Text

1-CW-2020-08 Draft Outlines
	ML20276A152
Person / Time
Site:	Callaway
Issue date:	09/09/2020
From:	Greg Werner; Operations Branch IV
To:	; Ameren Missouri
References
	Download: ML20276A152 (69)
	v • d • e

ES-401 PWR Examination Outline - RO Form ES-401-2 Facility: Callaway Plant Date of Exam: August 31, 2020 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

4 3

4 N/A 2

3 N/A 2

18 6

2 2

2 1

1 1

2 9

4 Tier Totals 6

5 5

3 4

4 27 10

2.

Plant Systems 1

3 1

4 3

1 1

3 3

3 28 5

2 2

1 0

2 1

1 0

0 0

10 3

Tier Totals 5

2 4

5 2

3 4

4 3

3 3

38 8

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

2 3

4 7

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)

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

EA2.02 Ability to determine or interpret the following as they apply to a reactor trip:

Proper actions to be taken if the automatic safety functions have not taken place (CFR 43.5 / 45.13) 4.3 1

000008 (APE 8) Pressurizer Vapor Space Accident / 3 X

AK3.05 Knowledge of the reasons for the following responses as they apply to the Pressurizer Vapor Space Accident:

ECCS termination or throttling criteria.

(CFR 41.5,41.10 / 45.6 / 45.13) 4.0 2

000009 (EPE 9) Small Break LOCA / 3 000011 (EPE 11) Large Break LOCA / 3 X

EA1.05 Ability to operate and monitor the following as they apply to a Large Break LOCA:

Manual and/or automatic transfer of suction of charging pumps to borated source (CFR 41.7 / 45.5 / 45.6).

4.3 3

000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 X

AK1.02 Knowledge of the operational implications of the following concepts as they apply to Reactor Coolant Pump Malfunctions (Loss of RC Flow):

Consequences of an RCPS failure (CFR 41.8 / 41.10 / 45.3) 3.7 4

000022 (APE 22) Loss of Reactor Coolant Makeup / 2 X

AK3.02 Knowledge of the reasons for the following responses as they apply to the Loss of Reactor Coolant Makeup:

Actions contained in SOPs and EOPs for RCPs, loss of makeup, loss of charging, and abnormal charging (CFR 41.5, 41.10 / 45.6 / 45.13) 3.5 5

000025 (APE 25) Loss of Residual Heat Removal System / 4 X

AK2.01 Knowledge of the interrelations between the Loss of Residual Heat Removal System and the following:

RHR heat exchangers.

(CFR 41.7 / 45.7) 2.9 6

000026 (APE 26) Loss of Component Cooling Water / 8 X

2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation.

(CFR: 41.10 / 43.5 / 45.2 / 45.6) 4.3 7

000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 X

AK3.03 Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure Control Malfunctions:

Actions contained in EOP for PZR PCS malfunctions (CFR 41.5,41.10 / 45.6 / 45.13) 3.7 8

000029 (EPE 29) Anticipated Transient Without Scram / 1 X

EA1.14 Ability to operate and monitor the following as they apply to an ATWS:

Driving of control rods into the core (CFR 41.7 / 45.5 / 45.6) 4.2 9

ES-401 3

Form ES-401-2 000038 (EPE 38) Steam Generator Tube Rupture / 3 X

EA2.16 Ability to determine or interpret the following as they apply to a SGTR:

Actions to be taken if S/G goes solid and water enters steam line.

(CFR 43.5 / 45.13) 4.2 10 000040 (APE 40; BW E05; CE E05; W E12)

Steam Line RuptureExcessive Heat Transfer / 4 X

AK1.07 Knowledge of the operational implications of the following concepts as they apply to Steam Line Rupture:

Effects of feedwater introduction on dry S/G (CFR 41.8 / 41.10 / 45.3) 3.4 11 000054 (APE 54; CE E06) Loss of Main Feedwater /4 X

2.4.4 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 12 000055 (EPE 55) Station Blackout / 6 X

EK1.01 Knowledge of the operational implications of the following concepts as they apply to the Station Blackout:

Effect of battery discharge rates on capacity (CFR 41.8 / 41.10 / 45.3) 3.3 13 000056 (APE 56) Loss of Offsite Power / 6 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 X

AA2.19 Ability to determine and interpret the following as they apply to the Loss of Vital AC Instrument Bus:

The plant automatic actions that will occur on the loss of a vital ac electrical instrument bus (CFR: 43.5 / 45.13) 4.0 14 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

AK3.03 Knowledge of the reasons for the following responses as they apply to the Loss of Instrument Air:

Knowing effects on plant operation of isolating certain equipment from instrument air (CFR 41.5,41.10 / 45.6 / 45.13) 2.9 15 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 (W E04) LOCA Outside Containment / 3 X

EK2.1 Knowledge of the interrelations between the (LOCA Outside Containment) and the following:

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(CFR: 41.7 / 45.7) 3.5 16

ES-401 4

Form ES-401-2 (W E11) Loss of Emergency Coolant Recirculation / 4 X

EK2.2 Knowledge of the interrelations between the (Loss of Emergency Coolant Recirculation) and the following:

Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

(CFR: 41.7 / 45.7) 3.9 17 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 X

EK1.3 Knowledge of the operational implications of the following concepts as they apply to the (Loss of Secondary Heat Sink):

Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Secondary Heat Sink).

(CFR: 41.8 / 41.10, 45.3) 3.9 18 K/A Category Totals:

4 3

4 2

3 2

Group Point Total:

18

ES-401 5

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 000005 (APE 5) Inoperable/Stuck Control Rod / 1 000024 (APE 24) Emergency Boration / 1 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 X

AK3.03 Knowledge of the reasons for the following responses as they apply to the Pressurizer Level Control Malfunctions:

False indication of PZR level when PROV or spray valve is open and RCS saturated (CFR 41.5,41.10 / 45.6 / 45.13) 3.5 19 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 X

AK1.01 Knowledge of the operational implications of the following concepts as they apply to Loss of Source Range Nuclear Instrumentation:

Effects of voltage changes on performance (CFR 41.8 / 41.10 / 45.3) 2.5 20 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 X

AA2.02 Ability to determine and interpret the following as they apply to the Loss of Condenser Vacuum:

Conditions requiring reactor and/or turbine trip (CFR: 43.5 / 45.13) 3.9 21 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 X

2.1.30 Ability to locate and operate components, including local controls.

(CFR: 41.7 / 45.7) 4.4 22 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 000076 (APE 76) High Reactor Coolant Activity / 9 X

AK2.01 Knowledge of the interrelations between the High Reactor Coolant Activity and the following:

Process radiation monitors (CFR 41.7 / 45.7) 2.6 23 000078 (APE 78*) RCS Leak / 3 NA

ES-401 6

Form ES-401-2 (W E01 & E02) Rediagnosis & SI Termination / 3 X

EK1.2 Knowledge of the operational implications of the following concepts as they apply to the (SI Termination):

Normal, abnormal and emergency operating procedures associated with (SI Termination).

(CFR: 41.8 / 41.10, 45.3) 3.4 24 (W E13) Steam Generator Overpressure / 4 X

2.2.44 Ability to interpret control room indication to verify the status and operations of a system, and understand how operator actions and directives affect plant and system conditions.

(CFR: 41.5 / 43.5 / 45.12) 4.2 25 (W E15) Containment Flooding / 5 X

EA1.3 Ability to operate and / or monitor the following as they apply to the (Containment Flooding):

Desired operating results during abnormal and emergency situations.

(CFR: 41.7 / 45.5 / 45.6) 2.8 26 (W E16) High Containment Radiation /9 (BW A01) Plant Runback / 1 NA (BW A02 & A03) Loss of NNI-X/Y/7 NA (BW A04) Turbine Trip / 4 NA (BW A05) Emergency Diesel Actuation / 6 NA (BW A07) Flooding / 8 NA (BW E03) Inadequate Subcooling Margin / 4 NA (BW E08; W E03) LOCA CooldownDepressurization / 4 X

EK2.2 Knowledge of the interrelations between the (LOCA Cooldown and Depressurization) and the following:

Facility*s heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

(CFR: 41.7 / 45.7) 3.7 27 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 (BW E13 & E14) EOP Rules and Enclosures NA (CE A11**; W E08) RCS OvercoolingPressurized Thermal Shock / 4 (CE A16) Excess RCS Leakage / 2 NA (CE E09) Functional Recovery NA (CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 NA K/A Category Point Totals:

2 2

1 1

1 2

Group Point Total:

9

ES-401 7

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

System # / Name K1 K2 K 3

K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR 003 (SF4P RCP) Reactor Coolant Pump ROX2 X

K1.03 Knowledge of the physical connections and/or cause-effect relationships between the RCPS and the following systems:

RCP seal system (CFR: 41.2 to 41.9 / 45.7 to 45.8) 3.3 28 003 (SF4P RCP) Reactor Coolant Pump ROX2 X

A3.05 Ability to monitor automatic operation of the RCPS, including:

RCP lube oil and bearing lift pumps (CFR: 41.7 / 45.5) 2.7 29 004 (SF1; SF2 CVCS) Chemical and Volume Control X

K1.19 Knowledge of the physical connections and/or cause-effect relationships between the CVCS and the following systems:

Primary grade water supply (CFR: 41.2 to 41.9 / 45.7 to 45.8) 2.7 30 005 (SF4P RHR) Residual Heat Removal ROX2 X

K3.07 Knowledge of the effect that a loss or malfunction of the RHRS will have on the following:

Refueling operations (CFR: 41.7 / 45.6) 3.2 31 005 (SF4P RHR) Residual Heat Removal ROX2 X

A4.02 Ability to manually operate and/or monitor in the control room:

Heat exchanger bypass flow control (CFR: 41.7 / 45.5 to 45.8) 3.4 32 006 (SF2; SF3 ECCS) Emergency Core Cooling X

K4.11 Knowledge of ECCS design feature(s) and/or interlock(s) which provide for the following:

Reset of SIS (CFR: 41.7) 3.9 33 007 (SF5 PRTS) Pressurizer Relief/Quench Tank X

G2.1.23 Ability to perform specific system and integrated plant procedures during all modes of plant operation (CFR: 41.10 / 43.5 / 45.2 / 45.6) 4.3 34 008 (SF8 CCW) Component Cooling Water ROX2 X

A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Loss of CCW pump (CFR: 41.5 / 43.5 / 45.3 / 45.13) 3.3 35 008 (SF8 CCW) Component Cooling Water ROX2 X

A1.02 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCWS controls including:

CCW temperature (CFR: 41.5 / 45.5) 2.9 36

ES-401 8

Form ES-401-2 010 (SF3 PZR PCS) Pressurizer Pressure Control X 2.1.32 Ability to explain and apply system limits and precautions.

(CFR: 41.10 / 43.2 / 45.12) 3.8 37 012 (SF7 RPS) Reactor Protection ROX2 X

K4.02 Knowledge of RPS design feature(s) and/or interlock(s) which provide for the following:

Automatic reactor trip when RPS Setpoints are exceeded for each RPS function; basis for each (CFR: 41.7) 3.9 38 012 (SF7 RPS) Reactor Protection ROX2 X

A2.07 Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Loss of dc control.

(CFR: 41.5 / 43.5 / 45.3 / 45.5) 3.2 39 013 (SF2 ESFAS) Engineered Safety Features Actuation X

K2.01 Knowledge of bus power supplies to the following:

ESFAS/safeguards equipment control (CFR: 41.7) 3.6 40 022 (SF5 CCS) Containment Cooling X

K3.01 Knowledge of the effect that a loss or malfunction of the CCS will have on the following:

Containment equipment subject to damage by high or low temperature, humidity, and pressure (CFR: 41.7 / 45.6) 2.9 41 025 (SF5 ICE) Ice Condenser NA 026 (SF5 CSS) Containment Spray ROX2 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 (CFR: 41.5 / 45.5) 3.9 42 026 (SF5 CSS) Containment Spray ROX2 X

K3.01 Knowledge of the effect that a loss or malfunction of the CSS will have on the following:

CCS (CFR: 41.7 / 45.6) 3.9 43 039 (SF4S MSS) Main and Reheat Steam ROX2 X

A1.03 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MRSS controls including:

Primary system temperature indications, and required values, during main steam system warm-up (CFR: 41.5 / 45.5) 2.6 44

ES-401 9

Form ES-401-2 039 (SF4S MSS) Main and Reheat Steam ROX2 X

K5.01 Knowledge of the operational implications of the following concepts as the apply to the MRSS:

Definition and causes of steam/water hammer (CFR: 41.5 / 45.7) 2.9 45 059 (SF4S MFW) Main Feedwater X

A3.06 Ability to monitor automatic operation of the MFW, including:

Feedwater Isolation (CFR: 41.7 / 45.5) 3.2 46 061 (SF4S AFW)

Auxiliary/Emergency Feedwater X

A3.01 Ability to monitor automatic operation of the AFW, including:

AFW startup and flows (CFR: 41.7 / 45.5) 4.2 47 062 (SF6 ED AC) AC Electrical Distribution X

A4.02 Ability to manually operate and/or monitor in the control room:

Remote racking in and out of breakers (CFR: 41.7 / 45.5 / to 45.8) 2.5 48 063 (SF6 ED DC) DC Electrical Distribution X 2.4.46 Ability to verify that the alarms are consistent with the plant conditions.

(CFR: 41.10 / 43.5 / 45.3 / 45.12) 4.2 49 064 (SF6 EDG) Emergency Diesel Generator X

K6.07 Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system:

Air receivers (CFR: 41.7 / 45.7) 2.7 50 073 (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 (CFR: 41.7) 4.0 51 076 (SF4S SW) Service Water ROX2 X

A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Loss of SWS (CFR: 41.5 / 43.5 / 45.3 / 45.13) 3.5 52 076 (SF4S SW) Service Water ROX2 X

K1.21 Knowledge of the physical connections and/or cause-effect relationships between the SWS and the following systems:

Auxiliary backup SWS (CFR: 41.2 to 41.9 / 45.7 to 45.8) 2.7 53

ES-401 10 Form ES-401-2 078 (SF8 IAS) Instrument Air X

K3.02 Knowledge of the effect that a loss or malfunction of the IAS will have on the following:

Systems having pneumatic valves and controls (CFR: 41.7 / 45.6) 3.4 54 103 (SF5 CNT) Containment X

A4.04 Ability to manually operate and/or monitor in the control room:

Phase A and phase B resets (CFR: 41.7 / 45.5 to 45.8) 3.5 55 053 (SF1; SF4P ICS*) Integrated Control NA K/A Category Point Totals:

3 1

4 3 1

1 3

3 3

Group Point Total:

28

ES-401 11 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

K6.11 Knowledge of the effect of a loss or malfunction on the following CRDS components:

Location and operation of CRDS fault detection (trouble alarms) and reset system, including rod control annunciator (CFR: 41.7/45.7) 2.9 56 002 (SF2; SF4P RCS) Reactor Coolant 011 (SF2 PZR LCS) Pressurizer Level Control 014 (SF1 RPI) Rod Position Indication X

K4.06 Knowledge of RPIS design feature(s) and/or interlock(s) which provide for the following:

Individual and group misalignment (CFR: 41.5 / 45.7) 3.4 57 015 (SF7 NI) Nuclear Instrumentation X

K2.01 Knowledge of bus power supplies to the following:

NIS channels, components, and interconnections (CFR: 41.7) 3.3 58 016 (SF7 NNI) Nonnuclear Instrumentation 017 (SF7 ITM) In-Core Temperature Monitor X

K6.01 Knowledge of the effect of a loss or malfunction of the following ITM system components:

Sensors and detectors (CFR: 41.7 / 45.7) 2.7 59 027 (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 X

A1.01 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with Spent Fuel Pool Cooling System operating the controls including:

Spent fuel pool water level (CFR: 41.5 / 45.5) 2.7 60 034 (SF8 FHS) Fuel-Handling Equipment 035 (SF 4P SG) Steam Generator X

K5.03 Knowledge of operational implications of the following concepts as the apply to the S/GS:

Shrink and swell concept (CFR: 41.5 / 45.7) 2.8 61 041 (SF4S SDS) Steam Dump/Turbine Bypass Control X

K4.18 Knowledge of SDS design feature(s) and/or interlock(s) which provide for the following:

Turbine trip (CFR: 41.7) 3.4 62 045 (SF 4S MTG) Main Turbine Generator

ES-401 12 Form ES-401-2 055 (SF4S CARS) Condenser Air Removal X

K1.06 Knowledge of the physical connections and/or cause-effect relationships between the CARS and the following systems:

PRM system (CFR: 41.2 to 41.9 / 45.7 to 45.8) 2.6 63 056 (SF4S CDS) Condensate 068 (SF9 LRS) Liquid Radwaste X

K1.07 Knowledge of the physical connections and/or cause effect relationships between the Liquid Radwaste System and the following systems:

Sources of liquid wastes for LRS (CFR: 41.2 to 41.9 / 45.7 to 45.8) 2.7 64 071 (SF9 WGS) Waste Gas Disposal 072 (SF7 ARM) Area Radiation Monitoring 075 (SF8 CW) Circulating Water X

A2.01 Ability to (a) predict the impacts of the 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 intake structure (CFR: 41.5 / 43.5 / 45.3 / 45.13) 3.0 65 079 (SF8 SAS**) Station Air 086 Fire Protection 050 (SF 9 CRV*) Control Room Ventilation NA K/A Category Point Totals:

2 1

0 2

1 2

1 1

0 0

0 Group Point Total:

10

ES-401 Generic Knowledge and Abilities Outline (Tier 3) RO Form ES-401-3 Facility:

Date of Exam:

Category K/A #

Topic RO SRO-only IR IR

1. Conduct of Operations 2.1.26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

(CFR: 41.10 / 45.12) 3.4 66 2.1.37 Knowledge of procedures, guidelines, or limitations associated with reactivity management.

(CFR: 41.1 / 43.6 / 45.6) 4.3 67 2.1.44 Knowledge of RO duties in the control room during fuel handling, such as l responding to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

(CFR: 41.10 / 43.7 / 45.12) 3.9 68 Subtotal 3

2. Equipment Control 2.2.14 Knowledge of the process for controlling equipment configuration or status.

(CFR: 41.10 / 43.3 / 45.13) 3.9 69 2.2.41 Ability to obtain and interpret station electrical and mechanical drawings.

(CFR: 41.10 / 45.12 / 45.13) 3.5 70 2.2.43 Knowledge of the process used to track inoperable alarms.

(CFR: 41.10 / 43.5 / 45.13) 3.0 71 Subtotal 3

3. Radiation Control 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

(CFR: 41.12 / 43.4 / 45.10) 3.2 72 2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

(CFR: 41.12 / 43.4 / 45.9) 2.9 73 Subtotal 2

4. Emergency Procedures/Plan 2.4.3 Ability to identify post-accident instrumentation.

(CFR: 41.6 / 45.4) 3.7 74 2.4.17 Knowledge of EOP terms and definitions.

(CFR: 41.10 / 45.13) 3.9 75 Subtotal 2

Tier 3 Point Total 10

ES-401 PWR Examination Outline - SRO Form ES-401-2 Facility: Callaway Plant Date of Exam: August 31, 2020 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

N/A N/A 18 3

3 6

2 9

2 2

4 Tier Totals 27 5

5 10

2.

Plant Systems 1

28 3

2 5

2 10 2

1 3

Tier Totals 38 5

3 8

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

2 3

4 7

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.)

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 15 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 000008 (APE 8) Pressurizer Vapor Space Accident / 3 000009 (EPE 9) Small Break LOCA / 3 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.

(CFR: 41.10 / 43.5 / 45.11) 4.1 76 000011 (EPE 11) Large Break LOCA / 3 000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 000022 (APE 22) Loss of Reactor Coolant Makeup / 2 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 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

2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

(CFR: 41.5 / 41.7 / 43.2) 4.2 77 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 000058 (APE 58) Loss of DC Power / 6 X

AA2.03 Ability to determine and interpret the following as they apply to the Loss of DC Power:

DC loads lost; impact on ability to operate and monitor plant systems (CFR: 43.5 / 45.13) 3.9 78 000062 (APE 62) Loss of Nuclear Service Water / 4 X

2.1.32 Ability to explain and apply system limits and precautions.

(CFR: 41.10 / 43.2 / 45.12) 4.0 80 000065 (APE 65) Loss of Instrument Air / 8

ES-401 16 Form ES-401-2 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 X

AA2.05 Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances:

Operational status of offsite circuit.

(CFR: 41.5 and 43.5 / 45.5, 45.7, and 45.8) 3.8 79 (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.

(CFR: 43.5 / 45.13) 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 17 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 X

2.2.40 Ability to apply Technical Specifications for a system.

(CFR: 41.10/43.2/43.5/45.3) 4.7 82 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 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 X

2.2.25 Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

(CFR: 41.5 / 41.7 / 43.2) 4.2 83 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

AA2.13 Ability to determine and interpret the following as they apply to the Plant Fire on Site:

Need for emergency plant shutdown (CFR: 43.5 / 45.13) 4.4 84 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 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 (BW A01) Plant Runback / 1 NA (BW A02 & A03) Loss of NNI-X/Y/7 NA (BW A04) Turbine Trip / 4 NA (BW A05) Emergency Diesel Actuation / 6 NA (BW A07) Flooding / 8 NA (BW E03) Inadequate Subcooling Margin / 4 NA (BW E08; W E03) LOCA CooldownDepressurization / 4 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 (BW E13 & E14) EOP Rules and Enclosures NA

ES-401 18 Form ES-401-2 (CE A11**; W E08) RCS OvercoolingPressurized Thermal Shock / 4 X

EA2.2 Ability to determine and interpret the following as they apply to the (Pressurized Thermal Shock):

Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments (CFR: 43.5 / 45.13) 4.1 85 (CE A16) Excess RCS Leakage / 2 NA (CE E09) Functional Recovery NA (CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 NA K/A Category Point Totals:

2 2

Group Point Total:

4

ES-401 19 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 ROX2 004 (SF1; SF2 CVCS) Chemical and Volume Control 005 (SF4P RHR) Residual Heat Removal ROX2 006 (SF2; SF3 ECCS) Emergency Core Cooling 007 (SF5 PRTS) Pressurizer Relief/Quench Tank 008 (SF8 CCW) Component Cooling Water ROX2 010 (SF3 PZR PCS) Pressurizer Pressure Control 012 (SF7 RPS) Reactor Protection ROX2 013 (SF2 ESFAS) Engineered Safety Features Actuation X

A2.04 Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations; Loss of instrument bus (CFR: 41.5 / 43.5 / 45.3 / 45.13) 4.2 86 022 (SF5 CCS) Containment Cooling 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.

(CFR: 41.7 / 43.5 / 45.12) 4.6 87 025 (SF5 ICE) Ice Condenser NA 026 (SF5 CSS) Containment Spray ROX2 039 (SF4S MSS) Main and Reheat Steam ROX2 059 (SF4S MFW) Main Feedwater 061 (SF4S AFW)

Auxiliary/Emergency Feedwater 062 (SF6 ED AC) AC Electrical Distribution X 2.2.37 Ability to determine operability and/or availability of safety related equipment.

(CFR: 41.7 / 43.5 / 45.12) 4.6 88 063 (SF6 ED DC) DC Electrical Distribution

ES-401 20 Form ES-401-2 064 (SF6 EDG) Emergency Diesel Generator X

A2.06 Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Operating unloaded, lightly loaded, and highly loaded time limit.

(CFR: 41.5 / 43.5 / 45.3 / 45.13) 3.3 89 073 (SF7 PRM) Process Radiation Monitoring X

A2.01 Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Erratic or failed power supply (CFR: 41.5 / 43.5 / 45.3 / 45.13) 2.9 90 076 (SF4S SW) Service Water ROX2 078 (SF8 IAS) Instrument Air 103 (SF5 CNT) Containment 053 (SF1; SF4P ICS*) Integrated Control NA K/A Category Point Totals:

3 2

Group Point Total:

5

ES-401 21 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 033 (SF8 SFPCS) Spent Fuel Pool Cooling 034 (SF8 FHS) Fuel-Handling Equipment X

A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the Fuel Handling System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Mispositioned fuel element (CFR: 41.5 / 43.5 / 45.3 / 45.13) 4.0 91 035 (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 068 (SF9 LRS) Liquid Radwaste 071 (SF9 WGS) Waste Gas Disposal 072 (SF7 ARM) Area Radiation Monitoring X

A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the ARM system-and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Detector failure (CFR: 41.5 / 43.5 / 43.3 / 45.13) 2.9 92 075 (SF8 CW) Circulating Water 079 (SF8 SAS**) Station Air 086 Fire Protection X

2.4.41 Knowledge of the emergency action level thresholds and classifications.

(CFR: 41.10 / 43.5 / 45.11) 4.6 93

ES-401 22 Form ES-401-2 050 (SF 9 CRV*) Control Room Ventilation NA K/A Category Point Totals:

2 1

Group Point Total:

3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) SRO Form ES-401-3 Facility: Callaway Plant Date of Exam: August 31, 2020 Category K/A #

Topic RO SRO-only IR IR

1. Conduct of Operations 2.1.34 Knowledge of primary and secondary plant chemistry limits.

(CFR: 41.10 / 43.5 / 45.12) 3.5 94 2.1.41 Knowledge of the refueling process.

(CFR: 41.2 / 41.10 / 43.6 / 45.13) 3.7 95 Subtotal 2

2. Equipment Control 2.2.5 Knowledge of the process for making design or operating changes to the facility.

(CFR: 41.10 / 43.3 / 45.13) 3.2 96 2.2.17 Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.

(CFR: 41.10 / 43.5 / 45.13) 3.8 97 Subtotal 2

3. Radiation Control 2.3.6 Ability to approve release permits.

(CFR: 41.13 / 43.4 / 45.10) 3.8 98 Subtotal 1

4. Emergency Procedures/Plan 2.4.29 Knowledge of the emergency plan.

(CFR: 41.10 / 43.5 / 45.11) 4.4 99 2.4.23 Knowledge of the bases for prioritizing emergency procedure implementation l during emergency operations.

(CFR: 41.10 / 43.5 / 45.13) 4.4 100 Subtotal 2

Tier 3 Point Total 7

ES-401 Record of Rejected K/As Form ES-401-4 Tier /

Group Randomly Selected K/A Reason for Rejection 1 / 1 K/A 027 AK3.01 AK3.03 - Pressurizer Pressure Control System Malfunction:

Actions contained in EOP for PZR PCS malfunctions.

Q#8 00027 AK3.04 - Pressurizer Pressure Control System Malfunction: Knowledge of the reasons for the following responses as they apply to the Pressurizer Pressure Control Malfunctions: Why, if PZR level is lost and then restored, that pressure recovers much more slowly.

Randomly replaced due to the inability to write a question with plausible distractors.

AK3.01 Isolation of PZR spray following loss of PZR heaters was reselected as the plant design did not contain the function / isolation supported by the K/A.

1 / 1 K/A 040 AK1.07 -

Steam Line Rupture:

Knowledge of the operational implications of the following concepts as they apply to Steam Line Rupture: Effects of feedwater introduction on dry S/G.

Q#11 00040 AK1.04 - Steam Line Rupture: Knowledge of the operational implications of the following concepts as they apply to Steam Line Rupture: Nil ductility temperature.

Randomly replaced due to the inability to write a question with plausible distractors.

1 / 2 K/A 028 AK3.03 Pressurizer (PZR)

Level Control Malfunction:

Knowledge of the reasons for the following responses as they apply to the Pressurizer Level Control Malfunctions:

False indication of PZR level when PORV or spray valve is open and RCS saturated.

Q#19 00028 AK3.04 - Pressurizer (PZR) Level Control Malfunction: Knowledge of the reasons for the following responses as they apply to the Pressurizer Level Control Malfunctions: Change in PZR level with power change, even though RCS T-ave. constant, due to loop size difference.

Plant design does not support this K/A as the loop sizes are effectively the same (27.5" ID vs 29").

ES-401 Record of Rejected K/As Form ES-401-4 1 / 2 K/A 061 G2.1.19 G2.1.30 Area Radiation Monitoring (ARM) System Alarms: Ability to locate and operate components, including local controls.

Q#22 00061 G2.1.31 - Area Radiation Monitoring (ARM) System Alarms: Ability to use plant computers to evaluate system or component status. Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

While there are some indications on the backpanel that may be used during source checks and alarms, plant lineups of ARMs are performed by the rad protection department. Randomly replaced due to the inability to write a question with plausible distractors applicable to control room operators.

Reselected G2.1.19 (Ability to use plant computers to evaluate system or component status.) due to inability to write question with plausible distractors.

1 / 2 K/A WE E13 G2.2.44 Steam Generator Overpressure: 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.

Q#25 WE E13 G2.2.12 - Steam Generator Overpressure:

Knowledge of surveillance procedures. Steam Generator overpressure is a functional restoration yellow path procedure that does not have surveillance procedures associated with it.

Randomly replaced K/A.

2 / 1 K/A 007 G2.1.23:

Pressurizer Relief Tank/Quench Tank System: Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Q#34 007 K5.02 - Pressurizer Relief Tank/Quench Tank System: Knowledge of the operational implications of the following concepts as the apply to PRTS: Method of forming a steam bubble in the PZR.

Unable to write a question with plausible distractors for the associated system as it does not apply to the K/A topic. The method of drawing a steam bubble in the PZR is independent of the PRT operation.

ES-401 Record of Rejected K/As Form ES-401-4 2 / 1 K/A 012 A2.07 -

Reactor Protection System: Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of dc control.

Q#39 012 A2.01 - Reactor Protection System: Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Faulty bistable operation.

Randomly replaced due to the inability to write a question with plausible distractors.

2 / 1 K/A 026 A1.01 -

Containment Spray System (CSS): Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including:

Containment Pressure.

Q#42 026 A1.06 - Containment Spray System (CSS):

Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: Containment spray pump cooling.

Randomly replaced as plant design did not support this K/A. Callaway's CTMT spray pumps are air cooled.

2 / 1 K/A 026 K3.01 -

Containment Spray System (CSS):

Knowledge of the effect that a loss or malfunction of the CSS will have on the following: CCS Q#43 026 K3.02 - Containment Spray System (CSS):

Knowledge of the effect that a loss or malfunction of the CSS will have on the following: Recirculation spray system.

Randomly replaced due to the inability to write a question with plausible distractors.

2 / 1 K/A 059 A3.06 - Main Feedwater (MFW)

System: Ability to monitor automatic operation of the MFW, including: Feedwater isolation.

Q#46 059 A3.02 - Main Feedwater (MFW) System:

Ability to monitor automatic operation of the MFW, including: Programmed levels of the S/G.

Randomly replaced due to the inability to write a question with plausible distractors as programmed SG level is independent of power level i.e. SG level is not a function of reactor power.

ES-401 Record of Rejected K/As Form ES-401-4 2 / 1 K/A 061 A3.01 -

Auxiliary / Emergency Feedwater (AFW)

System: Ability to monitor automatic operation of the AFW, including: AFW startup and flows.

Q#47 061 A3.04 - Auxiliary / Emergency Feedwater (AFW) System: Ability to monitor automatic operation of the AFW, including: Automatic AFW isolation.

Randomly replaced as plant design did not support this K/A. Callaway's AFW system does not have an automatic isolation feature.

2 / 1 K/A 103 A4.04 -

Containment System:

Ability to manually operate and/or monitor in the control room:

Phase A and phase B resets.

Q#55 103 A4.09 - Containment System: Ability to manually operate and/or monitor in the control room:

Containment vacuum system.

Randomly replaced due to the inability to write a question to this K/A in this system. Containment Purge would be the only applicable ventilation system which is covered under its own system topic.

2 / 2 K/A 014 K4.06 - Rod Position Indication System (RPIS):

Knowledge of RPIS design feature(s) and/or interlock(s) which provide for the following: Individual and group misalignment.

Q#57 014 K4.05 - Rod Position Indication System (RPIS): Knowledge of RPIS design feature(s) and/or interlock(s) which provide for the following: Zone reference lights.

Plant design does not support this K/A as there are no specific rod hold interlocks, there is rod overlap and rod movement rates and insertions due to runback etc but no hold interlocks.

SRO 1 / 2 K/A 059 G2.4.41 G2.2.25 - Accidental Liquid Radwaste Release: Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

Q#83 - 059 G2.4.35 Accidental Liquid Radwaste Release: Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

Randomly replaced due to the inability to write a SRO Level question with plausible distractors to this topic as there are few, if any, specific aux operator tasks for this event. A spill response team (which may or may not have Aux operators on it) would address the spill.

Reselected G2.4.41 as there was already one EAL question in order to avoid oversampling EALs for SROs.

ES-401 Record of Rejected K/As Form ES-401-4 SRO 2 / 1 K/A 073 A2.01 -

Process Radiation Monitoring (PRM)

System: Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Erratic or failed power supply.

Q#90 073 A2.03 - Process Radiation Monitoring (PRM)

System: Ability to (a) predict the impacts of the following malfunctions or operations on the PRM system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Calibration drift.

Randomly replaced due to the inability to write a SRO Level question with plausible distractors. If calibration drift is suspected the procedure selection to mitigate would be made by a different department after being notified by the shift.

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Callaway Date of Examination:

8/31/2020 Examination Level: RO SRO Operating Test Number:

2020-1 Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations RO Admin1 C, S, R N

G2.1.25 (3.9) Ability to interpret reference materials, such as graphs, curves, tables etc.

JPM: Calculate Boron Addition for blocking P-11 with 0 and 1 untrippable control rod.

Conduct of Operations RO Admin2 C, S, R N

G2.1.4 (3.3) Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.

JPM: Select available overtime shifts without violating shift staff limits in APA-ZZ-00905 Equipment Control RO Admin3 S, D G2.2.43 (3.0) Knowledge of the process used to track inoperable alarms.

JPM: Complete CA2557, Computer Point Status Log and delete PPC point from alarm Radiation Control RO Admin4 C, S, R M

G2.3.14 (3.4) Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

JPM: Determine if a respirator should be worn NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

Type Codes and Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1, randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 RO Administrative JPMs:

RO Admin #1 This is a NEW JPM. At the completion of this JPM, the applicant calculated the volume of borated water addition as 3245 lbm (+/- 1lbm) and 5893 lbm (+/- 1lbm) for the situations of 0 and 1 untrippable rods respectively.

RO Admin #2 This is a NEW JPM. At the completion of this JPM, the applicant determined they are available to fill the Thursday and Friday night shifts without violating the work hour restrictions of APA-ZZ-00905.

RO Admin #3 This is a BANK JPM that has not been used on at least the last 3 initial license exams. At the completion of this JPM, the applicant deleted PPC point AFQ0601 from alarm and correctly completed out a CA2557 column 1 and 5.

RO Admin #4 This is a MODIFIED BANK JPM. The original JPM (URO-ADM A004J) has not been used on at least the last 3 NRC ILT Exams.

This JPM was modified by adjusting the dose rate, internal dose without a respirator, the times to complete the job with and without a respirator, and the overall determination to wear a respirator.

ES-301 Administrative Topics Outline Form ES-301-1 Facility:

Callaway Date of Examination:

8/31/2020 Examination Level: RO SRO Operating Test Number:

2020-1 Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations SRO Admin1 C, S, R N

G2.1.2 (4.4) Knowledge of operator responsibilities during all modes of plant operations.

JPM: Determine risk management actions for NG07 Switchgear OOS.

Conduct of Operations SRO Admin2 C, S, R N

G2.1.1 (4.2) Knowledge of conduct of operatins requirements.

JPM: Determine Shift Manager Communication Requirements.

Equipment Control SRO Admin3 C, S, R N

G2.2.12 (4.1) Knowledge of surveillance procedures.

JPM: Review OSP-EG-P01AC, determine errors and document Operability concerns.

Radiation Control SRO Admin4 C, S, R M

G2.3.14 (3.8) Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.

JPM: Select individual to exceed dose limit for accident mitigation.

Emergency Plan SRO Admin5 C, S, R N

G2.4.44 (4.4) Knowledge of emergency plan protective action recommendations JPM: Complete CA 2843, PAR Flowchart.

NOTE: All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

Type Codes and Criteria:

(C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs and RO retakes)

(N)ew or (M)odified from bank ( 1)

(P)revious 2 exams ( 1, randomly selected)

ES-301 Administrative Topics Outline Form ES-301-1 SRO Administrative JPMs:

SRO Admin1 This is a NEW JPM. At the completion of this JPM, the applicant determined that 'B' ESW Train and the TDAFP shall be maintained operable. No work will be allowed on AEPS, Security Diesel, or within 50 feet of the startup transformer. The applicant also determined that 3 areas (NB02, TB 2065' general area, and the condensate polisher area) require a RMA walkdown.

SRO Admin2 This is a NEW JPM. At the completion of this JPM, the applicant listed the 6 individuals/positions that should be notified due to a contaminated, injured person that will be transported via ambulance offsite for medical assistance.

SRO Admin3 This is a NEW JPM. At the completion of this JPM, the applicant determined that the pump differential pressure was incorrectly calculated, Vibration data at position F is in the Alert Range and Vibration data at position J is in the Required Action Range which results in the 'A' CCW pump being declared Inoperable.

SRO Admin4 This is a MODIFIED BANK JPM. The bank JPM was used on the 2016 ILT NRC Exam. That JPM has been modified by changing the reason for the dose in excess of the federal limit along with the list of volunteers. Using HDP-ZZ-01450, the applicant will select 1 individual out of 8 choices (different from the 2016 choice) that meets the guidelines and complete section 1 of CA0276, Authorization To Exceed Federal Occupational Dose Limits, correctly per the included key.

SRO Admin5 This is a NEW TIME CRITICAL JPM. At the completion of this JPM, the applicant identified that sector D is also affected and the Evacuation distance changed from Sectors E, F, G 5 miles to D, E, F, and G 10 miles. The applicant also completed 3 sections (outline, method, reason for type of PA) of CA 2843, PAR Flowchart correctly.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Callaway Date of Examination:

8/31/2020 Exam Level: RO SRO-I SRO-U Operating Test Number:

2020-1 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code*

Safety Function Sim1. 024AA2.01 Emergency Boration / Loss of Shutdown Margin in Mode 4 - Emergency Borate from the RWST using 'B' SI Pump N, S, L, A 1

Sim2. 006A4.02 Emergency Core Cooling System / Open EMHV8802A ('A' SI Pump Discharge to Hot Leg Inj) in Mode 1

,2 or 3 EN, N, S 2

Sim3. 010A4.01 Pressurizer Pressure Control System (BB) /

Respond to a Master Pressure Controller Failure D, S, A 3

Sim4. 002A2.03 Reactor Coolant System / Perform ES-0.2, Natural Circulation Cooldown, Steps #7 and 8 to initiate a RCS cooldown N, S, L, A 4P Sim5. 103A4.04 Containment / Perform OTO-SA-00001, Attachment C, Containment Isolation Phase A Recovery EN, N, S 5

Sim6. 062A4.01 AC Electrical Distribution / Transfer 4160 VAC PB122 to transformer XPB123 (PA02 supplied) from XPB122 (PA01 supplied)

N, S, L 6

Sim7. 073A4.03 Process Radiation Monitoring System / Source Check GH-RE-10B per OSP-SP-00001 M, S 7

Sim8. 008A4.01 CCW System / Alternate CCW pumps in a single train then respond to a loss of both pumps and swap CCW service loop to the other CCW train within 10 minutes.

N, S, A 8

In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U RO only SRO-U SRO-U SRO-U

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 P1. 055EK3.02 Loss of Offsite and Onsite Power / Manually load equipment on to an AC Bus A, D, E, P1 6

P2. 061K1.07 Auxiliary Feedwater System / Emergency Makeup Water to CST per EOP Addendum 23 D, E 4S P3. 033A2.03 Spent Fuel Pool Cooling System / Perform Local actions to fill the SFP with Reactor Makeup Water Per OTN-EC-00001 Addendum 6 N, R 8

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for R /SRO-I/SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power/Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6/4-6 /2-3 9/ 8/ 4 1/ 1/ 1 1/ 1/ 1 (control room system) 1/ 1/ 1 2/ 2/ 1 3/ 3/ 2 (randomly selected) 1/ 1/ 1 Note 1: The JPMs from the 2017 exam were randomly selected by placing 11 slips of paper labeled A through K in a container. No JPMs from the 2019 NRC exam were available for random selection as those JPMs will be used as a part of 2020 Audit Exam.

Simulator JPMs S1 This is a NEW ALTERNATE PATH JPM. The applicant will perform actions of OTO-ZZ-00003, Loss of Shutdown Margin, and borate the RCS using the B SI Pump and associated piping. Both CCPs and the flowpath to the A SI pump are not available and/or successful in establishing emergency boration thereby requiring the use of the B SI Pump and associated flowpath.

S2 This is a NEW JPM. The applicant will perform actions of OTN-EM-00001, section 5.11 to open EMHV8802A, SI Pump A Disch To Hot Leg Inj without affecting RWST or RHUT inventory, starting the 'A' Train SI pump nor affecting the lineup (and therefore operability) of the opposite train which would place the plant in a LCO 3.0.3 condition.

SRO-U SRO-U

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 S3 This is an ALTERNATE PATH, BANK JPM. The JPM (URO-SBB-04-C166J(A))

was used on the 2016 ILT NRC Exam. The applicant will be directed to equalize RCS and Pressurizer Boron Concentration using OTG-ZZ-00004, Addendum 03.

When the master pressure controller is taken to AUTO the PZR spray valves fail open requiring the applicant to manually close the spray valves. Upon completion of this JPM, the master pressure controller failure has been addressed prior to a Reactor Trip being generated on low pressurizer pressure.

S4 This is a NEW ALTERNATE PATH JPM. The applicant will perform actions of ES-0.2, Natural Circulation Cooldown, steps 7 & 8. Conditions are such that the applicant will have to perform the RNO actions of both steps, starting 4 CRDM fans and using the more than one SG ASDs (as the applicant must diagnosis that the condenser is unavailable) to establish a cooldown rate without generating a Steam Line SI nor exceed the cooldown rate.

S5 This is a NEW JPM. The applicant will perform actions of OTO-SA-00001, Attachment C, CTMT Isolation Phase A Recovery. The applicant will have to reset the Phase A signal, establish RCP seal water return, restore sample flow to CTMT monitors, restore reactor makeup water, and provide a CTMT sump discharge flowpath.

S6 This is a NEW JPM. The applicant will perform actions of OTN-PB-00001, Addendum 3, Energizing and Cross-tying Buses PB121, PB122, and PB123, to transfer 4160 VAC bus PB122 from its normal supply (PA01 via XPB122) to its alternate supply (PA02 via XPB123) without deenergizing the bus.

S7 This is a MODIFIED BANK JPM. This JPM was developed and submitted for use on the 2017 ILT NRC exam but not used due to the final class makeup (No ROs in 2017). It was modified as the original JPM source checked a different monitor, BM-RE-52. The applicant will perform actions of OSP-SP-00001 and have successfully source checked all three channels of GH-RE-10B (105, 108, 109) by selecting each channel and then depressing the source check button on the RM11 console.

S8 This is a NEW ALTERNATE PATH Time Critical JPM. The applicant will perform actions of OTN-EG-00001 section 5.4 to alternate 'B' Train CCW pumps. After the pump swap, malfunctions occur resulting in a loss of all CCW. The applicant will start either 'A' Train CCW pump (EG HIS 21 or 23 to Start), establish service water to the 'A' CCW HX by opening EF HIS 51&59 and shift CCW loads to the

'A' Train by opening EG HS-15 and closing EG HS-16 10 minutes from the loss of both 'B' Train CCW pumps.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 In Plant JPMs P1 This is an ALTERNATE PATH, BANK JPM. This original JPM was used on the 2017 NRC ILT Exam. This JPM was modified by the addition of NG breaker status cue sheets and by making one step that was previously not critical a critical step (but this was not considered a significant modification and therefore listed as a BANK JPM). Upon completion of this JPM, the applicant will have closed the following breakers thereby loading equipment onto the NB01 bus:

NG0301 for NG03 bus NG0303 for Battery Chargers NK23 NK51-20 for Control Room emergency lighting P2 This is a BANK JPM that has not been used on at least the last 3 initial license exams. The applicant will perform actions of EOP Addendum 23, Local CST Emergency Fill, connecting a fire hose to the CST emergency fill connector on APV0043 and then unlock and open APV0043 and then open a fire hydrant thereby establishing fire water emergency fill to the CST.

P3 This is a NEW JPM. The applicant will enter the RCA and perform actions of OTN-EC-00001, Addendum 6, Filling the Spent Fuel Pool, Step 5.2.6. To initiate SFP makeup, the applicant will fully open ECV0076 and throttling open ECV0128 to achieve a SFP makeup flow of ~65,000 lbm/hr.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility:

Callaway Date of Examination:

8/31/2020 Exam Level: RO SRO-I SRO-U Operating Test Number:

2020-1 Control Room Systems:* 8 for RO, 7 for SRO-I, and 2 or 3 for SRO-U System/JPM Title Type Code*

Safety Function Sim1. 024AA2.01 Emergency Boration / Loss of Shutdown Margin in Mode 4 - Emergency Borate from the RWST using 'B' SI Pump N, S, L, A 1

Sim2. 006A4.02 Emergency Core Cooling System / Open EMHV8802A ('A' SI Pump Discharge to Hot Leg Inj) in Mode 1

,2 or 3 EN, N, S 2

Sim3. 010A4.01 Pressurizer Pressure Control System (BB) /

Respond to a Master Pressure Controller Failure D, S, A 3

Sim4. 002A2.03 Reactor Coolant System / Perform ES-0.2, Natural Circulation Cooldown, Steps #7 and 8 to initiate a RCS cooldown N, S, L, A 4P Sim5. 103A4.04 Containment / Perform OTO-SA-00001, Attachment C, Containment Isolation Phase A Recovery EN, N, S 5

Sim7. 073A4.03 Process Radiation Monitoring System / Source Check BM-RE-52 per OSP-SP-00001 M, S 7

Sim8. 008A4.01 CCW System / Alternate CCW pumps in a single train then respond to a loss of both pumps and swap CCW service loop to the other CCW train within 10 minutes.

N, S, A 8

In-Plant Systems:* 3 for RO, 3 for SRO-I, and 3 or 2 for SRO-U P1. 055EK3.02 Loss of Offsite and Onsite Power / Manually load equipment on to an AC Bus A, D, E, P1 6

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 P2. 061K1.07 Auxiliary Feedwater System / Emergency Makeup Water to CST per EOP Addendum 23 D, E 4S P3. 033A2.03 Spent Fuel Pool Cooling System / Perform Local actions to fill the SFP with Reactor Makeup Water Per OTN-EC-00001 Addendum 6 N, R 8

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions, all five SRO-U systems must serve different safety functions, and in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for R /SRO-I/SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power/Shutdown (N)ew or (M)odified from bank including 1(A)