ML17201Q545

2017 Point Beach Nuclear Plant Initial License Examination Forms ES-401-2 and ES-401-3 Revision 1

ML17201Q545
Person / Time
Site:	Point Beach
Issue date:	05/23/2017
From:	Jesse Seymour Operations Branch III
To:	Point Beach
Shared Package
ML16319A342	List: ML17201Q516 ML17201Q527 ML17201Q528 ML17201Q529 ML17201Q531 ML17201Q533 ML17201Q544 ML17201Q545 ML17201Q546 ML17201Q548
References
Download: ML17201Q545 (10)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Point Beach Date of Exam: May 2017 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G* A2 G* Total 1 2 3 4 5 6 1 2 3 4 Total

1. 1 3 3 3 3 3 3 18 3 3 6 Emergency &

Abnormal 2 2 1 1 N/A 1 2 N/A 2 9 2 2 4 Plant Evolutions Tier Totals 5 4 4 4 5 5 27 5 5 10 1 3 3 3 3 3 2 2 2 2 2 3 28 3 2 5 2.

Plant 2 1 0 1 1 1 1 1 1 1 1 1 10 0 1 2 3 Systems Tier Totals 4 3 4 4 4 3 3 3 3 3 4 38 4 4 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 Categories 10 7 2 3 3 2 2 2 1 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 outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 Radiation Control K/A is allowed if the K/A 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 associated 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 importance ratings (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

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)

K K K A A E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 0 EK2.03-Knowledge of the interrelations between a reactor trip and the following:

000007 Reactor Trip - Stabilization - Recovery / 1 3.5 1 3 Reactor trip status panel 0 AK2.03-Knowledge of the interrelations between the Pressurizer Vapor Space 000008 Pressurizer Vapor Space Accident / 3 2.5 2 3 Accident and the following: Controllers and positioners 2 EK3.28-Knowledge of the reasons for the following responses as the apply to the 000009 Small Break LOCA / 3 4.5 3 8 small break LOCA: Manual ESFAS initiation requirements 0 EK3.06-Knowledge of the reasons for the following responses as the apply to 000011 Large Break LOCA / 3 4.3 4 6 the Large Break LOCA: Actuation of Phase A and B during LOCA initiation 000015 RCP Malfunctions / 4 2 AA1.22-Ability to operate and / or monitor the following as they apply to the Reactor 4.0 5 000017 RCP Malfunctions (Loss of RC Flow) / 4 2 Coolant Pump Malfunctions (Loss of RC Flow): RCP seal failure/malfunction 0 AA1.02-Ability to operate and / or monitor the following as they apply to the Loss of 000022 Loss of Rx Coolant Makeup / 2 3.0 6 2 Reactor Coolant Makeup: CVCS charging low flow alarm, sensor, and indicator AA2.05-Ability to determine and interpret the following as they apply to the Loss of 0

000025 Loss of RHR System / 4 Residual Heat Removal System: Limitations on LPI flow and temperature rates of 3.1 7 5 change 000026 Loss of Component Cooling Water / 8 000027 Pressurizer Pressure Control System 02.

2.2.12-Knowledge of surveillance procedures. 3.7 8 Malfunction / 3 12 000029 ATWS / 1 0 EK1.01-Knowledge of the operational implications of the following concepts as they 000038 Steam Gen. Tube Rupture / 3 3.1 9 1 apply to the SGTR: Use of steam tables 000040 Steam Line Rupture - Excessive Heat Transfer 0 AK2.01-Knowledge of the interrelations between the Steam Line Rupture and the 2.6 10

/4 1 following: Valves WE12 Uncontrolled Depressurization of all Steam Generators / 4 000054 (CE/E06) Loss of Main Feedwater / 4 000055 Station Blackout / 6 0 AK3.02-Knowledge of the reasons for the following responses as they apply to the 000056 Loss of Off-site Power / 6 4.4 11 2 Loss of Offsite Power: Actions contained in EOP for loss of offsite power 000057 Loss of Vital AC Inst. Bus / 6 0 AA1.01-Ability to operate and / or monitor the following as they apply to the Loss of 000058 Loss of DC Power / 6 3.4 12 1 DC Power: Cross-tie of the affected dc bus with the alternate supply AA2.04-Ability to determine and interpret the following as they apply to the Loss of 0

000062 Loss of Nuclear Svc Water / 4 Nuclear Service Water: The normal values and upper limits for the temperatures of 2.5 13 4 the components cooled by SWS AA2.05-Ability to determine and interpret the following as they apply to the Loss of 0

000065 Loss of Instrument Air / 8 Instrument Air: When to commence plant shutdown if instrument air pressure is 3.4 14 5 decreasing

01. 2.1.31-Ability to locate control room switches, controls, and indications, and to W/E04 LOCA Outside Containment / 3 4.6 15 31 determine that they correctly reflect the desired plant lineup.

04.

W/E11 Loss of Emergency Coolant Recirc. / 4 2.4.46-Ability to verify that the alarms are consistent with the plant conditions. 4.2 16 46 EK1.01-Knowledge of the operational implications of the following concepts as they BW/E04; W/E05 Inadequate Heat Transfer - Loss of 0 apply to the (Loss of Secondary Heat Sink): Components, capacity, and function of 3.8 17 Secondary Heat Sink / 4 1 emergency systems 000077 Generator Voltage and Electric 0 AK1.02-Knowledge of the operational implications of the following concepts as they 3.3 18 Grid Disturbances / 6 2 apply to Generator Voltage and Electric Grid Disturbances: Over-excitation K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 ES-401, 39 of 50

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)

K K K A A E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 01.

000003 Dropped Control Rod / 1 2.1.27-Knowledge of system purpose and/or function. 3.9 19 27 000005 Inoperable/Stuck Control Rod / 1 AK1.01-Knowledge of the operational implications of the following concepts as they 000024 Emergency Boration / 1 01 apply to Emergency Boration: Relationship between boron addition and change in T- 3.4 20 ave 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 000036 Fuel Handling Accident / 8 000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 AA2.01-Ability to determine and interpret the following as they apply to the Area 000061 ARM System Alarms / 7 01 Radiation Monitoring (ARM) System Alarms: ARM panel displays 3.5 21 000067 Plant Fire On-site / 8 04.

000068 Control Room Evac. / 8 2.4.18-Knowledge of the specific bases for EOPs. 3.3 22 18 000069 Loss of CTMT Integrity / 5 W/E14 High Containment Pressure / 5 EK1.08-Knowledge of the operational implications of the following concepts as they 000074 Inad. Core Cooling / 4 08 apply to the Inadequate Core Cooling: Definition of subcooled liquid 2.8 23 W/E06 Degraded Core Cooling / 4 W/E07 Saturated Core Cooling / 4 000076 High Reactor Coolant Activity / 9 EK2.01-Knowledge of the interrelations between the (Reactor Trip or Safety Injection/Rediagnosis) and the following:Components, and functions of control and W/E01 Rediagnosis / 3 01 safety systems, including instrumentation, signals, interlocks, failure modes, and 3.3 24 automatic and manual features W/E02 SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 EK3.04-Knowledge of the reasons for the following responses as they apply to the (Containment Flooding): RO or SRO function within the control room team as W/E15 Containment Flooding / 5 04 appropriate to the assigned position, in such a way that procedures are adhered to 2.9 25 and the limitations in the facilities license and amendments are not violated W/E16 High Containment Radiation / 9 EA1.03-Ability to operate and / or monitor the following as they apply to the (LOCA W/E03 LOCA Cooldown - Depress. / 4 03 Cooldown and Depressurization): Desired operating results during abnormal and 3.7 26 emergency situations W/E09 Natural Circulation Operations / 4 W/E10 Natural Circulation with Steam Voide in Vessel with/without RVLIS. / 4 EA2.02-Ability to determine and interpret the following as they apply to the W/E08 RCS Overcooling - PTS / 4 02 (Pressurized Thermal Shock): Adherence to appropriate procedures and operation 3.5 27 within the limitations in the facility's license and amendments K/A Category Totals: 2 1 1 1 2 2 Group Point Total: 9 ES-401, 40 of 50

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)

K K K K K K A A A A System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 K6.14-Knowledge of the effect of a loss or malfunction on the following will 0 2.6 28 003 Reactor Coolant Pump 14 have on the RCPS: Starting requirements 3 A3.03-Ability to monitor automatic operation of the RCPS, including: Seal D/P 3.2 29 04.

004 Chemical and Volume Control 2.4.31-Knowledge of annunciator alarms, indications, or response procedures. 4.2 30 31 0 A4.01-Ability to manually operate and/or monitor in the control room: Controls 005 Residual Heat Removal and indication for RHR pumps 3.6 31 1

K3.02-Knowledge of the effect that a loss or malfunction of the ECCS will 0 02. have on the following: Fuel 4.3 32 006 Emergency Core Cooling 2.2.36-Ability to analyze the effect of maintenance activities, such as 2 36 3.1 33 degraded power sources, on the status of limiting conditions for operations.

04. 2.4.20-Knowledge of the operational implications of EOP warnings, cautions, 007 Pressurizer Relief/Quench Tank and notes.

3.8 34 20 K1.04-Knowledge of the physical connections and/or cause-effect relationships between the CCWS and the following systems: RCS, in order to 0 0 3.3 35 008 Component Cooling Water determine source(s) of RCS leakage into the CCWS 4 1 K4.01-Knowledge of CCWS design feature(s) and/or interlock(s) which 3.1 36 provide for the following: Automatic start of standby pump 0 K1.06-Knowledge of the physical connections and/or cause-effect 010 Pressurizer Pressure Control relationships between the PZR PCS and the following systems: CVCS 2.9 37 6

K2.01-Knowledge of bus power supplies to the following: RPS channels, 0 0 components, and interconnections 3.3 38 012 Reactor Protection K5.01-Knowledge of the operational implications of the following concepts as 1 1 3.3 39 the apply to the RPS: DNB K2.01-Knowledge of bus power supplies to the following: ESFAS/safeguards 013 Engineered Safety Features 0 0 equipment control 3.6 40 A1.01-Ability to predict and/or monitor changes in parameters (to Prevent Actuation 1 1 exceeding design limits) associated with operating the ESFAS controls 4.0 41 including: RCS pressure and temperature K3.01-Knowledge of the effect that a loss or malfunction of the CCS will have 0

022 Containment Cooling on the following: Containment equipment subject to damage by high or low 2.9 42 1 temperature, humidity, and pressure 025 Ice Condenser 0 K3.02-Knowledge of the effect that a loss or malfunction of the CSS will have 026 Containment Spray on the following: Recirculation spray system 4.2 43 2

K4.04-Knowledge of MRSS design feature(s) and/or interlock(s) which provide 0

039 Main and Reheat Steam for the following: Utilization of steam pressure program control when steam 2.9 44 4 dumping through atmospheric relief/dump valves, including T-ave. limits 1 K4.16-Knowledge of MFW design feature(s) and/or interlock(s) which provide 059 Main Feedwater for the following: Automatic trips for MFW pumps 3.1 45 6

0 K5.01-Knowledge of the operational implications of the following concepts as 061 Auxiliary/Emergency Feedwater the apply to the AFW: Relationship between AFW flow and RCS heat transfer 3.6 46 1

A1.03-Ability to predict and/or monitor changes in parameters (to prevent 0 exceeding design limits) associated with operating the ac distribution system 062 AC Electrical Distribution controls including: Effect on instrumentation and controls of switching power 2.5 47 3

supplies K1.02-Knowledge of the physical connections and/or cause-effect 0

063 DC Electrical Distribution relationships between the DC electrical system and the following systems: AC 2.7 48 2 electrical system K6.07-Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: Air receivers 0 1 A2.13-Ability to (a) predict the impacts of the following malfunctions or 2.7 49 064 Emergency Diesel Generator operations on the ED/G system; and (b) based on those predictions, use 7 3 procedures to correct, control, or mitigate the consequences of those 2.6 50 malfunctions or operations: Consequences of opening auxiliary feeder bus (ED/G sub supply)

K5.02-Knowledge of the operational implications as they apply to concepts as 0

073 Process Radiation Monitoring they apply to the PRM system: Radiation intensity changes with source 2.5 51 2 distance 0 A3.02-Ability to monitor automatic operation of the SWS, including:

076 Service Water Emergency heat loads 3.7 52 2

0 K2.01-Knowledge of bus power supplies to the following: Instrument air 078 Instrument Air compressor 2.7 53 1

A2.04-Ability to (a) predict the impacts of the following malfunctions or operations on the containment system and (b) based on those predictions, 0 0 use procedures to correct, control, or mitigate the consequences of those 3.5 54 103 Containment malfunctions or operations Containment evacuation (including recognition of 4 6 the alarm) 2.7 55 A4.06-Ability to manually operate and/or monitor in the control room:

Operation of the containment personnel airlock door K/A Category Totals: 3 3 3 3 3 2 2 2 2 2 3 Group Point Total: 28 ES-401, Page 41 of 50

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO)

K K K K K K A A A A System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 0 A3.07-Ability to monitor automatic operation of the CRDS, including:

001 Control Rod Drive 4.1 56 7 Boration/dilution 002 Reactor Coolant 0 K6.03-Knowledge of the effect of a loss or malfunction on the following will have 011 Pressurizer Level Control 2.9 57 3 on the PZR LCS: Relationship between PZR level and PZR heater control circuit 014 Rod Position Indication 0 K4.07-Knowledge of NIS design feature(s) and/or interlock(s) provide for the 015 Nuclear Instrumentation 3.7 58 7 following: Permissives 016 Non-nuclear Instrumentation 0 A4.01-Ability to manually operate and/or monitor in the control room: Actual in-017 In-core Temperature Monitor 3.8 59 1 core temperatures 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 01.

033 Spent Fuel Pool Cooling 2.1.32-Ability to explain and apply system limits and precautions. 3.8 60 32 034 Fuel Handling Equipment 035 Steam Generator 0 K5.05-Knowledge of the operational implications of the following concepts as 041 Steam Dump/Turbine Bypass Control 2.6 61 5 they apply to the SDS: Basis for RCS design pressure limits 045 Main Turbine Generator 0 K3.01-Knowledge of the effect that a loss or malfunction of the CARS will have 055 Condenser Air Removal 2.5 62 1 on the following: Main condenser 056 Condensate A2.04-Ability to (a) predict the impacts of the following malfunctions or operations 0 on the Liquid Radwaste System ; and (b) based on those predictions, use 068 Liquid Radwaste 3.3 63 4 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of automatic isolation 071 Waste Gas Disposal A1.01-Ability to predict and/or monitor changes in parameters (to prevent 0

072 Area Radiation Monitoring exceeding design limits) associated with operating the ARM system controls 3.4 64 1

including: Radiation levels 075 Circulating Water 0 K1.01-Knowledge of the physical connections and/or cause-effect relationships 079 Station Air 3.0 65 1 between the SAS and the following systems: IAS 086 Fire Protection K/A Category Totals: 1 0 1 1 1 1 1 1 1 1 1 Group Point Total: 10 ES-401, Page 42 of 50

ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)

K K K A A E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 000007 Reactor Trip - Stabilization - Recovery / 1 000008 Pressurizer Vapor Space Accident / 3 000009 Small Break LOCA / 3 000011 Large Break LOCA / 3 000015 RCP Malfunctions / 4 000017 RCP Malfunctions (Loss of RC Flow) / 4 0 AA2.03-Ability to determine and interpret the following as they apply to the Loss of 000022 Loss of Rx Coolant Makeup / 2 3.6 76 3 Reactor Coolant Makeup: Failures of flow control valve or controller 000025 Loss of RHR System / 4

04. 2.4.8-Knowledge of how abnormal operating procedures are used in conjunction with 000026 Loss of Component Cooling Water / 8 4.5 77 08 EOPs.

000027 Pressurizer Pressure Control System Malfunction / 3 0 EA2.09-Ability to determine or interpret the following as they apply to a ATWS:

000029 ATWS / 1 4.5 78 9 Occurrence of a main turbine/reactor trip 000038 Steam Gen. Tube Rupture / 3 000040 Steam Line Rupture - Excessive Heat Transfer

/4 WE12 Uncontrolled Depressurization of all Steam Generators / 4

04. 2.4.4-Ability to recognize abnormal indications for system operating parameters that 000054 (CE/E06) Loss of Main Feedwater / 4 4.7 79 04 are entry-level conditions for emergency and abnormal operating proedures.

02.

000055 Station Blackout / 6 2.2.37-Ability to determine operability and/or availability of safety related equipment. 4.6 80 37 000056 Loss of Off-site Power / 6 000057 Loss of Vital AC Inst. Bus / 6 000058 Loss of DC Power / 6 000062 Loss of Nuclear Svc Water / 4 000065 Loss of Instrument Air / 8 W/E04 LOCA Outside Containment / 3 W/E11 Loss of Emergency Coolant Recirc. / 4 EA2.02-Ability to determine and interpret the following as they apply to the (Loss of BW/E04; W/E05 Inadequate Heat Transfer - Loss of 0 Secondary Heat Sink): Adherence to appropriate procedures and operation within the 4.3 81 Secondary Heat Sink / 4 2 limitations in the facility's license and amendments 000077 Generator Voltage and Electric Grid Disturbances / 6 K/A Category Totals: 0 0 0 0 3 3 Group Point Total: 6 ES-401, 39 of 50

ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)

K K K A A E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod / 1 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 AA2.07-Ability to determine and interpret the following as they apply to the Loss of 000032 Loss of Source Range NI / 7 07 Source Range Nuclear Instrumentation: Maximum allowable channel disagreement 3.4 82 000033 Loss of Intermediate Range NI / 7 000036 Fuel Handling Accident / 8 000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid RadWaste Rel. / 9

01. 2.1.28-Knowledge of the purpose and function of major system components and 000060 Accidental Gaseous Radwaste Rel. / 9 controls.

4.1 83 28 000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8 000068 Control Room Evac. / 8 000069 Loss of CTMT Integrity / 5 W/E14 High Containment Pressure / 5 000074 Inad. Core Cooling / 4 W/E06 Degraded Core Cooling / 4 W/E07 Saturated Core Cooling / 4 AA2.04-Ability to determine and interpret the following as they apply to the High 000076 High Reactor Coolant Activity / 9 04 Reactor Coolant Activity: Process effluent radiation chart recorder 3.0 84 W/E01 Rediagnosis / 3 W/E02 SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5 W/E16 High Containment Radiation / 9 W/E03 LOCA Cooldown - Depress. / 4 W/E09 Natural Circulation Operations / 4 W/E10 Natural Circulation with Steam Voide in 04. 2.4.50-Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.

4.0 85 Vessel with/without RVLIS. / 4 50 W/E08 RCS Overcooling - PTS / 4 K/A Category Totals: 0 0 0 0 2 2 Group Point Total: 4 ES-401, 40 of 50

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO)

K K K K K K A A A A System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump A2.28-Ability to (a) predict the impacts of the following malfunctions or 2 operations on the CVCS; and (b) based on those predictions, use procedures 004 Chemical and Volume Control to correct, control, or mitigate the consequences of those malfunctions or 4.3 86 8

operations: Depressurizing of RCS while it is hot 005 Residual Heat Removal 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water A2.02-Ability to (a) predict the impacts of the following malfunctions or 0 operations on the PZR PCS; and (b) based on those predictions, use 010 Pressurizer Pressure Control procedures to correct, control, or mitigate the consequences of those 3.9 87 2

malfunctions or operations: Spray valve failures 012 Reactor Protection 013 Engineered Safety Features Actuation 022 Containment Cooling 025 Ice Condenser 026 Containment Spray A2.04-Ability to (a) predict the impacts of the following malfunctions or 0 operations on the MRSS; and (b) based on predictions, use procedures to 039 Main and Reheat Steam correct, control, or mitigate the consequences of those malfunctions or 3.7 88 4

operations: Malfunctioning steam dump 059 Main Feedwater 061 Auxiliary/Emergency Feedwater 2.2.44-Ability to interpret control room indications to verify the status and 02.

062 AC Electrical Distribution operation of a system, and understand how operator actions and directives 4.4 89 44 affect plant and system conditions.

063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Monitoring 2.4.21-Knowledge of the parameters and logic used to assess the status of

04. safety functions, such as reactivity control, core cooling and heat removal, 076 Service Water reactor coolant system integrity, containment conditions, radioactivity release 4.6 90 21 control, etc.

078 Instrument Air 103 Containment K/A Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 ES-401, Page 41 of 50

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (SRO)

K K K K K K A A A A System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive 002 Reactor Coolant 011 Pressurizer Level Control 014 Rod Position Indication 015 Nuclear Instrumentation

02. 2.2.42-Ability to recognize system parameters that are entry-level conditions for 016 Non-nuclear Instrumentation 4.6 91 42 Technical Specifications.

017 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 04.

035 Steam Generator 2.4.41-Knowledge of the emergency action level thresholds and classifications. 4.6 92 41 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal A2.03-Ability to (a) predict the impacts of the following malfunctions or operations 0 on the ARM system- and (b) based on those predictions, use procedures to 072 Area Radiation Monitoring 3 correct, control, or mitigate the consequences of those malfunctions or 2.9 93 operations: Blown power-supply fuses 075 Circulating Water 079 Station Air 086 Fire Protection K/A Category Totals: 0 0 0 0 0 0 0 1 0 0 2 Group Point Total: 3 ES-401, Page 42 of 50

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility Name: Point Beach Date of Exam: May 2017 RO SRO-Only Category K/A # Topic IR # IR #

66 2.1.14-Knowledge of criteria or conditions that require plant-wide announcements, such as pump 2.1. 14 starts, reactor trips, mode changes, etc. 3.1 67 2.1.38-Knowledge of the station's requirements for verbal communications when implementing 2.1. 38 procedures. 3.7

1. 2.1.

Conduct of Operations 2.1.

2.1. 02 2.1.2-Knowledge of operator responsibilities during all modes of plant operation. 4.4 94 2.1. 06 2.1.6-Ability to manage the control room crew during plant transients. 4.8 95 Subtotal 2 2 2.2. 03 2.2.3-Knowledge of the design, procedural, and operational differences between units. 3.8 68 2.2. 14 2.2.14-Knowledge of the process for controlling equipment configuration or status. 3.9 69 70 2.2.15-Ability to determine the expected plant configuration using design and configuration control 2.2. 15 documentation, such as drawings, line-ups, tag-outs, etc. 3.9 2.

Equipment 2.2.

Control 2.2. 07 2.2.7-Knowledge of the process for conducting special or infrequent tests. 3.6 96 2.2. 21 2.2.21-Knowledge of pre- and post-maintenance operability requirements. 4.1 97 Subtotal 3 2 2.3. 07 2.3.7-Ability to comply with radiation work permit requirements during normal or abnormal conditions. 3.5 71 2.3. 11 2.3.11-Ability to control radiation releases. 3.8 72 73 2.3.15-Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3. 15 portable survey instruments, personnel monitoring equipment, etc. 2.9 3.

Radiation 2.3.

Control 2.3.

2.3.13-Knowledge of radiological safety procedures pertaining to licensed operator duties, such as 2.3. 13 response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, 3.8 98 access to locked high-radiation areas, aligning filters, etc.

Subtotal 3 1 2.4. 14 2.4.14-Knowledge of general guidelines for EOP usage. 3.8 74 2.4. 45 2.4.45-Ability to prioritize and interpret the significance of each annunciator or alarm. 4.1 75

4. 2.4.

Emergency Procedures / 2.4.

Plan 2.4. 25 2.4.25-Knowledge of fire protection procedures. 3.7 99 2.4. 32 2.4.32-Knowledge of operator response to loss of all annunciators. 4.0 100 Subtotal 2 2 Tier 3 Point Total 10 7 ES-401, Page 43 of 50