ML22136A079
| ML22136A079 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/19/2019 |
| From: | Randy Baker NRC/RGN-III/DRS/OLB |
| To: | Florida Power & Light Energy Point Beach |
| Baker R | |
| Shared Package | |
| ML17215A928 | List: |
| References | |
| Download: ML22136A079 (15) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: POINT BEACH NUCLEAR PLANT UNITS 1 and 2 Date of Exam: JULY 15 - JULY 26, 2019 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 N/A 3
3 N/A 3
18 3
3 6
2 1
2 1
1 2
2 9
2 2
4 Tier Totals 4
5 4
4 5
5 27 5
5 10
- 2.
Plant Systems 1
3 2
3 3
2 2
3 3
3 2
2 28 3
2 5
2 0
1 1
1 1
1 1
1 1
1 1
10 0
2 1
3 Tier Totals 3
3 4
4 3
3 4
4 4
3 3
38 5
3 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
3 2
3 2
2 1
2 2
Note: 1.
Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)
- 2.
The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points, and the SRO-only exam must total 25 points.
- 3.
Systems/evolutions within each group are identified on the outline. Systems or evolutions that do not apply at the facility should be deleted with justification. Operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
- 4.
Select topics from as many systems and evolutions as possible. Sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5.
Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
- 7.
The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics IRs for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. If fuel-handling equipment is sampled in a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2. (Note 1 does not apply). Use duplicate pages for RO and SRO-only exams.
- 9.
For Tier 3, select topics from Section 2 of the K/A catalog and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.
G* Generic K/As These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.
These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.
ES-401 2
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 000007 (EPE 7; BW E02&E10; CE E02)
Reactor Trip, Stabilization, Recovery / 1 X
EK1.03 - Knowledge of the operational implications of the following concepts as they apply to the reactor trip: Reasons for closing the main turbine governor valve and main turbine stop valve after a reactor trip.
3.7 1
000008 (APE 8) Pressurizer Vapor Space Accident / 3 X
AK2.01 - Knowledge of the interrelations between the Pressurizer Vapor Space Accident and the following: Valves 2.7 2
000009 (EPE 9) Small Break LOCA / 3 X
EK2.03 - Knowledge of the interrelations between the small break LOCA and the following: S/Gs.
3.0 3
000011 (EPE 11) Large Break LOCA / 3 X
EA1.06 - Ability to operate and/or monitor the following as they apply to a Large Break LOCA:
D/Gs.
4.2 4
000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 X
AA2.09 - Ability to determine and interpret the following as they apply to Reactor Coolant Pump Malfunctions (Loss of RC Flow): When to secure RCPs on high stator temperatures.
3.4 5
000022 (APE 22) Loss of Reactor Coolant Makeup / 2 000025 (APE 25) Loss of Residual Heat Removal System / 4 X
2.4.8 - Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
3.8 6
000026 (APE 26) Loss of Component Cooling Water / 8 X
AA2.02 - Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: The cause of possible CCW loss.
2.9 7
000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 X
AA1.04 - Ability to operate and/or monitor the following as they apply to the Pressurizer Pressure Control Malfunctions: Pressure recovery using emergency-only heaters.
3.9 8
000029 (EPE 29) Anticipated Transient Without Scram / 1 X
EK3.10 - Knowledge of the reasons for the following responses as they apply to the ATWS:
Manual rod insertion.
4.1 9
000038 (EPE 38) Steam Generator Tube Rupture / 3 000040 (APE 40; BW E05; CE E05; W E12)
Steam Line RuptureExcessive Heat Transfer / 4 X
AK2.02 - Knowledge of the interrelations between the Steam Line Rupture and the following: Sensors and detectors.
2.6 10 000054 (APE 54; CE E06) Loss of Main Feedwater /4 X
AK1.02 - Knowledge of the operational implications of the following concepts as they apply to Loss of Main Feedwater: Effects of feedwater introduction on dry S/G.
3.6 11 000055 (EPE 55) Station Blackout / 6 X
EK1.02 - Knowledge of the operational implications of the following concepts as they apply to the Station Blackout: Natural circulation cooling.
4.1 12 000056 (APE 56) Loss of Offsite Power / 6 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 X
AK3.01 - Knowledge of the reasons for the following responses as they apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital AC electrical instrument bus.
4.1 13 000058 (APE 58) Loss of DC Power / 6 X
AA1.03 - Ability to operate and/or monitor the following as they apply to Loss of DC Power: Vital and battery bus components.
3.1 14 000062 (APE 62) Loss of Nuclear Service Water / 4 X
AA2.01 - Ability to determine or interpret the following as they apply to the Loss of Nuclear Service Water: Location of a leak in the SWS.
2.9 15 000065 (APE 65) Loss of Instrument Air / 8 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 X
2.1.32 - Ability to explain and apply system limits and precautions.
3.8 16 (W E04) LOCA Outside Containment / 3 X
2.4.35 - Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.
3.8 17
ES-401 3
Form ES-401-2 (W E11) Loss of Emergency Coolant Recirculation / 4 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 X
EK3.1 - Knowledge of the reasons for the following responses as they apply to the (Loss of Secondary Heat Sink): Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.
3.4 18 K/A Category Totals:
3 3
3 3
3 3
Group Point Total:
18
ES-401 4
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 000001 (APE 1) Continuous Rod Withdrawal / 1 000003 (APE 3) Dropped Control Rod / 1 X 2.4.45 - Ability to prioritize and interpret the significance of each annunciator or alarm.
4.1 19 000005 (APE 5) Inoperable/Stuck Control Rod / 1 X
AA2.03 - Ability to determine and interpret the following as they apply to the Inoperable/Stuck Control Rod: Required action if more than one rod is stuck or inoperable.
3.5 20 000024 (APE 24) Emergency Boration / 1 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 X
AK1.01 - Knowledge of the operational implications of the following concepts as they apply to Loss of Intermediate Range Nuclear Instrumentation: Effects of voltage changes on performance.
2.7 21 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 X
AK2.01 - Knowledge of the interrelations between the Fuel Handling Incidents and the following: Fuel Handling equipment.
2.9 22 000037 (APE 37) Steam Generator Tube Leak / 3 X
AK3.07 - Knowledge of the reasons for the following responses as they apply to the Steam Generator Tube Leak: Actions contained in EOP for S/G tube leak.
4.2 23 000051 (APE 51) Loss of Condenser Vacuum / 4 000059 (APE 59) Accidental Liquid Radwaste Release / 9 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 000061 (APE 61) Area Radiation Monitoring System Alarms / 7 000067 (APE 67) Plant Fire On Site / 8 X
AA1.05 - Ability to operate and/or monitor the following as they apply to the Plant Fire on Site:
Plant and control room ventilation systems.
3.0 24 000068 (APE 68; BW A06) Control Room Evacuation / 8 X
AA2.07 - Ability to determine and interpret the following as they apply to the Control Room Evacuation: PZR level.
4.1 25 000069 (APE 69; W E14) Loss of Containment Integrity / 5 X 2.2.44 - 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 26 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 E01 & E02) Rediagnosis & SI Termination / 3 (W E13) Steam Generator Overpressure / 4 (W E15) Containment Flooding / 5 (W E16) High Containment Radiation /9 X
EK2.1 - Knowledge of the interrelations between the (High Containment Radiation) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
3.0 27 (BW A01) Plant Runback / 1
ES-401 5
Form ES-401-2 (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 Point Totals:
1 2
1 1
2 2
Group Point Total:
9
ES-401 6
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 003 (SF4P RCP) Reactor Coolant Pump X
K1.01 - Knowledge of the physical connections and/or cause-effect relationships between the RCPS and the following systems:
2.6 28 003 (SF4P RCP) Reactor Coolant Pump X
A4.05 - Ability to manually operate and/or monitor in the control room: Seal leakage detection instrumentation 3.1 29 004 (SF1; SF2 CVCS) Chemical and Volume Control X
K4.12 - Knowledge of CVCS design feature(s) and/or interlock(s) which provide for the following: Minimum level of VCT.
3.1 30 005 (SF4P RHR) Residual Heat Removal X
K5.05 - Knowledge of the operational implications of the following concepts as they apply the RHRS: Plant response during "solid plant": pressure change due to the relative incompressibility of water.
2.7 31 006 (SF2; SF3 ECCS) Emergency Core Cooling X
K4.09 - Knowledge of ECCS design feature(s) and/or interlock(s) which provide for the following: Valve positioning on safety injection signal.
3.9 32 007 (SF5 PRTS) Pressurizer Relief/Quench Tank X
K1.01 - Knowledge of the physical connections and/or cause-effect relationships between the PRTS and the following systems:
Containment system.
2.9 33 008 (SF8 CCW) Component Cooling Water X
K3.01 - Knowledge of the effect that a loss or malfunction of the CCWS will have on the following: Loads cooled by CCWS.
3.4 34 008 (SF8 CCW) Component Cooling Water X
2.4.21 - Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.
4.0 35 010 (SF3 PZR PCS) Pressurizer Pressure Control X
A3.01 - Ability to monitor automatic operation of the PZR PCS, including: PRT temperature and pressure during PORV testing.
3.0 36 010 (SF3 PZR PCS) Pressurizer Pressure Control X
K5.01 - Knowledge of the operational implications of the following concepts as they apply to the PZR PCS: Determination of condition of fluid in PZR, using steam tables.
3.5 37 012 (SF7 RPS) Reactor Protection X
A4.06 - Ability to manually operate and/or monitor in the control room: Reactor trip breakers.
4.3 38 012 (SF7 RPS) Reactor Protection X
K1.02 - Knowledge of the physical connections and/or cause-effect relationships between the RPS and the following systems:
125VDC system.
3.4 39 013 (SF2 ESFAS) Engineered Safety Features Actuation X
K6.01 - Knowledge of the effect of a loss or malfunction on the following will have on the ESFAS: Sensors and detectors 2.7 40 022 (SF5 CCS) Containment Cooling X
A2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of service water.
2.9 41 025 (SF5 ICE) Ice Condenser 026 (SF5 CSS) Containment Spray X
A1.01 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: Containment pressure.
3.9 42 039 (SF4S MSS) Main and Reheat Steam X
A1.10 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MRSS controls including: Air ejector PRM.
2.9*
43
ES-401 7
Form ES-401-2 039 (SF4S MSS) Main and Reheat Steam X
A3.02 - Ability to monitor automatic operation of the MRSS, including: Isolation of the MRSS.
3.1 44 059 (SF4S MFW) Main Feedwater X
A2.05 - Ability to (a) predict the impacts of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Rupture in MFW suction or discharge line.
3.1 45 061 (SF4S AFW)
Auxiliary/Emergency Feedwater X
K2.02 - Knowledge of bus power supplies to the following: AFW electric drive pumps.
3.7 46 062 (SF6 ED AC) AC Electrical Distribution X
A1.03 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the AC distribution system controls including: Effect on instrumentation and controls of switching power supplies.
2.5 47 063 (SF6 ED DC) DC Electrical Distribution X
A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the DC electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Grounds.
2.5 48 064 (SF6 EDG) Emergency Diesel Generator X
K6.07 - Knowledge of the effect of a loss or malfunction of the following will have on the EDG system: Air receivers.
2.7 49 073 (SF7 PRM) Process Radiation Monitoring X
K4.01 - Knowledge of PRM system design feature(s) and/or interlock(s) which provide for the following: Release termination when radiation exceeds setpoint.
4.0 50 073 (SF7 PRM) Process Radiation Monitoring X
2.4.47 - Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
4.2 51 076 (SF4S SW) Service Water X
K2.08 - Knowledge of bus power supplies to the following: ESF-actuated MOVs.
3.1 52 076 (SF4S SW) Service Water X
A3.02 - Ability to monitor automatic operation of the SWS, including: Emergency heat loads.
3.7 53 078 (SF8 IAS) Instrument Air X
K3.03 - Knowledge of the effect that a loss or malfunction of the IAS will have on the following: Cross-tied units.
3.0 54 103 (SF5 CNT) Containment X
K3.03 - Knowledge of the effect that a loss or malfunction of the containment system will have on the following: Loss of containment integrity under refueling operations.
3.7 55 053 (SF1; SF4P ICS*) Integrated Control K/A Category Point Totals:
3 2
3 3
2 2
3 3
3 2
2 Group Point Total:
28
ES-401 8
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 001 (SF1 CRDS) Control Rod Drive X
K2.02 - Knowledge of bus power supplies to the following: One-line diagram of power supply to trip breakers.
3.6 56 002 (SF2; SF4P RCS) Reactor Coolant 011 (SF2 PZR LCS) Pressurizer Level Control X
K4.06 - Knowledge of PZR LCS design feature(s) and/or interlock(s) which provide for the following: letdown isolation.
3.3 57 014 (SF1 RPI) Rod Position Indication 015 (SF7 NI) Nuclear Instrumentation X
K6.04 - Knowledge of the effect of a loss or malfunction on the following will have on the NIS: Bistables and logic circuits.
3.1 58 016 (SF7 NNI) Nonnuclear Instrumentation X
A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the NNIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Detector failure.
3.0 59 017 (SF7 ITM) In-Core Temperature Monitor 027 (SF5 CIRS) Containment Iodine Removal 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control 029 (SF8 CPS) Containment Purge 033 (SF8 SFPCS) Spent Fuel Pool Cooling 034 (SF8 FHS) Fuel-Handling Equipment X
A4.02 - Ability to manually operate and/or monitor in the control room: Neutrons levels.
3.5 60 035 (SF 4P SG) Steam Generator 041 (SF4S SDS) Steam Dump/Turbine Bypass Control X 2.1.7 - Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
4.4 61 045 (SF 4S MTG) Main Turbine Generator X
A3.07 - Ability to monitor automatic operation of the MT/G system including: Turbine stop/governor valve closure on turbine trip.
3.5 62 055 (SF4S CARS) Condenser Air Removal 056 (SF4S CDS) Condensate 068 (SF9 LRS) Liquid Radwaste 071 (SF9 WGS) Waste Gas Disposal X
A1.06 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Waste Gas Disposal System operating the controls including: Ventilation system.
2.5 63 072 (SF7 ARM) Area Radiation Monitoring X
K5.01 - Knowledge of the operational implications of the following concepts as they apply to the ARM system: Radiation theory, including sources, types, units, and effects.
2.7 64 075 (SF8 CW) Circulating Water X
K3.07 - Knowledge of the effect that a loss or malfunction of the circulating water system will have on the following: ESFAS.
3.4* 65 079 (SF8 SAS**) Station Air 086 Fire Protection 050 (SF 9 CRV*) Control Room Ventilation K/A Category Point Totals:
0 1
1 1
1 1
1 1
1 1
1 Group Point Total:
10
ES-401 9
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 000007 (EPE 7; BW E02&E10; CE E02)
Reactor Trip, Stabilization, Recovery / 1 X
2.1.30 - Ability to locate and operate components, including local controls.
4.0 76 000008 (APE 8) Pressurizer Vapor Space Accident / 3 000009 (EPE 9) Small Break LOCA / 3 000011 (EPE 11) Large Break LOCA / 3 000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 000022 (APE 22) Loss of Reactor Coolant Makeup / 2 X
AA2.01 - Ability to determine or interpret the following as they apply to the Loss of Reactor Coolant Makeup: Whether charging line leak exists.
3.8 77 000025 (APE 25) Loss of Residual Heat Removal System / 4 000026 (APE 26) Loss of Component Cooling Water / 8 000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 000029 (EPE 29) Anticipated Transient Without Scram / 1 000038 (EPE 38) Steam Generator Tube Rupture / 3 X
2.4.4 - Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
4.7 78 000040 (APE 40; BW E05; CE E05; W E12)
Steam Line RuptureExcessive Heat Transfer / 4 000054 (APE 54; CE E06) Loss of Main Feedwater /4 000055 (EPE 55) Station Blackout / 6 000056 (APE 56) Loss of Offsite Power / 6 X
AA2.44 - Ability to determine or interpret the following as they apply to the Loss of Offsite Power:
Indications of loss of offsite power.
4.5 79 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 000058 (APE 58) Loss of DC Power / 6 000062 (APE 62) Loss of Nuclear Service Water / 4 000065 (APE 65) Loss of Instrument Air / 8 X
2.1.31 - Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.
4.3 80 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 (W E04) LOCA Outside Containment / 3 (W E11) Loss of Emergency Coolant Recirculation / 4 X
EA2.1 - Ability to determine and interpret the following as they apply to the (Loss of Emergency Coolant Recirculation): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
4.2 81 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 K/A Category Totals:
3 3
Group Point Total:
6
ES-401 10 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 000001 (APE 1) Continuous Rod Withdrawal / 1 000003 (APE 3) Dropped Control Rod / 1 000005 (APE 5) Inoperable/Stuck Control Rod / 1 000024 (APE 24) Emergency Boration / 1 X 2.1.27 - Knowledge of system purpose and/or function.
4.0 82 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 000037 (APE 37) Steam Generator Tube Leak / 3 000051 (APE 51) Loss of Condenser Vacuum / 4 000059 (APE 59) Accidental Liquid Radwaste Release / 9 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 X 2.4.30 - 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.
4.1 83 000061 (APE 61) Area Radiation Monitoring System Alarms / 7 000067 (APE 67) Plant Fire On Site / 8 000068 (APE 68; BW A06) Control Room Evacuation / 8 000069 (APE 69; W E14) Loss of Containment Integrity / 5 000074 (EPE 74; W E06 & E07)
Inadequate Core Cooling / 4 X
EA2.1 - Ability to determine and interpret the following as they apply to the (Saturated Core Cooling): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
4.0 84 000076 (APE 76) High Reactor Coolant Activity / 9 000078 (APE 78*) RCS Leak / 3 (W E01 & E02) Rediagnosis & SI Termination / 3 (W E13) Steam Generator Overpressure / 4 (W E15) Containment Flooding / 5 X
EA2.2 - Ability to determine or interpret the following as they apply to the (Containment Flooding): Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments.
3.3 85 (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
ES-401 11 Form ES-401-2 (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 Point Totals:
2 2
Group Point Total:
4
ES-401 12 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 003 (SF4P RCP) Reactor Coolant Pump 004 (SF1; SF2 CVCS) Chemical and Volume Control X
A2.10 - Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Inadvertent boration/dilution.
4.2 86 005 (SF4P RHR) Residual Heat Removal X
2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation.
4.4 87 006 (SF2; SF3 ECCS) Emergency Core Cooling 007 (SF5 PRTS) Pressurizer Relief/Quench Tank 008 (SF8 CCW) Component Cooling Water 010 (SF3 PZR PCS) Pressurizer Pressure Control 012 (SF7 RPS) Reactor Protection 013 (SF2 ESFAS) Engineered Safety Features Actuation 022 (SF5 CCS) Containment Cooling 025 (SF5 ICE) Ice Condenser 026 (SF5 CSS) Containment Spray X
A2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of spray pump 4.2 88 039 (SF4S MSS) Main and Reheat Steam 059 (SF4S MFW) Main Feedwater 061 (SF4S AFW)
Auxiliary/Emergency Feedwater 062 (SF6 ED AC) AC Electrical Distribution X
A2.06 - Ability to (a) predict the impacts of the following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Keeping the safeguards buses electrically separate.
3.9 89 063 (SF6 ED DC) DC Electrical Distribution X
2.4.49 - Ability to perform without reference to procedures those actions that require immediate operation of system components and controls.
4.4 90 064 (SF6 EDG) Emergency Diesel Generator 073 (SF7 PRM) Process Radiation Monitoring 076 (SF4S SW) Service Water 078 (SF8 IAS) Instrument Air 103 (SF5 CNT) Containment
ES-401 13 Form ES-401-2 053 (SF1; SF4P ICS*) Integrated Control K/A Category Point Totals:
3 2
Group Point Total:
5
ES-401 14 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 001 (SF1 CRDS) Control Rod Drive 002 (SF2; SF4P RCS) Reactor Coolant 011 (SF2 PZR LCS) Pressurizer Level Control 014 (SF1 RPI) Rod Position Indication 015 (SF7 NI) Nuclear Instrumentation 016 (SF7 NNI) Nonnuclear Instrumentation 017 (SF7 ITM) In-Core Temperature Monitor 027 (SF5 CIRS) Containment Iodine Removal 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control 029 (SF8 CPS) Containment Purge X
A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Maintenance or other activity taking place inside containment.
3.6 91 033 (SF8 SFPCS) Spent Fuel Pool Cooling X 2.4.41 - Knowledge of the emergency action level thresholds and classifications.
4.6 92 034 (SF8 FHS) Fuel-Handling Equipment 035 (SF 4P SG) Steam Generator 041 (SF4S SDS) Steam Dump/Turbine Bypass Control 045 (SF 4S MTG) Main Turbine Generator 055 (SF4S CARS) Condenser Air Removal 056 (SF4S CDS) Condensate X
A2.05 - Ability to (a) predict the impacts of the following malfunctions or operations on the Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Condenser tube leakage.
2.5 93 068 (SF9 LRS) Liquid Radwaste 071 (SF9 WGS) Waste Gas Disposal 072 (SF7 ARM) Area Radiation Monitoring 075 (SF8 CW) Circulating Water 079 (SF8 SAS**) Station Air 086 Fire Protection 050 (SF 9 CRV*) Control Room Ventilation K/A Category Point Totals:
2 1 Group Point Total:
3
ES-401 Generic Knowledge and Abilities Outline (Tier 3)
Form ES-401-3 Facility: POINT BEACH NUCLEAR PLANT UNITS 1 and 2 Date of Exam: JULY 15 - JULY 26, 2019 Category K/A #
Topic RO SRO-only IR IR
- 1. Conduct of Operations 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.
3.9 94 2.1.18 Ability to make accurate, clear, and concise logs, records, status boards, and reports.
3.6 66 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.
3.9 67 2.1.43 Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc.
4.1 68 2.1.45 Ability to identify and interpret diverse indications to validate the response of another indication.
4.3 95 Subtotal 3
2
- 2. Equipment Control 2.2.14 Knowledge of the process for controlling equipment configuration or status.
3.9 69 2.2.22 Knowledge of limiting conditions for operations and safety limits.
4.7 96 2.2.42 Ability to recognize system parameters that are entry-level conditions for Technical Specifications.
3.9 70 Subtotal 2
1
- 3. Radiation Control 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.
3.2 71 2.3.12 Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
3.2 72 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
3.8 97 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
3.4 73 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.
3.1 98 Subtotal 3
2
- 4. Emergency Procedures/Plan 2.4.3 Ability to identify post-accident instrumentation.
3.7 74 2.4.9 Knowledge of low power /shutdown implications in accident (e.g.
LOCA or loss of RHR) mitigation strategies.
4.2 99 2.4.20 Knowledge of operational implications of EOP warnings, cautions, and notes.
4.3 100 2.4.46 Ability to verify that the alarms are consistent with the plant conditions.
4.2 75 Subtotal 2
2 Tier 3 Point Total 10 7