Text

Final Written Examination and Operating Test Outlines (Folder 3)
	ML20297A306
Person / Time
Site:	Salem
Issue date:	10/23/2020
From:	; Public Service Enterprise Group
To:	; Operations Branch I
Shared Package
ML19105A168	List: ML19211C255; ML20176A296; ML20240A318; ML20240A322; ML20296A430; ML20296A432; ML20297A279; ML20297A306; ML20300A556; ML20301A632; ML21012A270;
References
	CAC 000500
	Download: ML20297A306 (39)
	v • d • e

ES-401 PWR Examination Outline Form ES-401-2 Facility: SALEM Date of Exam: JULY 2020 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 3 3 3 3 4 2 18 6 Emergency and Abnormal Plant 2 1 2 2 N/A 1 1 N/A 2 9 4 Evolutions Tier Totals 4 5 5 4 5 4 27 10 1 4 2 2 4 2 2 2 2 3 2 3 28 5 2.

Plant 2 1 1 2 2 0 1 1 1 1 0 0 10 3 Systems Tier Totals 5 3 4 6 2 3 3 3 4 2 3 38 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 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/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) X EK 2.03 - Knowledge of the interrelations between a 3.5 1 Reactor Trip, Stabilization, Recovery / 1 reactor trip and the following: Reactor trip status panel AK 2.02 - Knowledge of the interrelations between 000008 (APE 8) Pressurizer Vapor Space X the Pressurizer Vapor Space Accident and the 2.7 2 Accident / 3 following: Sensors and detectors EK 1.02 - Knowledge of the operational implications 000009 (EPE 9) Small Break LOCA / 3 X of the following concepts as they apply to the small 3.5 3 break LOCA: Use of steam tables 000011 (EPE 11) Large Break LOCA / 3 N/A - Not randomly selected AK 3.01 - Knowledge of the reasons for the 000015 (APE 15) Reactor Coolant Pump X following responses as they apply to the Reactor 2.5 4 Malfunctions / 4 Coolant Pump Malfunctions (Loss of RC Flow) :

Potential damage from high winding and/or bearing temperatures AA 1.07 - Ability to operate and / or monitor the 000022 (APE 22) Loss of Reactor Coolant X following as they apply to the Loss of Reactor 2.8 5 Makeup / 2 Coolant Makeup: Excess letdown containment isolation valve switches and indicators AA 2.04 - Ability to determine and interpret the 000025 (APE 25) Loss of Residual Heat X following as they apply to the Loss of Residual Heat 3.3 6 Removal System / 4 Removal System: Location and isolability of leaks 000026 (APE 26) Loss of Component N/A - Not randomly selected Cooling Water / 8 AK 3.03 - Knowledge of the reasons for the 000027 (APE 27) Pressurizer Pressure X following responses as they apply to the Pressurizer 3.7 7 Control System Malfunction / 3 Pressure Control Malfunctions: Actions contained in EOP for PZR PCS malfunction AK 3.12- Knowledge of the reasons for the following 000029 (EPE 29) Anticipated Transient X responses as the apply to the 4.4 8 Without Scram / 1 ATWS: Actions contained in EOP for ATWS 000038 (EPE 38) Steam Generator Tube N/A - Not randomly selected Rupture / 3 000040 (APE 40; BW E05; CE E05; W E12) X G 2.4.46 - Ability to verify that the alarms are 4.2 9 Steam Line RuptureExcessive Heat consistent with the plant conditions.

Transfer / 4 000054 (APE 54; CE E06) Loss of Main X AK 1.02 - Effects of feedwater introduction on dry 3.6 10 Feedwater /4 S/G 000055 (EPE 55) Station Blackout / 6 N/A - Not randomly selected AA 1.03 - Ability to operate and / or monitor the 000056 (APE 56) Loss of Offsite Power / 6 X following as they apply to the Loss of Offsite Power: 3.2 11 Adjustment of ED/G load by selectively energizing PZR backup heaters AA 2.13 - Ability to determine and interpret the 000057 (APE 57) Loss of Vital AC X following as they apply to the Loss of Vital AC 3.0 12 Instrument Bus / 6 Instrument Bus: VCT level and pressure indicators and recorders 000058 (APE 58) Loss of DC Power / 6 X Ability to determine and interpret the following as 3.5 13 they apply to the Loss of DC Power: DC Loads lost, impact on ability to operate and monitor plant systems 000062 (APE 62) Loss of Nuclear Service X G 2.2.40 - Ability to apply Technical Specifications 3.4 14 Water / 4 for a system AA 1.03 - Ability to operate and / or monitor the 000065 (APE 65) Loss of Instrument Air / 8 X following as they apply to the Loss of Instrument 3.5 15 Air: Emergency air compressor

ES-401 3 Form ES-401-2 000077 (APE 77) Generator Voltage and N/A - Not randomly selected Electric Grid Disturbances / 6 EK 2.1 - Knowledge of the interrelations between (W E04) LOCA Outside Containment / 3 X the (LOCA Outside Containment) and the following: 3.5 16 Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

EK 1.2 - Knowledge of the operational implications (W E11) Loss of Emergency Coolant X of the following concepts as they apply to the (Loss 3.6 17 Recirculation / 4 of Emergency Coolant Recirculation): Normal, abnormal and emergency operating procedures associated with (Loss of Emergency Coolant Recirculation)

EA 2.1 - Ability to determine and interpret the (BW E04; W E05) Inadequate Heat X following as they apply to the (Loss of Secondary 3.4 18 TransferLoss of Secondary Heat Sink / 4 Heat Sink): Facility conditions and selection of appropriate procedures during abnormal and emergency operations K/A Category Totals: 3 3 3 3 4 2 Group Point Total: 18/6

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/SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

000001 (APE 1) Continuous Rod Withdrawal / 1 N/A - Not randomly selected 000003 (APE 3) Dropped Control Rod / 1 X Knowledge of the reasons for the 3.8 19 following responses as they apply to the Dropped Control Rod:

Actions contained in EOP for dropped control rod.

000005 (APE 5) Inoperable/Stuck Control Rod / 1 X AA 1.04 - Ability to operate and / 3.9 20 or monitor the following as they apply to the Inoperable / Stuck Control Rod: Reactor and turbine power 000024 (APE 24) Emergency Boration / 1 X AK 2.01 - Knowledge of the 2.7 21 interrelations between Emergency Boration and the following: Valves 000028 (APE 28) Pressurizer (PZR) Level Control N/A - Not randomly selected Malfunction / 2 000032 (APE 32) Loss of Source Range Nuclear N/A - Not randomly selected Instrumentation / 7 000033 (APE 33) Loss of Intermediate Range Nuclear X AA 2.09 - Ability to determine and 3.4 22 Instrumentation / 7 interpret the following as they apply to the Loss of Intermediate Range Nuclear Instrumentation:

Conditions which allow bypass of an intermediate-range level trip switch.

000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 N/A - Not randomly selected 000037 (APE 37) Steam Generator Tube Leak / 3 N/A - Not randomly selected 000051 (APE 51) Loss of Condenser Vacuum / 4 N/A - Not randomly selected 000059 (APE 59) Accidental Liquid Radwaste Release / 9 N/A - Not randomly selected 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 N/A - Not randomly selected 000061 (APE 61) Area Radiation Monitoring System Alarms X AK 3.02 - Knowledge of the 3.4 23

/7 reasons for the following responses as they apply to the Area Radiation Monitoring (ARM) System Alarms: Guidance contained in alarm response for ARM system 000067 (APE 67) Plant Fire On Site / 8 N/A - Not randomly selected 000068 (APE 68; BW A06) Control Room Evacuation / 8 N/A - Not randomly selected 000069 (APE 69; W E14) Loss of Containment Integrity / 5 N/A - Not randomly selected 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling / X G 2.1.19 - Ability to use plant 3.9 24 4 computers to evaluate system or component status 000076 (APE 76) High Reactor Coolant Activity / 9 N/A - Not randomly selected 000078 (APE 78*) RCS Leak / 3 N/A - Not randomly selected (W E01 & E02) Rediagnosis & SI Termination / 3 X G 2.4.45 - Ability to prioritize and 4.1 25 interpret the significance of each annunciator or alarm (W E13) Steam Generator Overpressure / 4 N/A - Not randomly selected (W E15) Containment Flooding / 5 N/A - Not randomly selected (W E16) High Containment Radiation /9 X EK 2.1 - Knowledge of the 3.0 26 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

ES-401 5 Form ES-401-2 (BW A01) Plant Runback / 1 N/A - Not randomly selected (BW A02 & A03) Loss of NNI-X/Y/7 N/A - Not randomly selected (BW A04) Turbine Trip / 4 N/A - Not randomly selected (BW A05) Emergency Diesel Actuation / 6 N/A - Not randomly selected (BW A07) Flooding / 8 N/A - Not randomly selected (BW E03) Inadequate Subcooling Margin / 4 N/A - Not randomly selected (BW E08; W E03) LOCA CooldownDepressurization / 4 X EK 1.3 - Knowledge of the 3.5 27 operational implications of the following concepts as they apply to the (LOCA Cooldown and Depressurization): Annunciators and conditions indicating signals, and remedial actions associated with the (LOCA Cooldown and Depressurization)

(BW E09; CE A13**; W E09 & E10) Natural Circulation/4 N/A - Not randomly selected (BW E13 & E14) EOP Rules and Enclosures N/A - Not randomly selected (CE A11**; W E08) RCS OvercoolingPressurized Thermal N/A - Not randomly selected Shock / 4 (CE A16) Excess RCS Leakage / 2 N/A - Not randomly selected (CE E09) Functional Recovery N/A - Not randomly selected (CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 N/A - Not randomly selected K/A Category Point Totals: 1 2 2 1 1 2 Group Point Total: 9/4

ES-401 6 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

A 1.04 - Ability to predict and/or monitor 003 (SF4P RCP) Reactor Coolant X changes in parameters (to prevent exceeding 2.5 28 Pump design limits) associated with operating the RCPS controls including: RCP standpipe levels 004 (SF1; SF2 CVCS) Chemical and X K 2.03 - Knowledge of bus power supplies to 3.3 29 Volume Control the following: Charging Pumps G 2.1.28 - Knowledge of the purpose and 004 (SF1; SF2 CVCS) Chemical and X function of major system components and 4.1 30 Volume Control controls K 6.03 - Knowledge of the effect of a loss or 005 (SF4P RHR) Residual Heat X malfunction on the following will have on the 2.5 31 Removal RHRS: RHR heat exchanger K 5.04 - Knowledge of the operational 006 (SF2; SF3 ECCS) Emergency X implications of the following concepts as they 2.9 32 Core Cooling apply to ECCS: Brittle fracture, including causes and preventative actions.

K 3.01 - Knowledge of the effect that a loss or 007 (SF5 PRTS) Pressurizer X malfunction of the PRTS will have on the 3.3 33 Relief/Quench Tank following: Containment K 1.04 - Knowledge of the physical 008 (SF8 CCW) Component Cooling X connections and/or cause-effect relationships 3.3 34 Water between the CCWS and the following systems:

RCS, in order to determine source(s) of RCS leakage into the CCWS K 4.09 - Knowledge of CCWS design 008 (SF8 CCW) Component Cooling X feature(s) and/or interlock(s) which provide for 2.7 35 Water the following: The "standby" feature for the CCW pumps 010 (SF3 PZR PCS) Pressurizer X A 3.02 - Ability to monitor automatic operation 3.6 36 Pressure Control of the PZR PCS, including PZR pressure.

K 5.01 - Knowledge of the operational 012 (SF7 RPS) Reactor Protection X implications of the following concepts as the 3.3 37 apply to the RPS: DNB 012 (SF7 RPS) Reactor Protection X G 2.4.31 - Knowledge of annunciator alarms, 4.2 38 indications, or response procedures K 4.12 - Knowledge of ESFAS design 013 (SF2 ESFAS) Engineered X feature(s) and/or interlocks which provide the 3.7 39 Safety Features Actuation following: Safety injection block A 1.01 - Ability to predict and/or monitor 022 (SF5 CCS) Containment Cooling X changes in parameters (to prevent exceeding 3.6 40 design limits) associated with operating the CCS controls including: Containment temperature 025 (SF5 ICE) Ice Condenser N/A - Not randomly selected, not applicable to Salem 026 (SF5 CSS) Containment Spray X K 4.08 - Knowledge of CSS design feature(s) 4.1 41 and/or interlock(s) which provide for the following: Automatic swapover to containment sump suction for recirculation phase after LOCA (RWST low-low level alarm).

G 2.1.25 - Containment Spray: Ability to 026 (SF5 CSS) Containment Spray X interpret reference materials, such as graphs, 3.9 42 curves, tables, etc.

K 1.02 - Knowledge of the physical 039 (SF4S MSS) Main and Reheat X connections and/or cause-effect relationships 3.3 43 Steam between the MRSS and the following systems:

Atmospheric relief dump valves

ES-401 7 Form ES-401-2 K 1.02 - Knowledge of the physical 059 (SF4S MFW) Main Feedwater X connections and/or cause-effect relationships 3.4 44 between the MFW and the following systems:

AFW system A 2.12 - Ability to (a) predict the impacts of the 059 (SF4S MFW) Main Feedwater X following malfunctions or operations on the 3.1 45 MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of feedwater regulating valves 061 (SF4S AFW) X A 3.03 - Ability to monitor automatic operation 3.9 46 Auxiliary/Emergency Feedwater of the AFW, including: AFW S/G level control on automatic start K 1.02 - Knowledge of the physical 062 (SF6 ED AC) AC Electrical X connections and/or cause-effect relationships 4.1 47 Distribution between the ac distribution system and the following systems: ED/G 062 (SF6 ED AC) AC Electrical X A 4.07 - Ability to manually operate and/or 3.1 48 Distribution monitor in the control room: Synchronizing and paralleling of different ac supplies 063 (SF6 ED DC) DC Electrical X A 4.03 - Ability to manually operate and/or 3.0 49 Distribution monitor in the control room: Battery discharge rate K 6.07 - Knowledge of the effect of a loss or 064 (SF6 EDG) Emergency Diesel X malfunction of the following will have on the 2.7 50 Generator ED/G system. Air Receivers K 4.01 - Knowledge of PRM system design 073 (SF7 PRM) Process Radiation X feature(s) and/or interlock(s) which provide for 4.0 51 Monitoring the following: Release termination when radiation exceeds setpoint K 3.07 - Knowledge of the effect that a loss or 076 (SF4S SW) Service Water X malfunction of the SWS will have on the 3.7 52 following: ESF loads A 2.01 - Ability to (a) predict the impacts of the 076 (SF4S SW) Service Water X following malfunctions or operations on the 3.5 53 SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SWS 078 (SF8 IAS) Instrument Air X K 2.02 - Knowledge of bus power supplies to 3.3 54 the following: Emergency air compressor A 3.01 - Ability to monitor automatic operation 103 (SF5 CNT) Containment X of the containment system, including: 3.9 55 Containment isolation 053 (SF1; SF4P ICS*) Integrated N/A for NUREG-1122, Rev. 2 Control K/A Category Point Totals: 4 2 2 4 2 2 2 2 3 2 3 Group Point Total: 28/5

ES-401 8 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO/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 X K 2.05 - Knowledge of bus power supplies to 3.1 56 the following: M/G sets 002 (SF2; SF4P RCS) Reactor N/A - Not randomly selected Coolant 011 (SF2 PZR LCS) Pressurizer N/A - Not randomly selected Level Control 014 (SF1 RPI) Rod Position N/A - Not randomly selected Indication 015 (SF7 NI) Nuclear N/A - Not randomly selected Instrumentation 016 (SF7 NNI) Nonnuclear X K3.02 - Knowledge of the effect that a loss or 3.4 57 Instrumentation malfunction of the NNIS will have on the following: PZR LCS 017 (SF7 ITM) In-Core Temperature X K 4.01 - Knowledge of ITM system design 3.4 58 Monitor feature(s) and/or interlock(s) which provide for the following: Input to subcooling monitors 027 (SF5 CIRS) Containment Iodine N/A - Not randomly selected Removal 028 (SF5 HRPS) Hydrogen N/A - Not randomly selected Recombiner and Purge Control 029 (SF8 CPS) Containment Purge X K 1.03 - Knowledge of the physical 3.6 59 connections and/or cause-effect relationships between the Containment Purge System and the following systems: Engineered safeguards 033 (SF8 SFPCS) Spent Fuel Pool X K 4.03 - Spent Fuel Cooling: Knowledge of 2.6 62 Cooling design feature(s) and/or interlock(s) which provide for the following: Anti-siphon devices 034 (SF8 FHS) Fuel-Handling N/A - Not randomly selected Equipment 035 (SF 4P SG) Steam Generator X K 6.03 - Knowledge of the effect of a loss or 2.6 60 malfunction on the following will have on the S/GS: S/G level detector 041 (SF4S SDS) Steam X A 3.05 - Ability to monitor automatic operation 2.9 61 Dump/Turbine Bypass Control of the SDS, including: Main steam pressure 045 (SF 4S MTG) Main Turbine N/A - Not randomly selected Generator 055 (SF4S CARS) Condenser Air X K 3.01 - Knowledge of the effect that a loss or 2.5 63 Removal malfunction of the CARS will have on the following: Main condenser 056 (SF4S CDS) Condensate N/A - Not randomly selected 068 (SF9 LRS) Liquid Radwaste N/A - Not randomly selected 071 (SF9 WGS) Waste Gas N/A - Not randomly selected Disposal 072 (SF7 ARM) Area Radiation N/A - Not randomly selected Monitoring 075 (SF8 CW) Circulating Water X A 2.02 - Ability to (a) predict the impacts of the 2.5 64 following malfunctions or operations on the circulating water system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of circulating water pumps 079 (SF8 SAS**) Station Air N/A - Not randomly selected 086 Fire Protection X A 1.05 - Ability to predict and/or monitor 2.9 65 changes in parameters (to prevent exceeding design limits) associated with Fire Protection System operating the controls including: FPS lineups

ES-401 9 Form ES-401-2 050 (SF 9 CRV*) Control Room N/A for NUREG-1122, Rev. 2 Ventilation K/A Category Point Totals: 1 1 2 2 0 1 1 1 1 0 0 Group Point Total: 10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: SALEM Date of Exam: JULY 2020 Category K/A # Topic RO SRO-only IR # IR #

G 2.1.1 - Knowledge of conduct of operations requirements.

2.1. 3.8 66 2.1. G 2.1.3 - Knowledge of shift or short-term relief turnover 3.7 67 practices.

G 2.1.37 - Knowledge of procedures, guidelines, or limitations

1. Conduct of 2.1. associated with reactivity management.

4.3 68 Operations 2.1.

2.1.

Subtotal 2.2. G 2.2.14 - Knowledge of the process for controlling equipment 3.9 69 configuration or status.

2.2. G 2.2.13 - Knowledge of tagging and clearance procedures. 4.1 70

2. Equipment 2.2. G 2.2.12 - Knowledge of surveillance procedures. 3.7 71 Control 2.2.

2.2.

Subtotal G 2.3.14 - Knowledge of radiation or contamination hazards that 2.3. may arise during normal, abnormal, or emergency conditions or 3.4 72 activities.

G 2.3.4 - Knowledge of radiation exposure limits under normal or 2.3. emergency conditions.

3.2 73

3. Radiation 2.3.

Control 2.3.

2.3.

Subtotal 2.4. G 2.4.17 - Knowledge of EOP terms and definitions. 3.9 74 G 2.4.25 - Knowledge of fire protection procedures.

2.4. 3.3 75 2.4.

4. Emergency Procedures/Plan 2.4.

2.4.

Subtotal Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/1 000058G2.1.25 Unable to write a discriminating question utilizing graphs, curves, tables, etc. Replaced with K/A 000058G2.4.6.

1/1 000058G2.4.6. Unable to write a fair and discriminating RO level question.

Replaced with K/A 000058AA2.03 1/1 000065AA1.03 Unable to write a discriminating question with plausible distractors. Replaced with K/A 000065AA1.04.

1/2 000003AK1.22 Unable to write a discriminating question with plausible distractors. Replaced with K/A 000003AK3.04.

1/2 000033AA2.02 Unable to write a fair and discriminating RO level question.

Replaced with K/A 000033AA2.09.

1/2 WE01G2.4.45 Unable to write a discriminating question with plausible distractors. Replaced with K/A WE02G2.4.45.

2/1 003A1.04 Potential overlap with Question #4. Replaced with K/A 003A1.10.

2/1 004K2.06 Potential overlap with Question #12. Replaced with K/A 004K2.03.

2/1 006K5.09 Potential overlap with LOCA-2 questions (2,3,25,27).

Replaced with K/A 006K5.04.

2/1 010A3.01 Potential overlap with Question # 33. Replaced with K/A 010A3.02.

2/1 013A2.03 Unable to write a fair and discriminating RO level question.

Replaced with K/A 013K4.12.

2/1 026K2.01 Potential overlap with Question #40. Replaced with K/A 026K4.08.

2/1 026G2.4.8 Unable to write a discriminating question with plausible distractors. Replaced with K/A 026G2.1.25.

2/1 064A2.16 Unable to write a fair and discriminating RO level question.

Replaced with K/A 064K6.07.

2/2 035K6.02 Potential overlap with Question # 43. Replaced with K/A 035K6.03.

2/2 045K5.17 Unable to write a fair and discriminating RO level question.

Replaced with K/A 033K4.03.

3/1 G2.1.15 Unable to write a fair and discriminating RO level question.

Replaced with K/A G2.1.1.

3/1 G2.1.30 Unable to write discriminating question that maintained its focus on being a plantwide generic question. Replaced with K/A G2.1.3.

ES-401 Record of Rejected K/As Form ES-401-4 3/4 G2.4.39 Unable to write discriminating question that maintained its focus on being a plantwide generic question. Replaced with K/A G2.4.17.

ES-401 PWR Examination Outline Form ES-401-2 Facility: SALEM Date of Exam: JULY 2020 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 18 4 2 6 Emergency and Abnormal Plant 2 N/A N/A 9 3 1 4 Evolutions Tier Totals 27 7 3 10 1 28 3 2 5 2.

Plant 2 10 2 1 3 Systems Tier Totals 38 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 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 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.)