel activities inside the control room (CFR: 41.10 / 43.5 / 45.5 / 45.12 / 45.13) 3.2 83 28 (000037) (APE 37)
Steam Generator Tube Leak X
3.4 20 000051 (APE 51)
Loss of Condenser Vacuum / 4 29 (000059) (APE 59)
Accidental Liquid Radwaste Release X (059)(APE 59) Accidental Liquid Radiation Release (G2.1.20)
CONDUCT OF OPERATIONS: Ability to interpret and execute procedure steps. (CFR: 41.10/43.5/45.12) 4.6 84 000060 (APE 60)
Accidental Gaseous Radwaste Release /
9 30 (000061) (APE 61)
Area Radiation Monitoring System Alarms X (061)(APE 61) Area Radiation Monitoring System Alarms (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 21 000067 (APE 67)
Plant Fire On Site /
8 31 (000068) (APE 68; BW A06) Control Room Evacuation X
(000068AA1.06) Ability to operate and/or monitor the following as they apply to (APE 68) Control Room Evacuation (CFR: 41.5 /
41.7 / 45.5 to 45.8): Charging pump 3.7 22 000001 (APE 1)
Continuous Rod Withdrawal / 1 (000037AA1.13) Ability to operate and/or monitor the following as they apply to (APE 37) STEAM Generator Tube Leak (CFR: 41.5 / 41.7 / 45.5 to 45.8): S/GB radiation monitors E/APE # / Name /
Safety Function K1 K2 K3 A1
Page 5 of 16 000069 (APE 69; W E14) Loss of Containment Integrity / 5 000074 (EPE 74; W E06 & E07)
Inadequate Core Cooling / 4 32 (000076) (APE 76)
High Reactor Coolant Activity X
(000076AK2.08) Knowledge of the relationship between (APE
- 76) HIGH REACTOR COOLANT ACTIVITY and the following systems or components (CFR: 41.8 / 41.10 / 45.3): CVCS 3.4 23 33 (000078) (APE 78*)
RCS Leak X
(000078AK2.06) Knowledge of the relationship between (APE
- 78) REACTOR COOLANT SYSTEM LEAK and the following systems or components (CFR: 41.8 / 41.10 / 45.3): LRS 2.9 24 (W E01 & E02)
Rediagnosis & SI Termination / 3 (W E13) Steam Generator Overpressure / 4 (W E15)
Containment Flooding / 5 (W E16) High Containment Radiation /9 (BW A04) Turbine Trip / 4 (BW A05)
Emergency Diesel Actuation / 6 (BW A07) Flooding
/ 8 (BW E03)
Inadequate Subcooling Margin /
4 (BW E08; W E03)
LOCA Cooldown -
Depressurization / 4 (BW E09; CE A13**; W E09 &
E10) Natural Circulation/4 (BW E13 & E14)
EOP Rules and Enclosures (CE A11**; W E08)
RCS Overcooling -
Pressurized Thermal Shock / 4 34 (CE A16) Excess RCS Leakage X
(CA16AK3.10) Knowledge of the reasons for the following responses and/or actions as they apply to (CE A16) EXCESS RCS Leakage (CFR: 41.5 / 41.10 / 45.6 / 45.13): Identifying the RCS leak rate using tank or sump level changes 3.4 25 35 (CE E09) Functional Recovery X
(CE09EA2.16) Ability to determine and/or interpret the following as they apply to (CE E09) FUNCTIONAL RECOVERY (CFR:
41.10 / 43.5 / 45.13): Containment spray flow 4.0 26 (BW A01) Plant Runback / 1 (BW A02 & A03)
Loss of NNI-X/Y/7
Page 6 of 16 36 (CE E13*) Loss of Forced Circulation/LOOP/
Blackout X
(CE13EA2.06) Ability to determine and/or interpret the following as they apply to (CE E13) LOSS OF FORCED CIRCULATION AND/OR LOOP AND/OR A BLACKOUT (CFR:
41.10 / 43.5 / 45.13): PZR level and pressure 3.4 85 K/A Category Totals:
1 2
1 2
1/2 1/2 Group Point Total:
8/4
Page 7 of 16 ES-4.1-PWR ANO 2 Plant SystemsTier 2/Group 1 (RO/SRO)
Item # System / Name K1 K2 K3 K4 G*
K/A Topic(s)
IR Q#
37 (003) (SF4P RC)REACTOR COOLANT PUMP SYSTEM X
(003K5.04) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF4P RCP) REACTOR COOLANT PUMP SYSTEM (CFR: 41.5 / 45.3): Effects of RCP shutdown on secondary parameters, such as steam pressure, steam flow, and feed flow 3.5 27 38 (004) (SF1; SF2 CVCS) CHEMICAL AND VOLUME CONTROL SYSTEM X
(004K3.09) Knowledge of the effect that a loss or malfunction of the (SF1; SF2 CVCS) CHEMICAL AND VOLUME CONTROL SYSTEM will have on the following systems or system parameters (CFR: 41.7 /
45.4): LRS 2.8 28 39 (005) (SF4P RHR)
RESIDUAL HEAT REMOVAL SYSTEM X
(005K6.08) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF4P RHR)
RESIDUAL HEAT REMOVAL SYSTEM (CFR: 41.7 / 45.7): RHR flow controllers 3.7 29 40 (006) (SF2; SF3 ECCS)
EMERGENCY CORE COOLING SYSTEM X
(006A2.08) Ability to (a) predict the impacts of the following on the (SF2; SF3 ECCS) EMERGENCY CORE COOLING SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR: 41.5 / 45.6): ECCS valve failure mode 3.2 30 41 (007) (SF5 PRTS)
PRESSURIZER RELIEF/QUENCH TANK SYSTEM X (007)(SF5 PRTS) PRESSURIZER RELIEF/QUENCH TANK SYSTEM (G2.1.19) CONDUCT OF OPERATIONS: Ability to use available indications to evaluate system or component status (CFR: 41.10/45.12) 3.9 31 K5 K6 A1 A2 A3 A4
Page 8 of 16 42 (007) (SF5 PRTS)
PRESSURIZER RELIEF/QUENCH TANK SYSTEM X
(007K1.07) Knowledge of the physical connections and/or cause and effect relationships between the (SF5 PRTS) PRESSURIZER RELIEF/QUENCH TANK SYSTEM and the following systems (CFR:
41.2 to 41.9 / 45.7 to 45.8): Leakage collection 2.9 32 43 (008) (SF8 CCW)
COMPONENT COOLING WATER SYSTEM X
(008A1.04) Ability to predict and/or monitor changes in parameters associated with operation of the (SF8 CCW) COMPONENT COOLING WATER SYSTEM, including (CFR:
41.5 / 45.5): Surge tank level 3.4 33 44 (010) (SF3 PZR PCS)
PRESSURIZER PRESSURE CONTROL SYSTEM X
(010A4.01) Ability to manually operate and/or monitor the (SF3 PZR PCS) PRESSURIZER PRESSURE CONTROL SYSTEM in the control room (CFR: 41.7/45.5 to 45.8): PZR spray valve 3.8 34 45 (010) (SF3 PZR PCS)
PRESSURIZER PRESSURE CONTROL SYSTEM X
(010K4.04) Knowledge of (SF3 PZR PCS) PRESSURIZER PRESSURE CONTROL SYSTEM design features and/or interlocks that provide for the following (CFR: 41.7): Bias signals for SBCS (CE) 3.1 35 46 (012) (SF7 RPS)
(012K1.04) Knowledge of the physical connections and/or cause and effect relationships between the (SF7 RPS) REACTOR PROTECTION SYSTEM and the following systems (CFR: 41.2 to 41.9 /
45.7 to 45.8): RPIS 3.8 36 47 (012) (SF7 RPS)
(012K3.01) Knowledge of the effect that a loss or malfunction of the (SF7 RPS) REACTOR PROTECTION SYSTEM will have on the following systems or system parameters (CFR: 41.7 / 45.4): CRDS 4.2 37 48 (013) (SF2 ESFAS)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM X
(013A3.06) Ability to monitor automatic features of the (SF2 ESFAS) ENGINEERED SAFETY FEATURES ACTUATION SYSTEM, including (CFR: 41.7 / 45.7):
Containment integrity system isolation 4.0 38 49 (013) (SF2 ESFAS)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM X
(013A2.01) Ability to (a) predict the impacts of the following on the (SF2 ESFAS) ENGINEERED SAFETY FEATURES ACTUATION SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR: 41.5 / 45.6):
LOCA 4.4 86
Page 9 of 16 50 (022) (SF5 CCS)
CONTAINMENT COOLING SYSTEM X
(022K2.02) Knowledge of electrical power supplies to the following (CFR:
41.7): (SF5 CCS) CONTAINMENT COOLING SYSTEM Chillers 2.8 39 51 (022) (SF5 CCS)
CONTAINMENT COOLING SYSTEM X 022 G2.2.17 (Recommendation)
(022)(SF5 CCS) CONTAINMENT COOLING SYSTEM (G2.2.17)
EQUIPMENT CONTROL:
Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, coordination with system operator (CFR:
41.10/43.5/45.13) 3.8 87 025 (SF5 ICE) ICE CONDENSER SYSTEM 52 (026) (SF5 CSS)
CONTAINMENT SPRAY SYSTEM X
(026K2.01) Knowledge of electrical power supplies to the following (CFR:
41.7): (SF5 CSS) CONTAINMENT SPRAY SYSTEM Containment spray pumps 3.9 40 53 (039) (SF4S MSS)
MAIN AND REHEAT STEAM SYSTEM X
(039K6.11) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF4S MSS)
MAIN AND REHEAT STEAM SYSTEM (CFR: 41.7 / 45.7): SDS 3.4 41 54 (039) (SF4S MSS)
MAIN AND REHEAT STEAM SYSTEM X
(039A2.08) Ability to (a) predict the impacts of the following on the (SF4S MSS) MAIN AND REHEAT STEAM SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR: 41.5 / 45.6):
MT/G malfunctions 3.1 88 053 (SF1; SF4P ICS*)
INTEGRATED CONTROL SYSTEM 55 (059) (SF4S MFW)
MAIN FEEDWATER SYSTEM X
(059K4.20) Knowledge of (SF4S MFW) MAIN FEEDWATER SYSTEM design features and/or interlocks that provide for the following (CFR: 41.7):
Automatic feed pump recirculation flow 3.0 42 56 (059) (SF4S MFW)
MAIN FEEDWATER SYSTEM X (059) (SF4S MFW) MAIN FEEDWATER SYSTEM (G2.1.43)
CONDUCT OF OPERATIONS:
Ability to use an online power distribution monitoring system and/or procedures to determine the effects on reactivity of plant changes, such as RCS temperature, secondary plant, or fuel depletion 4.3 89
Page 10 of 16 57 (061) (SF4S AFW)
AUXILIARY /
(061A3.03) Ability to monitor automatic features of the (SF4S AFW) AUXILIARY/EMERGENCY FEEDWATER SYSTEM, including (CFR: 41.7 / 45.7): Automatic AFW S/G level control 3.8 43 58 (061) (SF4S AFW)
AUXILIARY /
(061K4.01) Knowledge of (SF4S AFW) AUXILIARY/EMERGENCY FEEDWATER SYSTEM design features and/or interlocks that provide for the following (CFR: 41.7):
Water sources and/or priority of use 4.0 44 59 (062) (SF6 ED AC)
AC ELECTRICAL DISTRIBUTION SYSTEM X
(062A4.01) Ability to manually operate and/or monitor the (SF6 ED AC) AC ELECTRICAL DISTRIBUTION SYSTEM in the control room (CFR: 41.7 / 45.5 to 45.8): All breakers (including available switchyard) 3.5 45 60 (063) (SF6 ED DC)
DC ELECTRICAL DISTRIBUTION SYSTEM X
(063A2.04) Ability to (a) predict the impacts of the following on the (SF6 ED DC) DC ELECTRICAL DISTRIBUTION SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR: 41.5 /
45.6): Battery malfunctions 3.9 46 61 (063) (SF6 ED DC)
DC ELECTRICAL DISTRIBUTION SYSTEM X
(063K4.01) Knowledge of (SF6 ED DC) DC ELECTRICAL DISTRIBUTION SYSTEM design features and/or interlocks that provide for the following (CFR: 41.7):
Manual/automatic transfers of control 3.4 47 62 (064) (SF6 EDG)
EMERGENCY DIESEL GENERATOR SYSTEM X (064) (SF6 EDG) EMERGENCY DIESEL GENERATOR SYSTEM (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 48 63 (064) (SF6 EDG)
EMERGENCY DIESEL GENERATOR SYSTEM X
(064K5.04) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF6 EDG) EMERGENCY DIESEL GENERATOR SYSTEM (CFR: 41.5 /
45.3): Operating overloaded or underloaded 3.6 49 64 (073) (SF7 PRM)
PROCESS RADIATION MONITORING SYSTEM X
(073K1.08) Knowledge of the physical connections and/or cause and effect relationships between the (SF7 PRM) PROCESS RADIATION MONITORING SYSTEM and the following systems (CFR: 41.2 to 41.9 /
45.7 to 45.8): SWS 3.1 50
Page 11 of 16 65 (076) (SF4S SW)
SERVICE WATER SYSTEM X
(076A1.07) Ability to predict and/or monitor changes in parameters associated with operation of the (SF4S SW) SERVICE WATER SYSTEM, including (CFR: 41.5 /
45.5): Intake screen D/P 2.9 51 66 (076) (SF4S SW)
SERVICE WATER SYSTEM X
(076A2.07) Ability to (a) predict the impacts of the following on the (SF4S SW) SERVICE WATER SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR: 41.5 / 45.6): Heat exchanger and condenser failure 3.2 90 67 (078) (SF8 IAS)
INSTRUMENT AIR SYSTEM X (078)(SF8 IAS) INSTRUMENT AIR SYSTEM (191003K1.10)
CONTROLLERS AND POSITIONERS (CFR 41.7):
Function and characteristics of air-operated valves, including failure modes 2.8 52 68 (103) (SF5 CNT)
CONTAINMENT SYSTEM X
(103A2.06) Ability to (a) predict the impacts of the following on the (SF5 CNT) CONTAINMENT SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR: 41.5 /
45.6): High containment pressure 4.5 53 69 (103) (SF5 CNT)
CONTAINMENT SYSTEM X
(103A3.01) Ability to monitor automatic features of the (SF5 CNT)
CONTAINMENT SYSTEM, including:
(CFR: 41.7 / 45.5): Containment Isolation 3.0 54 K/A Category Totals:
3 2
2 4
2 2
2 3/3 3
2 3/2 Group Point Total:
28/5
Page 12 of 16 ES-4.1-PWR ANO 2 Plant SystemsTier 2/Group 2 (RO/SRO)
G*
K/A Topic(s)
IR Q#
70 (001) (SF1 CRDS)
CONTROL ROD DRIVE SYSTEM X (001)(SF1 CRDS) CONTROL ROD DRIVE SYSTEM (191002K1.16)
SENSORS AND DETECTORS (CFR:
41.7): (POSITION DETECTORS)
Applications of reed switches, magnets, LVDTs, potentiometers, and limit switches 2.7 55 71 (002) (SF2; SF4P RCS) REACTOR COOLANT SYSTEM X
(002A1.12) Ability to predict and/or monitor changes in parameters associated with operation of the (SF2; SF4P RCS) REACTOR COOLANT SYSTEM, including (CFR: 41.5 / 45.5): Radioactivity level when venting CRDS 2.8 56 011 (SF2 PZR LCS)
PRESSURIZER LEVEL CONTROL SYSTEM 72 (014) (SF1 RPI)
ROD POSITION INDICATION SYSTEM X
(014A1.04) Ability to predict and/or monitor changes in parameters associated with operation of the (SF1 RPI) ROD POSITION INDICATION SYSTEM, including:
(CFR: 41.5 to 41.7 / 45.5) Axial and/or radial power distribution 3.1 57 73 (015) (SF7 NI)
NUCLEAR INSTRUMENTATIO N SYSTEM X (015) (SF7 NI) NUCLEAR INSTRUMENTATION SYSTEM (G2.1.14) CONDUCT OF OPERATIONS: Knowledge of criteria or conditions that require plantwide announcements, such as pump starts, reactor trips, and mode changes (CFR: 41.10 / 43.5 /
45.12) 3.1 91 016 (SF7 NNI)
NONNUCLEAR INSTRUMENTATIO N SYSTEM 017 (SF7 ITM) IN CORE TEMPERATURE MONITOR SYSTEM 74 (027) (SF5 CIRS)
CONTAINMENT IODINE REMOVAL SYSTEM X
(027K5.01) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF5 CIRS) CONTAINMENT IODINE REMOVAL SYSTEM (CFR: 41.5 /
45.3): Purpose of charcoal filters 2.9 58 75 (028) (SF5 HRPS)
HYDROGEN RECOMBINER AND PURGE CONTROL SYSTEM X
(028A1.02) Ability to predict and/or monitor changes in parameters associated with operation of the (SF5 HRPS) HYDROGEN RECOMBINER AND PURGE CONTROL SYSTEM including:
(CFR: 41.5 / 43.5 / 45.3 / 45.13)
Containment pressure 3.2 59 Item #
System / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4
Page 13 of 16 029 (SF8 CPS)
CONTAINMENT PURGE SYSTEM 74 033 (SF8 SFPCS)
SPENT FUEL POOL COOLING SYSTEM X
(033K2.01) Knowledge of the electrical power supplies to the following (SF8 SFPCS) SPENT FUEL POOL COOLING SYSTEM:
(CFR: 41.7) Spent Fuel Pool cooling pumps 3.1 58 76 (034) (SF8 FHS)
FUEL HANDLING EQUIPMENT SYSTEM X
(034K6.02) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF8 FHS)
FUEL HANDLING EQUIPMENT SYSTEM (CFR: 41.7 / 45.7): RMS 3.4 60 035 (SF4P SG)
STEAM GENERATOR SYSTEM 77 (041) (SF4S SDS)
STEAM DUMP/TURBINE BYPASS CONTROL SYSTEM X
(041K6.07) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF4S SDS)
STEAM DUMP/TURBINE BYPASS CONTROL SYSTEM (CFR: 41.7 /
45.7): CWS 3.1 61 78 (045) (SF4S MTG)
MAIN TURBINE GENERATOR SYSTEM X
(045A2.16) Ability to (a) predict the impacts of the following on the (SF4S MTG) MAIN TURBINE GENERATOR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR:
41.5 / 45.6): Turbine blade failure 3.3 92 050 (SF9 CRV*)
CONTROL ROOM VENTILATION 055 (SF4S CARS)
CONDENSER AIR REMOVAL SYSTEM 79 (056) (SF4S CDS)
CONDENSATE SYSTEM X
(056A2.05) Ability to (a) predict the impacts of the following on the (SF4S CDS) CONDENSATE SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operations (CFR: 41.5 / 45.6):
Condenser tube leakage 3.7 62 068 (SF9 LRS)
LIQUID RADWASTE SYSTEM 071 (SF9 WGS)
WASTE GAS DISPOSAL SYSTEM 072 (SF7 ARM)
AREA RADIATION MONITORING SYSTEM
Page 14 of 16 80 (075) (SF8 CW)
CIRCULATING WATER SYSTEM X (075)(SF8 CW) CIRCULATING WATER SYSTEM (G2.1.37)
CONDUCT OF OPERATIONS:
Knowledge of procedures, guidelines, or limitations associated with reactivity management (CFR: 41.1 / 41.5 / 41.10 /
43.6 / 45.6) 4.6 93 079 (SF8 SAS**)
STATION AIR SYSTEM 81 (086) (SF8 FPS)
FIRE PROTECTION SYSTEM X
(086K3.01) Knowledge of the effect that a loss or malfunction of the (SF8 FPS) FIRE PROTECTION SYSTEM will have on the following systems or system parameters (CFR 41.7/45.6):
Contingency capability for safe shutdown 3.4 63 K/A Category Totals:
0 1
1 0
0 2
3 1/1 0
0 1/2 Group Point Total:
9/3
Form 4.1-COMMON Common Examination Outline Page 15 of 16 ES-4.1-COMMON COMMON Examination Outline (ANO 2)
Facility: ANO 2 Date of Exam: 3/15/2023 Generic Knowledge and Abilities Outline (Tier 3) (RO/SRO)
RO SRO-Only Item #
IR Q#
IR Q#
- 1.
Conduct of Operations 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) 82 4.1 95 G2.1.9 (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) 83 4.5 94 G2.1.28 (G2.1.28) CONDUCT OF OPERATIONS: Knowledge of the purpose and function of major system components and controls (CFR: 41.7) 84 4.1 64 G2.1.40 (G2.1.40) CONDUCT OF OPERATIONS: Knowledge of refueling administrative requirements (CFR: 41.10 / 43.5 / 43.6 /
45.13) 85 2.8 65
- 2.
Equipment Control G2.2.13 (G2.2.13) EQUIPMENT CONTROL: Knowledge of tagging and clearance procedures (CFR: 41.10 / 43.1 / 45.13) 86 4.1 66 G2.2.39 (G2.2.39) EQUIPMENT CONTROL: Knowledge of less than or equal to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> TS action statements (does not include action statements of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or less that follow the expiration of a completion time for a TS condition for which an action statement has already been entered) (CFR: 41.7 / 41.10 / 43.2 /
45.13) 87 3.9 67 G2.2.37 (G2.2.37) EQUIPMENT CONTROL: Ability to determine operability or availability of safety related-related equipment (SRO Only)(CFR: 43.2 / 43.5 / 45.12) 88 4.6 96 G2.2.43 (G2.2.43) EQUIPMENT CONTROL: Knowledge of the process used to track inoperable alarms (CFR: 41.10 / 43.5 /
45.13) 89 3.3 97
- 3.
Radiation Control G2.3.12 (G2.3.12) RADIATION CONTROL: Knowledge of radiological safety principles and procedures pertaining to licensed operator duties, such as responding to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to high radiation areas, or alignment of filters (CFR: 41.12 / 45.9 / 45.10) 90 3.2 68 G2.3.6 (G2.3.6) RADIATION CONTROL: Ability to approve liquid or gaseous release permits (CFR: 41.13 / 43.4 / 45.10) 91 98 Subtotal N/A 1
N/A 1
- 4.
Emergency Procedures / Plan G2.4.4 (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) 92 4.5 69 G2.4.12 (G2.4.12) EMERGENCY PROCEDURES/PLAN: Knowledge of operating crew responsibilities during emergency and abnormal operations (CFR: 41.10 / 45.12) 93 4.3 99 G2.4.45 (G2.4.45) EMERGENCY PROCEDURES/PLAN: Ability to prioritize and interpret the significance of each annunciator or alarm (CFR: 41.10 / 43.5 / 45.3 / 45.12) 94 4.3 100 Subtotal N/A 1
N/A 2
Tier 3 Point Total N/A 6
N/A Category K/A #
Topic Subtotal N/A 2
N/A 2
Subtotal N/A 2
N/A 2
7
Form 4.1-COMMON Common Examination Outline Page 16 of 16 ES-4.1-COMMON COMMON Examination Outline (ANO 2)
Facility: ANO 2 Date of Exam: 3/15/2023 Theory (Tier 4) (RO)
Category K/A #
Topic RO Item #
IR Q#
Reactor Theory 192006 (192006K1.13) FISSION PRODUCT POISONS (CFR: 41.1):
Plot the curve and explain the reasoning for the reactivity insertion by xenon-135 versus time for the following: -- reactor shutdown 95 3
70 192007 (192007K1.01) FUEL DEPLETION AND BURNABLE POISONS (CFR: 41.1): Define burnable poison and state its use in the reactor 96 2.5 71 192008 (192008K1.21) REACTOR OPERATIONAL PHYSICS (CFR:
41.1): (POWER OPERATION) Explain the relationship between steam flow and reactor power given specific conditions 97 3.8 72 Subtotal N/A 3
Thermodynamics 193003 193003K1.16) STEAM (CFR: 41.14): Define the following terms
- subcooled and compressed liquids 98 2.7 73 193004 (193004K1.11) THERMODYNAMIC PROCESS (CFR: 41.14):
(CONDENSERS) Describe the process of condensate depression (subcooling) and its effect on plant operation 99 2.5 74 193009 (193009K1.06) CORE THERMAL LIMITS (CFR: 41.14):
Describe the function of the core protection calculator (thermal margin calculator) 100 3.7 75 Subtotal N/A 3
Tier 4 Point Total N/A 6
Form 4.1-1 Record of Rejected Knowledge and Abilities Refer to Examination Standard (ES)-4.2, Developing Written Examinations, Section B.3, for deviations from the approved written examination outline.
Tier/Group Randomly Selected K/A Reason for Rejection RO Tier 1 Group 1 Outline #9 Question #7 026 G2.2.35 (Original)
(026)(APE 26) Loss of Component Cooling Water (G2.2.35) EQUIPMENT CONTROL: Ability to determine TS for mode of operation (CFR 41.7/41.10/43.2/45.13) 026 G2.2.44 (Recommendation)
(026)(APE 26) Loss of Component Cooling Water (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.
The subject K/A is not relevant at the facility.
CCW is not a tech spec required system at ANO-2.
We recommend K/A 026 G2.2.44 as a replacement.
SRO Tier 1 Group 1 Outline #13 Question
- 78 040 G2.1.39 (Original)
(040)(APE 40/CE E05) Steam Line Rupture-Excessive Heat Transfer (G2.1.39( CONDUCT OF OPERATIONS: Knowledge of conservative decision-making practices (CFR: 41.10/43.5/45.12) 040 G2.1.32 (Recommendation)
(040)(APE 40/CE E05) Steam Line Rupture-Excessive Heat Transfer (G2.1.32( CONDUCT OF OPERATIONS: Ability to explain and apply systems precautions, limitations, notes, or cautions (CFR:
41.10/43.2/45.12)
It is not possible to prepare a question at the correct license level relevant to the subject K/A and meet difficulty level requirements.
We recommend K/A 040 G2.1.32 as a replacement.
RO Tier 1 Group 1 Outline #21 Question
- 16 062AK1.02 (Original)
(062AK1.02) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (APE 62)
LOSS OF SERVICE WATER (CFR:
41.5 / 41.7 / 45.7 / 45.8): Knowledge of backup cooling water systems 062AK1.01 (Recommendation)
(062AK1.01) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (APE 62)
LOSS OF SERVICE WATER (CFR:
41.5 / 41.7 / 45.7 / 45.8): Effects of loads cooled by service water The subject K/A is not relevant at the facility.
Loss of Service Water AOP does not address backup water systems.
We recommend K/A 062 AK1.01 as a replacement.
RO Tier 1 Group 1 Outline #22 Question
- 17 065AA2.12 (Original)
(065AA2.12) Ability to determine and/or interpret the following as they apply to (APE 65) LOSS OF Instrument Air (CFR: 41.10/43.5/45.13):
Implementation of TS and/or TRM as appropriate for loss of, or degraded, IAS 065AA2.10 (Recommendation)
(065AA2.10) Ability to determine and/or interpret the following as they apply to (APE 65) LOSS OF Instrument Air (CFR: 41.10/43.5/45.13): Instrument air pressure It is not possible (without spending an unreasonable amount of resources) to prepare a psychometrically question relate to the subject K/A. At ANO-2 Instrument Air is not a Tech Spec system.
We recommend K/A 065 AA2.10 as a replacement.
SRO Tier 1 Group 2 Outline #29 Question
- 84 059 G2.1.45 (Original)
(059)(APE 59) Accidental Liquid Radiation Release (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) 059 G2.1.45 (Recommendation)
(059)(APE 59) Accidental Liquid Radiation Release (G2.1.20)
CONDUCT OF OPERATIONS: Ability to interpret and execute procedure steps. (CFR: 41.10/43.5/45.12)
It is not possible to prepare a question at the correct license level related to the subject K/A.
We recommend 059 G2.1.20 as a replacement.
RO Tier 1 Group 2 Outline #30 Question
- 21 061 G2.1.34 (Original)
(061)(APE 61) Area Radiation Monitoring System Alarms (G2.1.34)
CONDUCT OF OPERATIONS:
Knowledge of RCS or balance of plant chemistry controls, including parameters measured and reasons for the control (CFR: 41.10/43.5/45.12) 061 G2.1.45 (Recommendation)
(061)(APE 61) Area Radiation Monitoring System Alarms (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)
It is not possible (without spending an unreasonable amount of resources) to prepare a psychometrically question relate to the subject K/A.
We recommend 061 G2.1.45 as a replacement.
RO Tier 2 Group 1 Outline #41 RO Question
- 31 007 G2.3.14 (Original)
(007)(SF5 PRTS) PRESSURIZER RELIEF/QUENCH TANK SYSTEM (G2.3.14) RADIATION CONTROL:
Knowledge of the radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities, such as analysis and interpretation of radiation and activity readings as they pertain to administrative, normal, abnormal, and emergency procedures or to analysis and interpretation of coolant activity, including comparison to emergency plan or regulator limits (SRO Only)(CFR: 43.4/45.10) 007 G2.1.19 (Recommended)
(007)(SF5 PRTS) PRESSURIZER RELIEF/QUENCH TANK SYSTEM (G2.1.19) CONDUCT OF OPERATIONS: Ability to use available indications to evaluate system or component status (CFR: 41.10/45.12)
It is not possible to prepare a question at the correct license level related to the subject K/A.
G2.3.14 is an SRO only K/A that was randomly selected to be on the RO portion of the exam.
We recommend 007 G2.1.19 as a replacement.
RO Tier 2 Group 1 Outline #44 RO Question
- 34 010A4.04 (Original)
(010A4.04) Ability to manually operate and/or monitor the (SF3 PZR PCS)
PRESSURIZER PRESSURE CONTROL SYSTEM in the control room (CFR: 41.7/45.5 to 45.8): SBCS valves (CE) 010A4.01 (Recommended)
(010A4.01) Ability to manually operate and/or monitor the (SF3 PZR PCS)
PRESSURIZER PRESSURE CONTROL SYSTEM in the control room (CFR: 41.7/45.5 to 45.8): PZR spray valve This K/A overlaps with Outline #45/RO Question #35.
We recommend 010A as a replacement.
SRO Tier 2 Group 1 Outline #51 Question
- 87 022 G2.2.18 (Original)
(022)(SF5 CCS) CONTAINMENT COOLING SYSTEM (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) 022 G2.2.17 (Recommendation)
(022)(SF5 CCS) CONTAINMENT COOLING SYSTEM (G2.2.17)
EQUIPMENT CONTROL: Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, coordination with system operator (CFR:
41.10/43.5/45.13)
The subject K/A is not relevant to the subject facility. Containment cooling is not a critical system when shutdown.
We recommend 022 G2.2.17 as a replacement.
RO Tier 2 Group 1 Outline #67 Question
- 52 078 191002K1.20 (Original)
(078)(SF8 IAS) INSTRUMENT AIR SYSTEM (191002K1.20) SENSORS AND DETECTORS (CFR: 41.7):
(NUCLEAR INSTRUMENTATION)
Effects of voltage changes on neutron detector performance 078 191003K1.10 (Recommendation)
(078)(SF8 IAS) INSTRUMENT AIR SYSTEM (191003K1.10)
CONTROLLERS AND POSITIONERS (CFR 41.7): Function and characteristics of air-operated valves, including failure modes The subject K/A is not relevant at the facility.
IAS does not go with a Nuclear Instruments K/A.
We recommend 191003K1.10 as a replacement K/A.
RO Tier 2 Group 1 Outline #69 Question
- 54 103A4.09 (Original)
(103A4.09) Ability to manually operator and/or monitor the (SF5 CNT)
CONTAINMENT SYSTEM in the control room (CFR: 41.7/45.5 to 45.8):
Containment vacuum system 103A3.01 (Recommendation)
(103A3.01) Ability to monitor automatic features of the (SF5 CNT)
CONTAINMENT SYSTEM, including:
(CFR: 41.7 / 45.5): Containment Isolation The subject K/A is not relevant at the facility.
ANO-2 does not have a Containment vacuum system. There are no other A4 K/As for system 103 due to all being deleted.
We recommend 103A3.01 as a replacement K/A.
RO Tier 2 Group 2 Outline #70 Question
- 55 001 191003K1.05 (Original)
(001)(SF1 CRDS) CONTROL ROD DRIVE SYSTEM (191003K1.05)
CONTROLLERS AND POSITIONERS (CFR: 41.7): Function and characteristics of valve positioners 001 191002K1.16 (Recommendation)
(001)(SF1 CRDS) CONTROL ROD DRIVE SYSTEM (191002K1.16)
SENSORS AND DETECTORS (CFR:
41.7): (POSITION DETECTORS)
Applications of reed switches, magnets, LVDTs, potentiometers, and limit switches The subject K/A is not relevant to the facility.
CRDS does not go with a valve positioners K/A.
We recommend 191002K1.16 as a replacement K/A.
RO Tier 2 Group 2 Outline #72 Question
- 57 014A4.05 (Original)
(014A4.05) Ability to manually operator and/or monitor the (SF1 RPI) ROD POSITION INDICATION SYSTEM in the control room (CFR: 41.7/45.5 to 45.8): RPI accuracy mode selection (W) 014A1.04 (Recommendation)
(014A1.04) Ability to predict and/or monitor changes in parameters associated with operation of the (SF1 RPI) ROD POSITION INDICATION SYSTEM, including: (CFR: 41.5 to 41.7
/ 45.5) Axial and/or radial power distribution The subject K/A is not relevant at the facility.
This K/A is for a Westinghouse plant.
We recommend 014A1.04 as a replacement K/A.
RO Tier 2 Group 2 Outline #74 Question
- 58 027K5.01 (Original)
(027K5.01) Knowledge of the operational implications or cause and effect relationship of the following concepts as they apply to the (SF5 CIRS) CONTAINMENT IODINE REMOVAL SYSTEM (CFR: 41.5/45.3):
Purpose of charcoal filters 033K2.01 (Recommendation)
(033K2.01) Knowledge of the electrical power supplies to the following (SF8 SFPCS) SPENT FUEL POOL COOLING SYSTEM: (CFR: 41.7)
Spent Fuel Pool cooling pumps The subject K/A is not relevant at the facility.
At ANO-2 per SAR, containment air purification (iodine removal) is accomplished by the Containment Spray system. No charcoal filters are used. Already sampling Containment Spray system in Tier 2 Group 1.
There are no K/As in the Containment Iodine Removal System that can be used that are not related to Containment Spray for ANO-2.
We recommend 033K2.01 as a replacement K/A.
RO Tier 2 Group 2 Outline #75 Question
- 59 028K1.01 (Original)
(028K1.01) Knowledge of the physical connnections and/or cause and effect relationships between the (SF5 HRPS)
HYDROGEN RECOMBINER AND PURGE CONTROL SYSTEM and the following systems (CFR: 41.2 to 41.9/45.7 to 45.8): Containment annulus ventilation system 028A1.02 (Recommendation)
(028A1.02) Ability to predict and/or monitor changes in parameters associated with operation of the (SF5 HRPS) HYDROGEN RECOMBINER AND PURGE CONTROL SYSTEM including: (CFR: 41.5 / 43.5 / 45.3 /
45.13) Containment pressure The subject K/A is not relevant at the facility.
ANO-2 does not have an annulus ventilation system.
We recommend 028A1.02 as a replacement K/A.
SRO Tier 2 Group 2 Outline #80 Question
- 93 075 G2.1.46 (Original)
(075)(SF8 CW) CIRCULATING WATER SYSTEM (G2.1.46)
CONDUCT OF OPERATIONS: Ability to use integrated control systems to operate plant systems or components (CFR: 41.10/45.12/45.13) 075 G2.1.37 (Recommendation)
(075)(SF8 CW) CIRCULATING WATER SYSTEM (G2.1.37)
CONDUCT OF OPERATIONS:
Knowledge of procedures, guidelines, or limitations associated with reactivity management (CFR: 41.1 / 41.5 / 41.10
/ 43.6 / 45.6)
The subject K/A is not relevant at the facility.
ANO-2 does not have an integrated control system.
We recommend 075 G2.1.37 as a replacement K/A.
RO Tier 2 Group 2 Outline #81 Question
- 63 086K3.04 (Original)
(086K3.04) Knowledge of the effect that a loss or malfunction of the (SF8 FPS)
FIRE PROTECTION SYSTEM will have on the following systems or system parameters (CFR: 41.7/45.6): AC distribution 086K3.01 (Recommendation)
(086K3.01) Knowledge of the effect that a loss or malfunction of the (SF8 FPS)
FIRE PROTECTION SYSTEM will have on the following systems or system parameters (CFR 41.7/45.6):
Contingency capability for safe shutdown The subject K/A is not relevant at the facility.
ANO-2 does not have a reasonable like between FPS malfunctions and AC Distribution.
We recommend 086K3.01 as a replacement K/A.
SRO Tier 3 Outline #88 Question
- 96 2.2.42 (Original)
(G2.2.42) EQUIPMENT CONTROL:
Ability to recognize system parameters that are entry-level conditions for TS (CFR: 41.7/41.10/43.2/43.3/45.3) 2.2.37 (Recommendation)
(G2.2.37) EQUIPMENT CONTROL:
Ability to determine operability or availability of safety related-related equipment (SRO Only)(CFR: 43.2 /
43.5 / 45.12)
It is not possible to prepare a question at the correct license level related to the subject K/A.
G2.2.42 concerns ability to recognize system parameters that are entry level conditions for Tech Specs. This was randomly selected to be on the SRO only portion of the exam.
We recommend 2.2.37 as a replacement K/A.
RO Tier 3 Outline #90 Question
- 68 2.3.11 (Original)
(G2.3.11) RADIATION CONTROL:
Ability to control radiation releases (CFR: 41.11 / 43.4 / 45.10) 2.3.12 (Recommendation)
(G2.3.12) RADIATION CONTROL:
Knowledge of radiological safety principles and procedures pertaining to licensed operator duties, such as responding to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to high radiation areas, or alignment of filters (CFR: 41.12 / 45.9 / 45.10)
This K/A overlaps with Outline #91/SRO Question #98.
We recommend 2.3.12 as a replacement K/A.
3.2-1 Administrative Topics Outline Form 3.2-1 Revision 1 Facility:
ANO-2 Date of Examination:
March 2023 Examination Level: RO SRO Operating Test Number:
2023 Administrative Topic (see Note)
Type Code*
Activity and Associated K/A A1. Conduct of Operations 2.1.25 RO (4.3)
D/R Calculate makeup volumes for raising Spent Fuel Pool level A2JPM-NRC-ADMIN-SFPMU2 A2. Conduct of Operations 2.1.1 RO (2.9)
P/R Determine acceptable control room loading.
A2JPM-NRC-ADMIN-CRLD A3. Equipment Control 2.2.15 RO (3.9)
N/R Determine restoration position for Shutdown Cooling/LPSI valves following tagging.
A2JPM-NRC-ADMIN-SDCTG1 A4. Radiation Control 2.3.12 RO (3.2)
D/R Determine Condenser off gas rad monitor setting A2JPM-NRC-ADMIN-CRMON Emergency Plan NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
- Type Codes and Criteria:
(0) (C)ontrol room (0) (S)imulator (4) Class(R)oom (2) (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)
(1) (N)ew or (M)odified from bank ( 1)
(1) (P)revious 2 exams ( 1, randomly selected)
3.2-1 Administrative Topics Outline Form 3.2-1 Revision 1 Facility:
ANO-2 Date of Examination:
3/13/2023 Examination Level: RO SRO Operating Test Number:
2023 Administrative Topic (see Note)
Type Code*
Activity and Associated K/A A5. Conduct of Operations 2.1.25 SRO (4.4)
D/R Approve Spent Fuel Pool Makeup Calculation A2JPM-NRC-ADMIN-SFPMU2 A6. Conduct of Operations 2.1.40 SRO (3.9)
D/R Determine Shutdown Operations Protection Plan Condition A2JPM-NRC-ADMIN-SOPP1 A7. Equipment Control 2.2.15 SRO (4.3)
N/R Approve restoration positions for Shutdown Cooling/LPSI valves following tagging.
A2JPM-NRC-ADMIN-SDCTG2 A8. Radiation Control 2.3.4 SRO (3.7)
P/D/R Calculate expected dose for entry during an emergency and determine if entry is allowed.
A2JPM-NRC-ADMIN-EMGRESPSRO A9. Emergency Plan 2.4.44 SRO (4.6)
D/R Determine Protective Action Recommendations A2JPM-NRC-ADMIN-PAR8 NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).
- Type Codes and Criteria:
(0) (C)ontrol room (0) (S)imulator (5) Class(R)oom (4) (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)
(1) (N)ew or (M)odified from bank ( 1)
(1) (P)revious 2 exams ( 1, randomly selected)
Revision 0 3.2-2 Control Room/In-Plant Systems Outline Form 3.2-2 Facility: ANO-2 Date of Examination: _March 2023___
Exam Level: RO X
SRO-I X SRO-U X Operating Test No.: 2023 Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code*
Safety Function S1.
A2JPM-NRC-CEA01 001 A4.03; RO 3.7 / SRO 3.7 Perform Control Element Assembly Exercise test D/S 1
Reactivity S2.
A2JPM-NRC-EOP08 002 A2.01; RO 4.4 / SRO 4.5 Perform Standard Attachment 22 Isolating LOCA outside containment P/D/A/L/S 2
Inventory S3.
A2JPM-NRC-EOP16 006 A2.13; RO 3.6 / SRO 4.0 Inadvertent SIAS on both trains, Alternate path containment temperature/pressure rising requires aligning SW to containment coolers.
N/A/EN/S 3
Pressure Control S4.
A2JPM-NRC-SW02 076 A4.02; RO 3.7 / SRO 3.7 Shift Service Water Pump 2P-4A suction and discharge to ECP D/S 4
Heat Removal Secondary S5.
A2JPM-NRC-CSASV 026 A4.01; RO 3.9 / SRO 3.9 Verify CSAS Attachment 41, Alternate path CSAS signal fails to actuate requiring manual operation of components P/A/EN/L/S 5
Containment S6.
A2JPM-RO-ELEC05 062 A4.07; RO 3.7 / SRO 3.7 Transfer Auxiliaries between Startup transformers.
M/S 6
Electrical S7.
A2JPM-NRC-CPC06 012 A4.02; RO 3.8 / SRO 3.8 Place #1 CEAC to INOP on B CPC D/S 7
Instrumentation S8..
A2JPM-NRC-FP01 086 A4.02; RO 3.2 / SRO 3.2 Respond to a fire panel alarm D/S 8
Plant Service Systems Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P1.
A2JPM-NRC-EFWRA 061 A2.04; RO 4.1 / SRO 4.0 Reset the EFW pump trip throttle valve. Alternate path, emergency tappet nut does not return to trip reset position and has to be reset manually.
A/E/D/R 4
Heat Removal Secondary P2.
A2JPM-NRC-SITIP 011 EA1.09; RO 4 / SRO 4 Isolate Safety Injection Tanks. Alternate path, red train handswitches do not work from control room and A/B SITs have to be isolated at the breaker.
M/A/E/L 2
Inventory P3.
A2JPM-NRC-XFCEA 001 A2.14 RO 3.4 / SRO 3.6 Transfer a CEA to the hold bus following CEDMCS voltage alarms.
D/E 1
Reactivity All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
SROU JPMS are bold (S3, S8, P1, P2, P3)
SROI do all JPMs except S2 (italics)
Revision 0
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)
(P)revious 2 exams (R)CA (S)imulator (5 / 4 / 3) 4-6 / 4-6 / 2-3 (0 / 0 / 0)
(7 / 6 / 3) 9 / 8 / 4 (3 / 3 / 3) 1 / 1 / 1 (2 / 2 / 1) 1 / 1 / 1 (control room system)
(3 / 2 / 1) 1 / 1 / 1 (3 / 3 / 2) 2 / 2 / 1 (2 / 1 / 0) 3 / 3 / 2 (randomly selected)
(1 / 1 / 1) 1 / 1 / 1 (8 / 7 / 2)
Scenario 1 Form 3.3-1 Facility: ANO-2 Source: New Scenario #1 (New)
Op-Test No.: 2023 Examiners:
Operators:
Initial Conditions: 100%, 250 EFPD.
Turnover: None Scheduled evolution: Start 2C-5B Vacuum pump and secure 2C-5A Vacuum Pump.
Critical Tasks: Manually trip the reactor before completion of Reactivity Section in SPTAs, Commence a cool down within 30 minutes of entering LOCA EOP.
Event No.
Malf. No.
Event Type*
Event Description 1
N (BOP)
N (SRO)
Start 2C-5B Vacuum pump and secure 2C-5A Vacuum Pump OP-2106.010, Condenser Vacuum Operations 2
CVC2P36CFAL C (ATC)
C (SRO) 2P-36C charging pump breaker trip OP-2203.036, Loss of Charging AOP 3
DO_HS_8259_G CV82591 C (BOP)
C (SRO) 2RITS-8271-2 Containment Atmosphere Monitor (CAMS) coupling fails.
OP-2203.012K Annunciator 2K11 Corrective Action-XRI2RITS8231A DO_RITS82313_10 C (BOP)
C (SRO)
TS (SRO) 2RITS-8231-1 CAMS particulate detector fails high on start.
OP-2203.012J Annunciator 2K10 Corrective Action-4 RCLOCATCA C (ATC)
C (SRO)
TS (SRO) 15 gpm LOCA on RCS Cold Leg OP-2203.016, Excess RCS Leakage 5
RCP2P32BGRN RPSRXAUTO RPSRXMAN RPSDSSAUTO RPSDSSMAN MC (BOP)
MC (ATC)
C (All)
B RCP Trip and neither RPS nor DSS will automatically or manually trip the reactor. CT1 OP-2202.001, Standard Post Trip Actions (SPTAs),
6 RCLOCATCA M (All)
LOCA Leakage rises to 250 gpm on trip. CT2 OP-2202.003, Loss of Coolant Accident EOP 7
K05-C02 C (BOP)
C (SRO) 2P-60B LPSI Motor Overload alarm OP-2203.012E, 2K-05 ACA End Point Cool down commenced after entry into LOCA EOP.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control
Scenario 1 Form 3.3-2 Target Quantitative Attributes (Section D.5.d)
Actual Attributes Malfunctions after EOP entry (1-2) 1 Abnormal Events (2-4) 3 Major Transients (1-2) 1 EOPs entered requiring substantive actions (1-2) 1 EOP contingencies requiring substantive actions ( 1per scenario set) 0 Pre-identified Critical Tasks (2) 2 Critical Task Safety Significance Initiating Cue Measurable Performance Standard Performance Feedback References CT-1:
Manually trip the reactor prior to finishing Reactivity Safety Function of SPTAs.
Following a reactor trip, safety systems are designed to keep the plant in a safe state by meeting specified critical safety function criteria (SFSC). If the heat generated by the reactor is greater than normal decay heat levels, then the heat removal capacity of the safety systems may be inadequate resulting in core damage.
Immediate Actions/Procedurally Directed Use the following as needed RPS Pushbuttons DSS Pushbutton Open 2B712 &
2B812 to de-energize MG sets.
Attempted RPS Trip Pushbuttons (2C03),
DSS Pushbutton, RPS Trip Pushbuttons (2C14).
Opened breakers 2B712 2B812 Reactor Tripped.
Reactor Power Lowering CE EPGB Simulator CTs: CT-01, Establish reactivity control (SPTA-
- 01)
CR-ANO-2-2010-948, Critical task criteria CT-2:
Commence RCS Cooldown within 30 minutes of entry into OP-2202.003, LOCA EOP.
Cooling down and depressurizing the RCS removes decay heat and lowers the DP at the break, slowing the leak rate and reducing makeup volume required. SDC entry conditions are also required for long-term cooling.
Procedural Direction.
Commence RCS Cooldown (LOCA EOP)
Using Steam Dump Bypass Control System in automatic or manual to open steam dumps and begin lowering RCS temperature.
RCS Tcold temperature lowering.
CE EPGB Simulator CTs: CT-20, Cool down and depressurize RCS (LOCA-09)
CR-ANO-2-2010-948, Critical task criteria
Scenario 1 Form 3.3-2 Scenario #1 NARRATIVE When the crew has completed their control room walk down and brief, they will start 2C-5B Vacuum pump and Secure 2C-5A Vacuum pump. (N-BOP/SRO)
When vacuum pumps have been swapped and cued by the lead examiner, C Charging pump will trip. The SRO will enter the Loss of Charging AOP. The ATC will check for a suction source and discharge flow path. The ATC will then start a backup charging pump by moving the lead charging pump selector switch. (C-ATC/SRO) [Site OE: CR-ANO-2-2015-0432, 2P-36A charging pump stopped running, CR-ANO-2-2001-0685, 2P-36C tripped.]
After a backup charging pump has been placed in service and cued by lead examiner, the in-service Containment Air Monitor System (CAMS) unit 2RITS-8271-2 coupling will fail. The ATC should report the 2K-11 H10 CNTMT Air Monitor trouble alarm and refer to the ACA. The BOP should investigate and determine that 2RITS-8271-2 has low flow. When contacted, the NLO will report the coupling has failed. (C-BOP/SRO)The BOP should use OP-2104.033 Ventilation System Operations to place the standby CAMS unit in service. When the standby CAMS unit is placed in service, the particulate detector will fail (C-BOP/SRO) requiring entry into Tech Spec 3.4.6.1 Action
- a. (TS-SRO) [Site OE: CR-ANO-2-2013-1880, CAMS particulate detector failure, CR-ANO 2011-2691, for CAMS unit low air flow and CR-ANO-2-2006-1191, for sample motor failure.]
At the lead examiners cue, a 15 gpm RCS leak will start. The SRO will enter the excess RCS leakage AOP, OP 2203.016. ATC and BOP will perform RCS Leak rate determinations. The SRO will enter Tech Spec 3.4.6.2. (TS-SRO) The SRO will direct the ATC to maintain pressurizer level within 5% of set point by starting additional charging pumps as needed. The SRO will also direct the ATC to isolate letdown to determine the leak location. (C-ATC/SRO) After the crew has determined the leak is not in letdown, they will then begin to restore letdown get ready for plant shutdown. [Industry OE: SEN-220, SEN-216, & SEN-182, RCS leakage events.]
After CRS has entered TS for RCS Leakage and cued by lead examiner, B Reactor Coolant Pump (RCP) will trip which should cause an automatic reactor trip. RPS will not function requiring a manual reactor trip from the Diverse Scram System (DSS). (C-ALL) The crew will trip the reactor by opening supply power to MG Sets 2B-712/812 (MC-BOP/ATC). After the reactor is tripped, a Large Break LOCA will occur. (M-ALL) The SRO will enter OP 2202.001, Standard Post Trip Actions (SPTAs). The crew should recognize the signs of LOCA and ensure Safety Injection Actuation Signal (SIAS) and Containment Cooling Actuation Signal (CCAS) actuated. The crew will restore service water to Component Cooling water (CCW). The CRS should direct Steam Generator pressure be lowered using Auto Local control of the Steam Dump Bypass Control System (SDBCS) to maintain MTS as RCS pressure lowers. After diagnosing and entering LOCA EOP, the ATC will commence cool down of the RCS and control RCS pressure to restore pressurizer level. The BOP will override Service Water to Component Cooling Water and Auxiliary Cooling Water. 2 minutes after SIAS, 2P-60B LPSI Motor Overload alarms. Crew will use Annunciator Corrective action and dispatch NLO. Following report of high amps on 2P-60B breaker 2A-405, crew will use ACA to secure 2P-60B LPSI pump. (C-BOP/SRO) [Industry OE: SEN-220, SEN-216, & SEN-182, RCS leakage events.]
Scenario 3 Form 3.3-1 Facility: ANO-2 Source: New Scenario #3 (New)
Op-Test No.: 2023 Examiners:
Operators:
Initial Conditions: 100% Power Turnover: #1 EDG Surveillance in progress for PMT run, 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> loaded run complete, ready to be unloaded and secured.
Scheduled evolution: Unload and secure #1 EDG using OP-2104.036, Emergency Diesel Generator.
Critical Tasks: Stabilize and control RCS pressure within the PT limits. Start at least one HPSI Pump.
Event No.
Malf. No.
Event Type*
Event Description 1
N (BOP)
N (SRO)
TS (SRO)
Unload and secure #1 EDG OP-2104.036, Emergency Diesel Generator Operations 2
K12-C05 MC (ATC)
C (ATC)
C (SRO)
Boric Acid Makeup Tank Temperature Low Alarms OP-2203.012L, Annunciator 2K12 Corrective Actions 3
K05-H05 C (BOP)
C (SRO) 2A-4 Vital 4160 Bus Room Cooler belt breaks.
OP=2203.012E, Annunciator 2K05 Corrective Actions 4
CWS2P3BFLT R (ATC)
C (BOP)
C (SRO) 2P-3B Circulating Water Pump Trips OP-2203.019, Loss of Condenser Vacuum AOP 5
SGBTUBE C (ALL)
TS (SRO) 6 gpm steam generator tube leak on B Steam Generator.
OP-2203.038 Primary to Secondary Leakage AOP 6
MSSGBLK M (All)
Excess Steam Demand inside containment. CT1 OP-2202.001, Standard Post Trip Actions EOP OP-2202.009, Functional Recovery EOP 7
ESFSIAS2 MC (BOP)
C (BOP)
C (SRO) 2P-89A & B HPSI Pumps fail to start on SIAS. CT2 Steam Generator Tube Leak Rises to 80 gpm on reactor Trip.
OP-2202.010 Standard Attachments EOP End Point Post Blowdown Control is established and at least one HPSI pump is in service.
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS)Tech Spec, (MC)Manual Control
Scenario 3 Form 3.3-2 Target Quantitative Attributes (Section D.5.d)
Actual Attributes Malfunctions after EOP entry (1-2) 1 Abnormal Events (2-4) 3 Major Transients (1-2) 2 EOPs entered requiring substantive actions (1-2) 1 EOP contingencies requiring substantive actions ( 1per scenario set) 1 Pre-identified Critical Tasks (2) 2 Critical Task Safety Significance Initiating Cue Measurable Performance Standard Performance Feedback References CT-1:
Stabilize and control RCS temperature after the ESD blowdown terminates. Maintain RCS pressure within the Pressure-Temperature limit of 200°F MTS.
If RCS heatup is allowed after SG blowdown, the RCS could over pressurize and result in lifting PZR and SG safeties.
These pressure stresses added to thermal stresses of rapid cooldown could present PTS concerns.
Procedurally Directed Maintain RCS post-cooldown conditions as follows:
Maintain RCS temperature by steaming intact SG using Upstream ADV.
Throttled 2CV-1001 Upstream ADV for A SG as needed to stabilize temperature post blowdown.
Core CET temperatures stable or lowering.
CT-07, Establish RCS temperature Control (SPTA-07, ESDE-05, HR-05)
CT-2:
Establish one full train of HPSI prior to zero degrees MTS.
SI flow keeps the core covered, cooled, and borated.
Inadequate HPSI flow could result in eventual core uncover and fuel damage.
Procedural Direction.
HPSI flow is throttled and HPSI throttle criteria are NOT met.
HPSI Pump not running after SIAS.
On 2C16/2C17, Start HPSI pump(s) not running following SIAS.
On 2C16/2C17 indications of HPSI Pressure.
CT-16 Establish required SI flow (IC-
- 03)
EN-OP-123 Time Critical Operation Actions,
Scenario 3 Form 3.3-2 Scenario #1 NARRATIVE Simulator session begins with the plant at 100% power steady state. The #1 EDG is in service and running at 1400 kW. The BOP will unload and secure the #1 Emergency Diesel Generator. (N-BOP/SRO) The SRO will have to enter TS 3.8.1.1 action b and TS 3.4.4 action b. (TS-SRO)
When the #1 EDG is secured and the SRO has entered the appropriate TS or when cued by the lead examiner, the B Boric Acid Makeup Tank (BAM tank) low temperature alarm will annunciate.
(I-ATC/SRO) The crew will place the BAM tank on recirc and manually energize the 2T-6B BAM Tank Heaters to restore tank temperature to clear the alarm. (MC-ATC) [Site OE: CR-ANO 2011-03642, Boric Acid tank temperature control out of cal.]
After the ATC has placed the BAM tank on recirc and energized the heaters, and cued by the lead examiner, 2VUC-2A, 2A-4 Vital 4160V bus room cooler belts will break. This will cause a 2A-4 room cooler trouble alarm in the control room and actual room temperature to rise. The BOP will refer to OP-2203.012E, 2K05 Annunciator Corrective Actions (ACA). The BOP will dispatch a NLO to investigate 2VUC-2A. The NLO will report broken belts on 2VUC-2A and the BOP will use the ACA to place 2VUC-2B room cooler in service. (C-BOP/SRO) [Site OE: CR-ANO-2-2014-1955, Fan belt broken on room cooler]
After the BOP has started the idle vital bus room cooler and cued by lead examiner, the B Circulating Water pump will trip causing a reduction in Main Condenser vacuum. The SRO will enter Loss of Condenser Vacuum, 2203.019. The BOP will verify Condenser vacuum less than 7 inches HG Abs. The SRO will direct the ATC to commence emergency boration from a Boric Acid Makeup tank to lower reactor power. (R-ATC) The SRO will direct the BOP to lower turbine load to maintain condenser vacuum within the acceptable region described in the AOP. (C-BOP/SRO)
When condenser vacuum has started to improve and is within the acceptable region of the AOP attachment, emergency boration and CEA insertion will be secured. The crew should then prepare to commence a controlled down power to restore condenser vacuum less than 5.15 inches HG Abs. [Site OE: CR-ANO-2-2003-1142, A Circulating Water Pump Failure.]
When condenser vacuum has been stabilized or at the lead examiners cue, a primary to secondary leak will start. The CRS will enter the primary to secondary leakage AOP, OP 2203.038. ATC and BOP will perform RCS Leak rate determinations. The CRS will enter Tech Spec 3.4.6.2 action a and Tech Spec 3.4.5 action b. (TS-SRO)The CRS will direct the NLOs to control secondary contamination using standard attachment 19 and direct the chemists to sample the SGs for activity. The crew will isolate Main steam from A Steam Generator to 2P-7A EFW pump and commence a plant shutdown. (C-ALL) Isolation of Main Steam to 2P-7A will cause entry into Tech Spec 3.7.1.2 action a. (TS-SRO) [Site OE: Primary to secondary leak, CR-ANO-2-2005-0344, Industry OE: SEN 16, SER 33-87, SOER 83-2, SOER 93-1]
When the crew has commenced power reduction or at the lead examiners cue, a Main Steam Line Break will occur inside containment. (M-All) The crew will recognize containment pressure approaching trip set point and take the unit offline. The crew will then implement OP-2202.001, Standard Post Trip Actions (SPTA) EOP. The crew will assess safety functions. Main Steam Isolation (MSIS) and Containment Spray (CSAS) will actuate tripping Main Feedwater pumps, Condensate pumps, AFW pump, closing the MSIVs and feedwater block valves. When actuating SIAS, 2P-89A and 2P-89B HPSI Pumps will fail to start on SIAS requiring manually starting HPSI Pumps.(MC-BOP, C-BOP/SRO) [CR-ANO-2-2006-0848, Component failed to respond to SIAS
Scenario 3 Form 3.3-2 signal. [Industry OE for Excess Steam Demand, SOER 82-7, Reactor Vessel Pressurized Thermal Shock.]
Following the Reactor Trip, the leak in the B Steam Generator will rise to 80 gpm. After completing SPTAs, The SRO will diagnose Excess Steam Demand and Steam Generator Tube Rupture events and enter OP-2202.009, Functional Recovery EOP. The crew will maintain post blowdown temperature and pressure of the RCS to prevent pressurized thermal shock. The BOP will steam A SG using the upstream Atmospheric Dump valve when B SG blows dry. The ATC should use Auxiliary Spray to maintain RCS pressure.
Events and Evolutions Checklist Form 3.4-1 Crew A Facility: ANO-2 Date of Exam: March 2023 Operating Test No.: 2023 A
P P
L I
C A
N T
E V
E N
T T
Y P
E Scenarios 1
2 3
4 T
O T
A L
M I
N I
M U
M(*)
CREW POSITION CREW POSITION CREW POSITION CREW POSITION S
R O
A T
C B
O P
S R
O A
T C
B O
P S
R O
A T
C B
O P
S R
O A
T C
B O
P R
I U
RO SRO-I SRO-U X U1 RX 0
1 1 0 NOR 1,
1 2
1 1 1 I/C 2,3,4, 5,7 3,4,5, 7
9 4
4 2 MAJ 6
6 2
2 2 1 MC 7
1 1
1 0 TS 3,4 2
0 2 2 RO SRO-I SRO-U X U2 RX 0
1 1 0 NOR 1
1 1
1 1 I/C 2,3,4,5, 7
5 4
4 2 MAJ 6
1 2
2 1 MC 0
1 1 0 TS 1,5 2
0 2 2 RO X R1 SRO-I SRO-U RX 4
1 1
1 0 NOR 1
1 1
1 1 I/C 3, 5, 7 2,5 5
4 4 2 MAJ 6
6 2
2 2 1 MC 5
2 2
1 1 0 TS 0
0 2 2 RO X R2 SRO-I SRO-U RX 0
1 1 0 NOR 1
1 1
1 1 I/C 2,4,5 3,4,5, 7
7 4
4 2 MAJ 6
6 2
2 2 1 MC 4
7 2
1 1 0 TS 0
0 2 2
Events and Evolutions Checklist Form 3.4-1 Crew B Facility: ANO-2 Date of Exam: March 2023 Operating Test No.: 2023 A
P P
L I
C A
N T
E V
E N
T T
Y P
E Scenarios 1
2 3
4 T
O T
A L
M I
N I
M U
M(*)
CREW POSITION CREW POSITION CREW POSITION CREW POSITION S
R O
A T
C B
O P
S R
O A
T C
B O
P S
R O
A T
C B
O P
S R
O A
T C
B O
P R
I U
RO SRO-I SRO-U X U3 RX 0
1 1 0 NOR 1,
1 1
1 1 I/C 2,3,4, 5,7 5
4 4 2 MAJ 6
1 2
2 1 MC 0
1 1 0 TS 3,4 2
0 2 2 RO SRO-I SRO-U RX 1
1 0 NOR 1
1 1 I/C 4
4 2 MAJ 2
2 1 MC 1
1 0 TS 0
2 2 RO X R3 SRO-I SRO-U RX 4
1 1
1 0 NOR 1
1 1
1 1 I/C 3, 5, 7 2,5 5
4 4 2 MAJ 6
6 2
2 2 1 MC 5
2 2
1 1 0 TS 0
0 2 2 RO X R4 SRO-I SRO-U RX 0
1 1 0 NOR 1
1 1
1 1 I/C 2,4,5 3,4,5, 7
7 4
4 2 MAJ 6
6 2
2 2 1 MC 4
7 2
1 1 0 TS 0
0 2 2
Events and Evolutions Checklist Form 3.4-1 Crew C Facility: ANO-2 Date of Exam: March 2023 Operating Test No.: 2023 A
P P
L I
C A
N T
E V
E N
T T
Y P
E Scenarios 1
2 3
4 T
O T
A L
M I
N I
M U
M(*)
CREW POSITION CREW POSITION CREW POSITION CREW POSITION S
R O
A T
C B
O P
S R
O A
T C
B O
P S
R O
A T
C B
O P
S R
O A
T C
B O
P R
I U
RO SRO-I X I2 SRO-U RX 4
1 1
1 0 NOR 1,
1 1
1 1 I/C 2,3,4, 5,7 2,5 7
4 4 2 MAJ 6
6 2
2 2 1 MC 2
1 1
1 0 TS 3,4 2
0 2 2 RO SRO-I X I1 SRO-U RX 0
1 1 0 NOR 1
1 2
1 1 1 I/C 3, 5, 7 2,3,4,5, 7
8 4
4 2 MAJ 6
6 2
2 2 1 MC 5
1 1
1 0 TS 1,5 2
0 2 2 RO SRO-I X I3 SRO-U RX 0
1 1 0 NOR 1
1 1
1 1 I/C 2,4,5 2,3,4,5, 7
8 4
4 2 MAJ 6
6 2
2 2 1 MC 4
1 1
1 0 TS 1,5 2
0 2 2 RO SRO-I SRO-U RX 1
1 0 NOR 1
1 1 I/C 4
4 2 MAJ 2
2 1 MC 1
1 0 TS 0
2 2