ML23199A148
| ML23199A148 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 02/03/2023 |
| From: | NRC/RGN-III/DORS/OB |
| To: | Florida Power & Light Energy Point Beach |
| Jim Nance | |
| Shared Package | |
| ML22007A029 | List: |
| References | |
| Download: ML23199A148 (1) | |
Text
1 Form 4.1-PWR Pressurized-Water Reactor Examination Outline Facility: Point Beach Nuclear Power Station, Units 1 & 2 K/A Catalog Rev. 3 Rev.
0 Date of Exam: 2/13/2023 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
2 3
3 3
4 3
18 3
3 6
2 2
1 1
2 1
1 8
2 2
4 Tier Totals 4
4 4
5 5
4 26 5
5 10
- 2.
Plant Systems 1
3 3
2 2
3 3
2 3
2 2
3 28 3
2 5
2 1
0 1
1 1
1 1
0 1
1 1
9 0
1 2
3 Tier Totals 4
3 3
3 4
4 3
3 3
3 4
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.
2 ES-4.1-PWR PWR Examination Outline (Point Beach)
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 (000007) (EPE 7; BW E02 & E10; CE E02) Reactor Trip, Stabilization, Recovery X
(000007EK1.01) Knowledge of the operational implications and/or cause and effect relationships of the following concepts as they apply to (EPE 7) REACTOR TRIP: (CFR: 41.8 / 41.10 / 45.3):
Principles of neutron detection 3.3 1
2 (000008) (APE 8)
Pressurizer Vapor Space Accident X
(000008AA2.06) Ability to determine and/or interpret the following as they apply to (APE 8) PRESSURIZER VAPOR Space Accident (CFR: 43.5 / 45.13): PORV logic control under low-pressure conditions 3.0 2
3 (000011) (EPE 11)
Large Break LOCA X
(000011EK2.03) Knowledge of the relationship between (EPE 11)
LARGE-Break LOCA and the following systems or components (CFR: 41.7 / 45.7): RCS 4.3 3
4 (000015) (APE 15)
Reactor Coolant Pump Malfunctions X
(000015AA1.24) Ability to operate and/or monitor the following as they apply to (APE 15) REACTOR COOLANT Pump Malfunctions (CFR: 41.7 / 45.5 / 45.6): RCP thermal barrier 3.8 4
5 (000027) (APE 27)
Pressurizer Pressure Control System Malfunction X
(000027AA1.01) Ability to operate and/or monitor the following as they apply to (APE 27) PRESSURIZER PRESSURE Control System Malfunction (CFR: 41.7 / 45.5 / 45.6): PZR heaters, sprays, and PORVs 3.8 5
6 (000029) (EPE 29)
Anticipated Transient Without Scram X
(000029EA2.14) Ability to determine and/or interpret the following as they apply to (EPE 29) ANTICIPATED TRANSIENT WITHOUT SCRAM (ATWS) (CFR: 43.5 / 45.13): Occurrence of a reactor trip 4.6 6
7 (000038) (EPE 38)
Steam Generator Tube Rupture X
(000038EK2.13) Knowledge of the relationship between (EPE 38)
STEAM GENERATOR Tube Rupture and the following systems or components (CFR: 41.7 / 41.8 / 45.4 / 45.7 / 45.8): Main steam system 3.6 7
8 (000040) (APE 40; BW E05; CE E05; W E12) Steam Line Rupture - Excessive Heat Transfer X
(000040) (APE 40; BW E05; CE E05; W E12) Steam Line Rupture
- Excessive Heat Transfer (G2.4.18) EMERGENCY PROCEDURES/PLAN: Knowledge of the specific bases for emergency and abnormal operating procedures (CFR: 41.10 / 43.1
/ 45.13) 3.3 8
9 (000054) (APE 54; CE E06) Loss of Main Feedwater X
(000054AA2.09) Ability to determine and/or interpret the following as they apply to (APE 54) LOSS OF Main Feedwater (CFR: 43.5 /
45.13): S/G dryout conditions 4.1 9
10 (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 10 11 (000057) (APE 57)
Loss of Vital AC Instrument Bus X
(000057) (APE 57) Loss of Vital AC Electrical Instrument Bus (G2.1.19) CONDUCT OF OPERATIONS: Ability to use available indications to evaluate system or component status (CFR: 41.10 /
45.12) 3.9 11 12 (000058) (APE 58)
Loss of DC Power X
(000058AK1.04) Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to (APE 58) LOSS OF DC Power (CFR: 41.8 / 41.10 / 45.3): Loss of breaker protection 3.7 12 13 (000062) (APE 62)
Loss of Service Water X
(000062AK3.03) Knowledge of the reasons for the following responses and/or actions as they apply to (APE 62) LOSS OF SERVICE WATER (CFR: 41.4 / 41.8 / 45.7): Guidance actions contained in AOPs for loss of service water 3.9 13 14 (000065) (APE 65)
Loss of Instrument Air X
(000065) (APE 65) Loss of Instrument Air (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 14 15 (000077) (APE 77)
Generator Voltage and Electric Grid Disturbances X
(000077AA1.02) Ability to operate and/or monitor the following as they apply to (APE 77) GENERATOR VOLTAGE AND ELECTRIC Grid Disturbances (CFR: 41.5 / 41.10 / 45.5 / 45.7 / 45.8):
Turbine/generator controls 3.6 15
3 ES-4.1-PWR PWR Examination Outline (Point Beach)
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#
16 (W E04) LOCA Outside Containment X
(WE04EA2.03) Ability to determine and/or interpret the following as they apply to (W E04) LOCA Outside Containment (CFR: 41.10 /
43.5 / 45.13): RCS pressure 3.9 16 17 (W E11) Loss of Emergency Coolant Recirculation X
(WE11EK2.09) Knowledge of the relationship between (W E11)
LOSS OF EMERGENCY Coolant Recirculation and the following systems or components (CFR: 41.7 / 41.8 / 45.2 / 45.4): ECCS 4.1 17 18 (BW E04; W E05)
Inadequate Heat Transfer - Loss of Secondary Heat Sink X
(WE05EK3.09) Knowledge of the reasons for the following responses and/or actions as they apply to (W E05) Loss of Secondary Heat Sink (CFR: 41.5 / 41.10 / 45.6 / 45.13):
Depressurizing an S/G and establishing feed flow from the CDS 4.0 18 19 (000009) (EPE 9)
Small Break LOCA X
(000009) (EPE 9) Small Break LOCA (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 76 20 (000022) (APE 22)
Loss of Reactor Coolant Makeup X
(000022) (APE 22) Loss of Reactor Coolant Makeup (G2.1.2)
CONDUCT OF OPERATIONS: Knowledge of operator responsibilities during any mode of plant operation (CFR:
41.10 / 43.1 / 45.13) 4.4 77 21 (000025) (APE 25)
Loss of Residual Heat Removal System X
(000025AA2.08) Ability to determine and/or interpret the following as they apply to (APE 25) LOSS OF RESIDUAL Heat Removal System (CFR: 43.5 / 45.13): RHR heat exchange inlet and outlet temperatures 3.5 78 22 (000026) (APE 26)
Loss of Component Cooling Water X
(000026AA2.01) Ability to determine and/or interpret the following as they apply to (APE 26) LOSS OF Component Cooling Water (CFR: 41.10 / 43.5 / 45.13): Location of a leak in the CCWS 3.5 79 23 (000027) (APE 27)
Pressurizer Pressure Control System Malfunction X
(000027AA2.09) Ability to determine and/or interpret the following as they apply to (APE 27) PRESSURIZER PRESSURE Control System Malfunction (CFR: 43.5 / 45.13): Reactor power 3.4 80 24 (000055) (EPE 55)
Station Blackout X
(000055) (EPE 55) Station Blackout (G2.1.23) CONDUCT OF OPERATIONS: Ability to perform general and/or normal operating procedures during any plant condition (CFR: 41.10 /
43.5 / 45.2 / 45.6) 4.4 81 K/A Category Totals:
2 3
3 3
4/3 3/3 Group Point Total:
18/6
4 ES-4.1-PWR PWR Examination Outline (Point Beach)
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#
25 (000005) (APE 5)
Inoperable/Stuck Control Rod X
(000005) (APE 5) Inoperable/Stuck Control Rod (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) 4.5 19 26 (000024) (APE 24)
Emergency Boration X
(000024AK1.01) Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to (APE 24) EMERGENCY Boration (CFR: 41.6 / 41.7 / 41.8 / 41.10 /
45.3): Relationship between boron addition and change in T-ave.
3.9 20 27 (000033) (APE 33)
Loss of Intermediate Range Nuclear Instrumentation X
(000033AK2.03) Knowledge of the relationship between (APE 33)
LOSS OF INTERMEDIATE RANGE Nuclear Instrumentation and the following systems or components (CFR: 41.7 / 45.7): RPS 3.8 21 28 (000036) (APE 36; BW/A08) Fuel-Handling Incidents X
(000036AA2.03) Ability to determine and/or interpret the following as they apply to (APE 36) FUEL HANDLING INCIDENTS (CFR:
41.7 / 43.5 / 43.7 / 45.13): Magnitude of potential radioactive release 3.5 22 29 (000069) (APE 69; W E14) High Containment Pressure X
(WE14EA1.06) Ability to operate and/or monitor the following as they apply to (W E14) HIGH CONTAINMENT PRESSURE (CFR:
41.5 to 41.8 / 45.5 to 45.8): CSS 4.2 23 30 (W E01 & E02)
Rediagnosis & SI Termination X
(WE02EK3.05) Knowledge of the reasons for the following responses and/or actions as they apply to (W E02) SI TERMINATION (CFR: 41.5 / 41.10 / 45.6 / 45.13): Implementing procedure foldout page actions 3.8 24 31 (W E13) Steam Generator Overpressure X
(WE13EA1.05) Ability to operate and/or monitor the following as they apply to (W E13) STEAM Generator Overpressure (CFR: 41.5 to 41.8 / 45.5 to 45.8): RCS 3.4 25 32 (W E15)
Containment Flooding X
(WE15EK1.04) Knowledge of the operational implications and/or cause and effect relationships of the following as they apply to (W E15) Containment Flooding (CFR: 41.5 / 41.7 / 45.7 / 45.8):
Design-basis flood level in containment 3.1 26 33 (000003) (APE 3)
Dropped Control Rod X
(000003AA2.06) Ability to determine and/or interpret the following as they apply to (APE 3) DROPPED Control Rod (CFR: 43.5 / 45.13): Ex-core NIS 3.8 82 34 (000059) (APE 59)
Accidental Liquid Radwaste Release X
(000059AA2.05) Ability to determine and/or interpret the following as they apply to (APE 59) ACCIDENTAL LIQUID Radwaste Release (CFR: 43.5 / 45.13): The occurrence of automatic safety actions as a result of a high-radiation signal 3.9 83 35 (000061) (APE 61)
Area Radiation Monitoring System Alarms X
(000061) (APE 61) Area Radiation Monitoring System Alarms (G2.2.15) EQUIPMENT CONTROL: Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, lineups, or tagouts (reference potential) (CFR: 41.10 / 43.3 / 45.13) 4.3 84 36 (000067) (APE 67)
Plant Fire On Site X
(000067) (APE 67) Plant Fire On Site (G2.4.5) EMERGENCY PROCEDURES/PLAN: Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions (CFR: 41.10 / 43.5 / 45.13) 4.3 85 000001 (APE 1)
Continuous Rod Withdrawal / 1 000028 (APE 28)
Pressurizer (PZR)
Level Control Malfunction / 2 000032 (APE 32)
Loss of Source Range Nuclear Instrumentation / 7 000037 (APE 37)
Steam Generator Tube Leak / 3
5 ES-4.1-PWR PWR Examination Outline (Point Beach)
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#
000051 (APE 51)
Loss of Condenser Vacuum / 4 000060 (APE 60)
Accidental Gaseous Radwaste Release / 9 000068 (APE 68; BW A06) Control Room Evacuation / 8 000074 (EPE 74; W E06 & E07)
Inadequate Core Cooling / 4 000076 (APE 76)
High Reactor Coolant Activity / 9 000078 (APE 78*)
RCS Leak / 3 (W E16) High Containment Radiation /9 (BW A01) Plant Runback / 1 (BW A02 & A03)
Loss of NNI-X/Y/7 (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 (CE A16) Excess RCS Leakage / 2 (CE E09) Functional Recovery (CE E13*) Loss of Forced Circulation /
LOOP / Blackout / 4 K/A Category Totals:
2 1
1 2
1/2 1/2 Group Point Total:
8/4
6 ES-4.1-PWR PWR Examination Outline (Point Beach)
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 (003) (SF4P RCP)
REACTOR COOLANT PUMP SYSTEM X
(003A2.04) Ability to (a) predict the impacts of the following on the (SF4P RCP) REACTOR COOLANT PUMP 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 / 45.3 /
45.13): Effects of fluctuation of VCT pressure on RCP seal injection flow 3.1 27 38 (004) (SF1; SF2 CVCS) CHEMICAL AND VOLUME CONTROL SYSTEM X
(004A1.11) Ability to predict and/or monitor changes in parameters associated with operation of the (SF1; SF2 CVCS) CHEMICAL AND VOLUME CONTROL SYSTEM, including (CFR: 41.5 to 41.7 / 45.5):
Letdown and charging flows 3.8 28 39 (005) (SF4P RHR)
RESIDUAL HEAT REMOVAL SYSTEM X
(005) (SF4P RHR) RESIDUAL HEAT REMOVAL SYSTEM (191003K1.01) CONTROLLERS AND POSITIONERS (CFR: 41.7):
Function and operation of flow controller in manual and automatic modes 3.2 29 40 (006) (SF2; SF3 ECCS)
EMERGENCY CORE COOLING SYSTEM X
(006A4.11) Ability to manually operate and/or monitor the (SF2; SF3 ECCS) EMERGENCY CORE COOLING SYSTEM in the control room (CFR: 41.7 / 45.5 to 45.8):
Overpressure protection system 3.7 30 41 (006) (SF2; SF3 ECCS)
EMERGENCY CORE COOLING SYSTEM X
(006K5.04) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF2; SF3 ECCS)
EMERGENCY CORE COOLING SYSTEM (CFR: 41.5 / 45.7): Brittle fracture, including causes and preventive actions 3.6 31 42 (007) (SF5 PRTS)
PRESSURIZER RELIEF/QUENCH TANK SYSTEM X
(007A2.05) Ability to (a) predict the impacts of the following on the (SF5 PRTS) PRESSURIZER RELIEF/QUENCH TANK 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 / 45.3 / 45.13):
Exceeding PRT/quench tank high-pressure limits 3.9 32 43 (007) (SF5 PRTS)
PRESSURIZER RELIEF/QUENCH TANK SYSTEM X
(007K6.09) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF5 PRTS)
PRESSURIZER RELIEF/QUENCH TANK SYSTEM (CFR: 41.7 / 45.7):
Makeup/fill water 2.5 33 44 (008) (SF8 CCW)
COMPONENT COOLING WATER SYSTEM X
(008A2.10) Ability to (a) predict the impacts of the following on the (SF8 CCW) COMPONENT COOLING WATER 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 /45.3 /
45.13): SWS malfunction 3.4 34
7 ES-4.1-PWR PWR Examination Outline (Point Beach)
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#
45 (008) (SF8 CCW)
COMPONENT COOLING WATER SYSTEM X
(008K2.01) Knowledge of electrical power supplies to the following (CFR: 41.7): (SF8 CCW)
COMPONENT COOLING WATER SYSTEM CCW valves 3.0 35 46 (010) (SF3 PZR PCS)
PRESSURIZER PRESSURE CONTROL SYSTEM X
(010K6.08) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF3 PZR PCS)
PRESSURIZER PRESSURE CONTROL SYSTEM (CFR: 41.7 /
45.7): PZR LCS 3.4 36 47 (012) (SF7 RPS)
(012K2.01) Knowledge of electrical power supplies to the following (CFR: 41.7): (SF7 RPS) REACTOR PROTECTION SYSTEM RPS channels, components, and interconnections 4.0 37 48 (013) (SF2 ESFAS)
ENGINEERED SAFETY FEATURES ACTUATION SYSTEM X
(013K4.02) Knowledge of (SF2 ESFAS) ENGINEERED SAFETY FEATURES ACTUATION SYSTEM design features and/or interlocks that provide for the following (CFR:
41.2 / 41.6 / 41.7): Containment isolation signal actuation/reset 4.3 38 49 (022) (SF5 CCS)
CONTAINMENT COOLING SYSTEM X
(022A3.01) Ability to monitor automatic features of the (SF5 CCS)
CONTAINMENT COOLING SYSTEM, including (CFR: 41.7 /
45.5): Initiation of ESFAS mode of operation 4.2 39 50 (022) (SF5 CCS)
CONTAINMENT COOLING SYSTEM X
(022K1.05) Knowledge of the physical connections and/or cause and effect relationships between the (SF5 CCS) CONTAINMENT COOLING SYSTEM and the following systems (CFR: 41.2 to 41.9 / 45.7 to 45.8): ESFAS 4.1 40 51 (026) (SF5 CSS)
CONTAINMENT SPRAY SYSTEM X
(026K1.02) Knowledge of the physical connections and/or cause and effect relationships between the (SF5 CSS) CONTAINMENT SPRAY SYSTEM and the following systems (CFR: 41.2 to 41.9 / 45.7 to 45.8):
Cooling water 3.6 41 52 (039) (SF4S MSS)
MAIN AND REHEAT STEAM SYSTEM X
(039K3.07) Knowledge of the effect that a loss or malfunction of the (SF4S MSS) MAIN AND REHEAT STEAM SYSTEM will have on the following systems or system parameters (CFR: 41.7 / 45.6):
Auxiliary steam system 2.6 42 53 (059) (SF4S MFW)
MAIN FEEDWATER SYSTEM X
(059K2.01) Knowledge of electrical power supplies to the following (CFR: 41.7): (SF4S MFW) MAIN FEEDWATER SYSTEM MFW system pumps 3.2 43 54 (061) (SF4S AFW)
AUXILIARY /
(061K3.01) Knowledge of the effect that a loss or malfunction of the (SF4S AFW)
AUXILIARY/EMERGENCY FEEDWATER SYSTEM will have on the following systems or system parameters (CFR: 41.5 / 41.7 /
45.6): RCS 4.3 44
8 ES-4.1-PWR PWR Examination Outline (Point Beach)
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#
AC ELECTRICAL DISTRIBUTION SYSTEM X
(062A3.07) Ability to monitor automatic operation of the (SF6 ED AC) AC ELECTRICAL DISTRIBUTION SYSTEM, including (CFR: 41.7 / 45.5): Automatic bus transfer 3.6 45 56 (063) (SF6 ED DC)
DC ELECTRICAL DISTRIBUTION SYSTEM X
(063A1.04) Ability to predict and/or monitor changes in parameters associated with operation of the (SF6 ED DC) DC ELECTRICAL DISTRIBUTION SYSTEM, including (CFR: 41.5 / 45.5): Battery charger voltage and/or current 3.3 46 57 (064) (SF6 EDG)
EMERGENCY DIESEL GENERATOR SYSTEM X
(064) (SF6 EDG) EMERGENCY DIESEL GENERATOR SYSTEM (G2.1.30) CONDUCT OF OPERATIONS: Ability to locate and operate components, including local controls (CFR: 41.7 / 45.7) 4.4 47 58 (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 GENERATORS (CFR: 41.5
/ 45.7): Operating overloaded or underloaded 3.6 48 59 (073) (SF7 PRM)
PROCESS RADIATION MONITORING SYSTEM X
(073) (SF7 PRM) PROCESS RADIATION MONITORING SYSTEM (G2.3.12) RADIATION CONTROL:
Knowledge of radiological safety principles and procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, or alignment of filters (CFR: 41.12 / 43.4 / 45.9 / 45.10) 3.2 49 60 (073) (SF7 PRM)
PROCESS RADIATION MONITORING SYSTEM X
(073K4.02) Knowledge of (SF7 PRM) PROCESS RADIATION MONITORING SYSTEM design features and/or interlocks that provide for the following (CFR:
41.7): System actuations based on PRM signals 3.7 50 61 (076) (SF4S SW)
SERVICE WATER SYSTEM X
(076A4.01) Ability to manually operate and/or monitor the (SF4S SW) SERVICE WATER SYSTEM in the control room (CFR: 41.7 / 45.5 to 45.8): SWS pumps 3.9 51 62 (078) (SF8 IAS)
INSTRUMENT AIR SYSTEM X
(078K5.03) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF8 IAS) INSTRUMENT AIR SYSTEM (CFR: 41.5 / 45.7): Loss of instrument air 3.9 52 63 (103) (SF5 CNT)
CONTAINMENT SYSTEM X
(103K1.14) Knowledge of the physical connections and/or cause and effect relationships between the (SF5 CNT) CONTAINMENT SYSTEM and the following systems (CFR: 41.9 / 45.7 to 45.8): MRSS 3.2 53 64 (103) (SF5 CNT)
CONTAINMENT SYSTEM X
(103K6.10) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF5 CNT)
CONTAINMENT SYSTEM (CFR:
41.7 / 45.7): CSS 3.9 54
9 ES-4.1-PWR PWR Examination Outline (Point Beach)
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#
65 (026) (SF5 CSS)
CONTAINMENT SPRAY SYSTEM X
(026A2.04) Ability to (a) predict the impacts of the following on the (SF5 CSS) CONTAINMENT SPRAY 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 / 45.3 / 45.13): Failure of spray pump 4.0 86 66 (059) (SF4S MFW)
MAIN FEEDWATER SYSTEM X
(059) (SF4S MFW) MAIN FEEDWATER SYSTEM (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) 3.5 87 67 (061) (SF4S AFW)
AUXILIARY /
(061) (SF4S AFW) AUXILIARY /
EMERGENCY FEEDWATER SYSTEM (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 88 68 (062) (SF6 ED AC)
AC ELECTRICAL DISTRIBUTION SYSTEM X
(062A2.19) Ability to (a) predict the impacts of the following on the (SF6 ED AC) AC 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 / 43.5 / 45.3 / 45.13): Loss of Class 1E DC distribution system 4.1 89 69 (063) (SF6 ED DC)
DC ELECTRICAL DISTRIBUTION SYSTEM X
(063A2.03) 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 / 43.5 / 45.3 / 45.13):
Malfunction of battery chargers 3.6 90 (025) (SF5 ICE) ICE CONDENSER SYSTEM (053) (SF1; SF4P ICS*) INTEGRATED CONTROL SYSTEM K/A Category Totals:
3 3
2 2
3 3
2 3/3 2
2 3/2 Group Point Total:
28/5
10 ES-4.1-PWR PWR Examination Outline (Point Beach)
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#
70 (002) (SF2 RCS)
(002) (SF2 RCS) REACTOR COOLANT SYSTEM (G2.2.3)
EQUIPMENT CONTROL: (Multi-unit license) Knowledge of the design, procedural, and/or operational differences between units (CFR:
41.5 / 41.6 / 41.7 / 41.10 / 45.12) 3.8 55 71 (011) (SF2 PZR LCS)
PRESSURIZER LEVEL CONTROL SYSTEM X
(011K6.23) Knowledge of the effect of the following plant conditions, system malfunctions, or component malfunctions on the (SF2 PZR LCS)
PRESSURIZER LEVEL CONTROL SYSTEM (CFR: 41.7 / 45.7): Level channels 3.6 56 72 (016) (SF7 NNI)
NONNUCLEAR INSTRUMENTATION SYSTEM X
(016K5.02) Knowledge of the operational implications or cause and effect relationships of the following concepts as they apply to the (SF7 NNI) NONNUCLEAR INSTRUMENTATION SYSTEM (CFR: 41.5 / 45.7): Relationship between meter readings and actual parameter values 3.2 57 73 (017) (SF7 ITM) IN CORE TEMPERATURE MONITOR SYSTEM X
(017K4.02) Knowledge of (SF7 ITM)
IN CORE TEMPERATURE MONITOR SYSTEM design features and/or interlocks that provide for the following (CFR: 41.7): Sensing and determination of location core hot spots 3.4 58 74 (033) (SF8 SFPCS)
SPENT FUEL POOL COOLING SYSTEM X
(033K1.09) Knowledge of the physical connections and/or cause and effect relationships between the (SF8 SFPCS) SPENT FUEL POOL COOLING SYSTEM and the following systems (CFR: 41.2 to 41.9 / 45.7 to 45.8): RMS 3.1 59 75 (041) (SF4S SDS)
STEAM DUMP/TURBINE BYPASS CONTROL SYSTEM X
(041A1.02) Ability to predict and/or monitor changes in parameters associated with operation of the (SF4S SDS) STEAM DUMP/TURBINE BYPASS CONTROL SYSTEM, including (CFR: 41.5 / 45.5): Steam pressure 3.7 60 76 (050) (SF9 CRV*)
CONTROL ROOM VENTILATION X
(050A4.05) Ability to manually operate and/or monitor the (SF9 CRV) CONTROL ROOM VENTILATION in the control room (CFR: 41.7 / 45.5 to 45.8): Heaters 2.5 61 77 (055) (SF4S CARS)
CONDENSER AIR REMOVAL SYSTEM X
(055K3.01) Knowledge of the effect that a loss or malfunction of the (SF4S CARS) CONDENSER AIR REMOVAL SYSTEM will have on the following systems or system parameters (CFR: 41.7 / 45.6): Main condenser 3.8 62 78 (056) (SF4S CDS)
CONDENSATE SYSTEM X
(056A3.09) Ability to monitor automatic features of the (SF4S CDS) CONDENSATE SYSTEM, including (CFR: 41.7 / 45.5):
Automatic protection of MFW pump low suction pressure 3.6 63
11 ES-4.1-PWR PWR Examination Outline (Point Beach)
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#
79 (034) (SF8 FHS) FUEL HANDLING EQUIPMENT SYSTEM X
(034) (SF8 FHS) FUEL HANDLING EQUIPMENT SYSTEM (G2.2.6) EQUIPMENT CONTROL:
Knowledge of the process for making changes to procedures (CFR: 41.10 / 43.3 / 45.13) 3.6 91 80 (015) (SF7 NIS)
NUCLEAR INSTRUMENTATION SYSTEM X
(015) (SF7 NIS) NUCLEAR INSTRUMENTATION SYSTEM (G2.2.35) EQUIPMENT CONTROL: Ability to determine TS for mode of operation (CFR:
41.7 / 41.10 / 43.2 / 45.13) 4.5 92 81 (071) (SF9 WGS)
WASTE GAS DISPOSAL SYSTEM X
(071A2.03) Ability to (a) predict the impacts of the following on the (SF9 WGS) WASTE GAS DISPOSAL 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 / 45.3 / 45.13 /
45.8 to 45.9): WGS component malfunctions 2.7 93 (002) (SF2; SF4P RCS)
REACTOR COOLANT SYSTEM (014) (SF1 RPI) ROD POSITION INDICATION SYSTEM (015) (SF7 NI)
NUCLEAR INSTRUMENTATION SYSTEM (027) (SF5 CIRS)
CONTAINMENT IODINE REMOVAL SYSTEM (034) (SF8 FHS) FUEL HANDLING EQUIPMENT SYSTEM (035) (SF4P SG) STEAM GENERATOR SYSTEM (045) (SF4S MTG) MAIN TURBINE GENERATOR SYSTEM (068) (SF9 LRS) LIQUID RADWASTE SYSTEM (072) (SF7 ARM) AREA RADIATION MONITORING SYSTEM (075) (SF8 CW)
CIRCULATING WATER SYSTEM (079) (SF8 SAS**)
STATION AIR SYSTEM (086) (SF8 FPS) FIRE PROTECTION SYSTEM K/A Category Totals:
1 0
1 1
1 1
1 0/1 1
1 1/2 Group Point Total:
9/3
12 Form 4.1-COMMON Common Examination Outline ES-4.1-COMMON COMMON Examination Outline (Point Beach)
Facility:
Point Beach Nuclear Power Station, Units 1 & 2 Date of Exam:
2/13/2023 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 G2.1.15 (G2.1.15) CONDUCT OF OPERATIONS: Knowledge of administrative requirements for temporary management direction, such as standing orders, night orders, or operations memoranda (CFR: 41.10 / 45.12) 82 2.7 64 G2.1.47 (G2.1.47) CONDUCT OF OPERATIONS: Ability to direct non-licensed personnel activities inside the control room (CFR: 41.10 /
43.5 / 45.5 / 45.12 / 45.13) 83 3.2 65 G2.1.25 (G2.1.25) CONDUCT OF OPERATIONS: Ability to interpret reference materials, such as graphs, curves, and tables (reference potential) (CFR: 41.10 / 43.5 / 45.12) 84 4.2 94 G2.1.39 (G2.1.39) CONDUCT OF OPERATIONS: Knowledge of conservative decision-making practices (CFR: 41.10 / 43.5 /
45.12) 85 4.3 95 Subtotal N/A 2
N/A 2
- 2.
Equipment Control 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) 86 2.9 66 G2.2.20 (G2.2.20) EQUIPMENT CONTROL: Knowledge of the process for managing troubleshooting activities (CFR: 41.10 / 43.5 / 45.13) 87 2.6 67 G2.2.12 (G2.2.12) EQUIPMENT CONTROL: Knowledge of surveillance procedures (CFR: 41.10 / 43.2 / 45.13) 88 4.1 96 G2.2.36 (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) 89 4.2 97 Subtotal N/A 2
N/A 2
- 3.
Radiation Control G2.3.11 (G2.3.11) RADIATION CONTROL: Ability to control radiation releases (CFR: 41.11 / 43.4 / 45.10) 90 3.8 68 G2.3.5 (G2.3.5) RADIATION CONTROL: Ability to use RMSs, such as fixed radiation monitors and alarms or personnel monitoring equipment (CFR: 41.11 / 41.12 / 43.4 / 45.9) 91 2.9 98 Subtotal N/A 1
N/A 1
- 4.
Emergency Procedures /
Plan G2.4.12 (G2.4.12) EMERGENCY PROCEDURES/PLAN: Knowledge of operating crew responsibilities during emergency and abnormal operations (CFR: 41.10 / 45.12) 92 4.0 69 G2.4.28 (G2.4.28) EMERGENCY PROCEDURES/PLAN: Knowledge of procedures relating to a security event (ensure that the test item includes no safeguards information) (CFR: 41.10 / 43.5 / 45.13) 93 4.1 99 G2.4.35 (G2.4.35) EMERGENCY PROCEDURES/PLAN: Knowledge of non-licensed operator responsibilities during an emergency (CFR:
41.10 / 43.1 / 43.5 / 45.13) 94 4.0 100 Subtotal N/A 1
N/A 2
Tier 3 Point Total N/A 6
N/A 7
13 Form 4.1-COMMON Common Examination Outline ES-4.1-COMMON COMMON Examination Outline (Point Beach)
Facility:
Point Beach Nuclear Power Station, Units 1 & 2 Date of Exam:
2/13/2023 Theory (Tier 4) (RO)
Category K/A #
Topic RO Item #
IR Q#
Reactor Theory 192006 (192006K1.01) FISSION PRODUCT POISONS (CFR: 41.1): Define fission product poison 95 2.6 70 192007 (192007K1.05) FUEL DEPLETION AND BURNABLE POISONS (CFR: 41.1): Describe the effects of boration/dilution on reactivity during forced-flow and natural circulation conditions 96 3.2 71 192008 (192008K1.27) REACTOR OPERATIONAL PHYSICS (CFR: 41.1):
(NORMAL REACTOR SHUTDOWN) Explain the relationship between decay heat generation and (1) power level history, (2) power production, and (3) time since reactor shutdown 97 3.4 72 Subtotal N/A 3
Thermodynamics 193003 (193003K1.14) STEAM (CFR: 41.14): Define the following term: --
superheated vapor 98 2.5 73 193004 (193004K1.15) THERMODYNAMIC PROCESS (CFR: 41.14):
(THROTTLING AND THE THROTTLING PROCESS) Determine the exit conditions for a throttling process based on the use of steam and/or water 99 2.8 74 193009 (193009K1.01) CORE THERMAL LIMITS (CFR: 41.14): Explain radial peaking factor 100 2.8 75 Subtotal N/A 3
Tier 4 Point Total N/A 6