ML21013A543

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Initial License Exam Forms ES-401-1 and 401-3
ML21013A543
Person / Time
Site: Monticello 
(DPR-022)
Issue date: 11/03/2020
From:
NRC/RGN-III/DRS/OLB
To:
Nuclear Management Co
Zoia C
Shared Package
ML19127A315 List:
References
Download: ML21013A543 (16)
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Text

ES-401 1

Form ES-401-1 Facility: Monticello Nuclear Generating Plant Date of Exam: October 19 - 30, 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

3 3

4 N/A 4

3 N/A 3

20 4

3 7

2 1

1 1

1 2

1 7

1 2

3 Tier Totals 4

4 5

5 5

4 27 5

5 10

2.

Plant Systems 1

2 2

2 3

3 3

2 3

2 2

2 26 3

2 5

2 1

1 2

1 1

1 1

1 1

1 1

12 0

1 2

3 Tier Totals 3

3 4

4 4

4 3

4 3

3 3

38 4

4 8

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

2 3

4 7

3 2

2 3

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. 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-401-1 ES-401 BWR Examination Outline Form ES-401-1 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 295001 (APE 1) Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 01 AK3.01 - Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: Reactor water level response (CFR 41.5 / 45.6) 3.4 1

295003 (APE 3) Partial or Complete Loss of AC Power / 6 03 AA1.03 - Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C. POWER: Systems necessary to assure safe plant shutdown (CFR 41.7 / 45.6) 4.4 2

295004 (APE 4) Partial or Total Loss of DC Power / 6 03 AA2.03 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Battery voltage (CFR 41.10 / 43.5 / 45.13) 2.8 3

295005 (APE 5) Main Turbine Generator Trip /

3 2.4 35 2.4.35 - Knowledge of the local auxiliary operator tasks during an emergency and the resultant operational effects (CFR 41.10 / 43.5. 45.13) 3.8 4

295006 (APE 6) Scram / 1 03 AK1.03 - Knowledge of the operational implications of the following concepts as they apply to SCRAM:

Reactivity control (CFR 41.8 to 10) 3.7 5

295016 (APE 16) Control Room Abandonment

/ 7 02 AK2.02 - Knowledge of the interrelations between CONTROL ROOM ABANDONMENT and the following: Local control room stations: Plant specific (CFR 41.7 / 45.8) 4.0 6

295018 (APE 18) Partial or Complete Loss of CCW / 8 03 AK3.03 - Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Securing individual components (prevent equipment damage) (CFR 41.5 / 45.6) 3.1 7

295019 (APE 19) Partial or Complete Loss of Instrument Air / 8 01 AA1.01 - Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: Backup air supply (CFR 41.7 / 45.6) 3.5 8

295021 (APE 21) Loss of Shutdown Cooling /

4 03 AA2.03 - Ability to determine and/or interpret the following as they apply to LOSS OF SHUTDOWN COOLING: Reactor water level (CFR 41.10 / 43.5 /

45.13) 3.5 9

295023 (APE 23) Refueling Accidents / 8 2.2 22 2.2.22 - Knowledge of limiting conditions for operations and safety limits (CFR 41.5 / 43.2 /

45.2) 4.0 10 295024 High Drywell Pressure / 5 01 EK1.01 - Knowledge of the operational implications of the following concepts as they apply to HIGH DRYWELL PRESSURE: Drywell integrity (CFR 41.8 to 10) 4.1 11 295025 (EPE 2) High Reactor Pressure / 3 10 EK2.10 - Knowledge of the interrelations between HIGH REACTOR PRESSURE and the following:

SPDS: Plant specific (CFR 41.7 / 45.8) 2.9 12 295026 (EPE 3) Suppression Pool High Water Temperature / 5 04 EK3.04 - Knowledge of the reasons for the following responses as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: SBLC injection (CFR 41.5 / 45.6) 3.7 13 295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 Not Applicable 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only) / 5 01 EA1.01 - Ability to operate and/or monitor the following as they apply to HIGH DRYWELL TEMPERATURE: Drywell spray: Mark-I&II (CFR 41.7 / 45.6) 3.8 14

ES-401 3

Form ES-401-1 295030 (EPE 7) Low Suppression Pool Water Level / 5 03 EA2.03 - Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL: Reactor pressure (CFR 41.10 / 43.5 / 45.13) 3.7 15 295031 (EPE 8) Reactor Low Water Level / 2 2.1 19 2.1.19 - Ability to use plant computers to evaluate system or component status (CFR 41.10 / 45.12) 3.9 16 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 06 EK1.06 - Knowledge of the operational implications of the following concepts as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN:

Cooldown effects on reactor power (CFR 41.8 to

10) 4.0 17 295038 (EPE 15) High Offsite Radioactivity Release Rate / 9 04 EK2.04 - Knowledge of the interrelations between HIGH OFF-SITE RELEASE RATE and the following: Stack-gas monitoring system: Plant specific (CFR 41.7 / 45.8) 3.9 18 600000 (APE 24) Plant Fire On Site / 8 04 AK3.04 - Knowledge of the reasons for the following responses as they apply to PLANT FIRE ON SITE: Actions contained in the abnormal procedure for plant fire on site (CFR 41.5 / 45.6) 2.8 19 700000 (APE 25) Generator Voltage and Electric Grid Disturbances / 6 04 AA1.04 - Ability to operate and/or monitor the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Reactor controls (CFR 41.5 and 10 / 45.5, 7, and 8) 4.1 20 K/A Category Totals:

3 3

4 4

3 3 Group Point Total:

20

ES-401 4

Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 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 295002 (APE 2) Loss of Main Condenser Vacuum / 3 04 AA2.04 - Ability to determine and/or interpret the following as they apply to LOSS OF MAIN CONDENSER VACUUM: Offgas system flow (CFR 41.10 / 43.5 / 45.13) 2.8 21 295007 (APE 7) High Reactor Pressure / 3 295008 (APE 8) High Reactor Water Level / 2 2.4 49 2.4.49 - Ability to perform without reference to procedures those actions that require immediate operation of system components and controls (CFR 41.10 / 43.2 / 45.6) 4.6 22 295009 (APE 9) Low Reactor Water Level / 2 03 AK1.03 - Knowledge of the operational implications of the following concepts as they apply to LOW REACTOR WATER LEVEL: Jet pump net positive suction head (CFR 41.8 to 10) 2.7 23 295010 (APE 10) High Drywell Pressure / 5 295011 (APE 11) High Containment Temperature (Mark III Containment only) / 5 Not Applicable 295012 (APE 12) High Drywell Temperature /

5 02 AK2.02 - Knowledge of the interrelations between HIGH DRYWELL TEMPERATURE and the following: Drywell cooling (CFR 41.7 / 45.8) 3.6 24 295013 (APE 13) High Suppression Pool Temperature. / 5 295014 (APE 14) Inadvertent Reactivity Addition / 1 02 AK3.02 - Knowledge of the reasons for the following responses as they apply to INADVERTENT REACTIVITY ADDITION: Control rod blocks (CFR 41.5 / 45.6) 3.7 25 295015 (APE 15) Incomplete Scram / 1 295017 (APE 17) Abnormal Offsite Release Rate / 9 295020 (APE 20) Inadvertent Containment Isolation / 5 & 7 295022 (APE 22) Loss of Control Rod Drive Pumps / 1 295029 (EPE 6) High Suppression Pool Water Level / 5 295032 (EPE 9) High Secondary Containment Area Temperature / 5 295033 (EPE 10) High Secondary Containment Area Radiation Levels / 9 01 EA1.01 - Ability to operate and/or monitor the following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS:

Area radiation monitoring system (CFR 41.7 /

45.6) 3.9 26 295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9 295035 (EPE 12) Secondary Containment High Differential Pressure / 5 295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5 500000 (EPE 16) High Containment Hydrogen Concentration / 5 03 EA2.03 - Ability to determine and/or interpret the following as they apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS: Combustible limits for drywell (CFR 41.10 / 43.5 / 45.13) 3.3 27 K/A Category Point Totals:

1 1

1 1

2 1

Group Point Total:

7

ES-401 5

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

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A 3

A4 G*

K/A Topic(s)

IR 203000 (SF2, SF4 RHR/LPCI)

RHR/LPCI: Injection Mode 03 01 K3.03 (SF4) - Knowledge of the effect that a loss or malfunction of the RHR/LPCI:

INJECTION MODE (PLANT SPECIFIC) will have on the following: Automatic depressurization logic (CFR 41.7 / 45.4)

K4.01 (SF2) - Knowledge of RHR/LPCI:

INJECTION MODE (PLANT SPECIFIC) design feature(s) and/or interlocks which provide for the following: Automatic system initiation/injection (CFR 41.7) 4.2 4.2 28 29 205000 (SF4 SCS) Shutdown Cooling 03 K5.03 - Knowledge of the operational implications of the following concepts as they apply to SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE): Heat removal mechanisms (CFR 41.5 / 45.3) 2.8 30 206000 (SF2, SF4 HPCIS)

High-Pressure Coolant Injection 04 A1.04 (SF4) - Ability to predict and/or monitor changes in parameters associated with operating the HIGH PRESSURE COOLANT INJECTION SYSTEM controls including:

Suppression pool level (CFR 41.5 / 45.5) 3.7 31 207000 (SF4 IC) Isolation (Emergency) Condenser Not Applicable 209001 (SF2, SF4 LPCS)

Low-Pressure Core Spray 05 K6.05 (SF2) - Knowledge of the effect that a loss or malfunction of the following will have on the LOW PRESSURE CORE SPRAY SYSTEM: ECCS room cooler(s) (CFR 41.7 /

45.7) 2.8 32 209002 (SF2, SF4 HPCS)

High-Pressure Core Spray Not Applicable 211000 (SF1 SLCS) Standby Liquid Control 06 A2.06 - Ability to (a) predict the impacts of the following on the STANDBY LIQUID CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Valve openings (CFR 41.5 / 45.6) 3.1 33 212000 (SF7 RPS) Reactor Protection 08 A3.08 - Ability to monitor automatic operations of the REACTOR PROTECTION SYSTEM including: Recirculation pump trip (CFR 41.7 /

45.7) 3.7 34 215003 (SF7 IRM)

Intermediate-Range Monitor 04 A4.04 - Ability to manually operate and/or monitor in the control room: IRM back panel switches, meters, and indicating lights (CFR 41.7 / 45.5 to 8) 3.1 35 215004 (SF7 SRMS) Source-Range Monitor 01 2.4 21 K4.01 - Knowledge of SOURCE-RANGE MONITOR (SRM) SYSTEM design feature(s) and/or interlocks which provide for the following: Rod withdrawal blocks (CFR 41.7) 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) 3.7 4.0 36 37 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor 01 K1.01 - Knowledge of the physical connections and/or cause-effect relationships between AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM and the following: RPS (CFR 41.2 to 9 / 45.7 to 8) 4.0 38

ES-401 6

Form ES-401-1 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling 01 K2.01 (SF2) - Knowledge of electrical power supplies to the following: Motor operated valves (CFR 41.7) 2.8 39 218000 (SF3 ADS) Automatic Depressurization 01 K3.01 - Knowledge of the effect that a loss or malfunction of the AUTOMATIC DEPPRESURIZATION SYSTEM will have on the following: Restoration of reactor water level after a break that does not depressurize the reactor when required (CFR 41.7 / 45.4) 4.4 40 223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff 07 K4.07 - Knowledge of PRIMARY CONTAINMENT ISOLATION/NUCLEAR STEAM SUPPLY SHUTOFF design feature(s) and/or interlocks which provide for the following: Physical separation of system components (to prevent localized environmental factors, electrical faults, and physical events from impairing system response) (CFR 41.7) 2.8 41 239002 (SF3 SRV) Safety Relief Valves 04 04 K5.04 - Knowledge of the operational implications of the following concepts as they apply to RELIEF/SAFETY VALVES: Tail pipe temperature monitoring (CFR 41.5 / 45.3)

K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the RELIEF/SAFETY VALVES: DC power: Plant specific (CFR 41.7 / 45.7) 3.3 3.0 42 43 259002 (SF2 RWLCS) Reactor Water Level Control 03 K6.03 - Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR WATER LEVEL CONTROL SYSTEM: Main Steam flow input (CFR 41.7 /

45.7) 3.1 44 261000 (SF9 SGTS) Standby Gas Treatment 04 A1.04 - Ability to predict and/or monitor changes in parameters associated with operating the STANDBY GAS TREATMENT SYSTEM controls including: Secondary containment differential pressure (CFR 41.5 /

45.5) 3.0 45 262001 (SF6 AC) AC Electrical Distribution 01 07 K5.01 - Knowledge of the operational implications of the following concepts as they apply to A.C. ELCTRICAL DISTRIBUTION:

Principle involved with paralleling two A.C.

sources (CFR 41.5 / 45.3)

A2.07 - Ability to (a) predict the impacts of the following on the A.C. ELCTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Energizing a dead bus (CFR 41.5 / 45.6) 3.1 3.0 46 47 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC) 01 A3.01 - Ability to monitor automatic operations of the UNINTERRUPTABLE POWER SUPPLY (AC/DC) including: Transfer from preferred to alternate source (CFR 41.7 / 45.7) 2.8 48 263000 (SF6 DC) DC Electrical Distribution 02 A4.02 - Ability to manually operate and/or monitor in the control room: Battery voltage indicator: Plant specific (CFR 41.7 / 45.5 to 8) 3.2 49 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG 2.2 36 2.2.36 - Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations (CFR 41.10 / 43.2 /

45.13) 3.1 50

ES-401 7

Form ES-401-1 300000 (SF8 IA) Instrument Air 03 01 K1.03 - Knowledge of the physical connections and/or cause-effect relationships between INSTRUMENT AIR SYSTEM and the following: Containment air (CFR 41.2 to 9 /

45.7 to 8)

A2.01 - Ability to (a) predict the impacts of the following on the INSTRUMENT AIR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Air dryer and filter malfunctions (CFR 41.5 / 45.6) 2.8 2.9 51 52 400000 (SF8 CCS) Component Cooling Water 01 K2.01 - Knowledge of electrical power supplies to the following: CCW pumps (CFR 41.7) 2.9 53 510000 (SF4 SWS*) Service Water (Normal and Emergency)

Not Applicable K/A Category Point Totals:

2 2

2 3

3 3

2 3

2 2

2 Group Point Total:

26

ES-401 8

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

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR 201001 (SF1 CRDH) CRD Hydraulic 201002 (SF1 RMCS) Reactor Manual Control 01 K3.01 - Knowledge of the effect that a loss or malfunction of the REACTOR MANUAL CONTROL SYSTEM will have on the following:

Ability to move control rods (CFR 41.7 / 45.4) 3.4 54 201003 (SF1 CRDM) Control Rod and Drive Mechanism 201004 (SF7 RSCS) Rod Sequence Control 201005 (SF1, SF7 RCIS) Rod Control and Information 201006 (SF7 RWMS) Rod Worth Minimizer 202001 (SF1, SF4 RS) Recirculation 16 K4.16 (SF4) - Knowledge of RECIRCULATION SYSTEM design feature(s) and/or interlocks which provide for the following:

Recirculation pump downshift/runback: Plant-Specific (CFR 41.7) 3.3 55 202002 (SF1 RSCTL) Recirculation Flow Control 204000 (SF2 RWCU) Reactor Water Cleanup 07 K5.07 - Knowledge of the operational implications of the following concepts as they apply to REACTOR WATER CLEANUP SYSTEM: Conductivity measurement (CFR 41.5 / 45.3) 2.5 56 214000 (SF7 RPIS) Rod Position Information 215001 (SF7 TIP) Traversing In-Core Probe 04 K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the TRAVERSING IN-CORE PROBE: Primary containment isolation system (CFR 41.7 / 45.7) 3.1 57 215002 (SF7 RBMS) Rod Block Monitor 216000 (SF7 NBI) Nuclear Boiler Instrumentation 03 A1.03 - Ability to predict and/or monitor changes in parameters associated with operating the NUCLEAR BOILER INSTRUMENTATION controls including: Surveillance testing (CFR 41.5 / 45.5) 2.9 58 219000 (SF5 RHR SPC) RHR/LPCI:

Torus/Suppression Pool Cooling Mode 223001 (SF5 PCS) Primary Containment and Auxiliaries 09 A2.09 - Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT SYSTEM AND AUXILIARIES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Vacuum breaker malfunction (CFR 41.5 / 45.6) 3.4 59 226001 (SF5 RHR CSS) RHR/LPCI:

Containment Spray Mode

ES-401 9

Form ES-401-1 230000 (SF5 RHR SPS) RHR/LPCI:

Torus/Suppression Pool Spray Mode 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup 02 A3.02 - Ability to monitor automatic operations of the FUEL POOL COOLING AND CLEAN-UP including: Pump trip(s) (CFR 41.7 /

45.7) 2.6 60 234000 (SF8 FH) Fuel-Handling Equipment 239001 (SF3, SF4 MRSS) Main and Reheat Steam 10 A4.10 (SF3) - Ability to manually operate and/or monitor in the control room: Reactor power (CFR 41.7 /

45.5 to 8) 3.8 61 239003 (SF9 MSVLCS) Main Steam Isolation Valve Leakage Control 241000 (SF3 RTPRS) Reactor/Turbine Pressure Regulating 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 256000 (SF2 CDS) Condensate 259001 (SF2 FWS) Feedwater 2.1 25 2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc. (CFR 41.10 / 43.5 /

45.12) 3.9 62 268000 (SF9 RW) Radwaste 271000 (SF9 OG) Offgas 272000 (SF7, SF9 RMS) Radiation Monitoring 286000 (SF8 FPS) Fire Protection 03 K2.03 - Knowledge of electrical power supplies to the following: Fire detection system (CFR 41.7) 2.5 63 288000 (SF9 PVS) Plant Ventilation 02 K1.02 - Knowledge of the physical connections and/or cause-effect relationships between PLANT VENTILATION SYSTEMS and the following: Secondary Containment (CFR 41.2 to 9 / 45.7 to 8) 3.4 64 290001 (SF5 SC) Secondary Containment 290003 (SF9 CRV) Control Room Ventilation 04 K3.04 - Knowledge of the effect that a loss or malfunction of the CONTROL ROOM HVAC will have on the following: Control room pressure (CFR 41.7 / 45.6) 2.8 65 290002 (SF5 RVI) Reactor Vessel Internals 51001 (SF8 CWS*) Circulating Water Not Applicable K/A Category Point Totals:

1 1

2 1

1 1

1 1

1 1

1 Group Point Total:

12

ES-401 10 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 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 295001 (APE 1) Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 295003 (APE 3) Partial or Complete Loss of AC Power / 6 295004 (APE 4) Partial or Total Loss of DC Power / 6 295005 (APE 5) Main Turbine Generator Trip /

3 05 AA2.05 - Ability to determine and/or interpret the following as they apply to MAIN TURBINE GENERATOR TRIP: Reactor power (CFR 41.10 /

43.5 / 45.13) 3.9 76 295006 (APE 6) Scram / 1 295016 (APE 16) Control Room Abandonment

/ 7 2.1 20 2.1.20 - Ability to interpret and execute procedure steps (CFR 41.10 / 43.5 / 45.12) 4.6 77 295018 (APE 18) Partial or Complete Loss of CCW / 8 295019 (APE 19) Partial or Complete Loss of Instrument Air / 8 295021 (APE 21) Loss of Shutdown Cooling /

4 295023 (APE 23) Refueling Accidents / 8 01 AA2.01 - Ability to determine and/or interpret the following as they apply to REFUELING ACCIDENTS: Area radiation levels (CFR 41.10 /

43.5 / 45.13) 4.0 78 295024 High Drywell Pressure / 5 295025 (EPE 2) High Reactor Pressure / 3 295026 (EPE 3) Suppression Pool High Water Temperature / 5 295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 Not Applicable 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only) / 5 2.4 6

2.4.6 - Knowledge of EOP mitigation strategies (CFR 41.10 / 43.5 / 45.13) 4.7 79 295030 (EPE 7) Low Suppression Pool Water Level / 5 02 EA2.02 - Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL: Suppression pool temperature (CFR 41.10 / 43.5 / 45.13) 3.9 80 295031 (EPE 8) Reactor Low Water Level / 2 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 2.4 2

2.4.2 - Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions (CFR 41.7 / 45.7 and 8) 4.6 81 295038 (EPE 15) High Offsite Radioactivity Release Rate / 9 600000 (APE 24) Plant Fire On Site / 8 16 AA2.16 - Ability to determine and/or interpret the following as they apply to PLANT FIRE ON SITE:

Vital equipment and control systems to be maintained and operated during a fire (CFR 41.10 /

43.5 / 45.13) 3.5 82 700000 (APE 25) Generator Voltage and Electric Grid Disturbances / 6 K/A Category Totals:

4 3

Group Point Total:

7

ES-401 11 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 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 295002 (APE 2) Loss of Main Condenser Vacuum / 3 295007 (APE 7) High Reactor Pressure / 3 295008 (APE 8) High Reactor Water Level / 2 295009 (APE 9) Low Reactor Water Level / 2 295010 (APE 10) High Drywell Pressure / 5 295011 (APE 11) High Containment Temperature (Mark III Containment only) / 5 Not Applicable 295012 (APE 12) High Drywell Temperature /

5 295013 (APE 13) High Suppression Pool Temperature. / 5 2.2 44 2.2.44 - Ability to interpret control room indications to verify status and operation of a system, and understand how operator actions and directives affect plant and system conditions (CFR 41.5 / 43.5 / 45.12) 4.4 83 295014 (APE 14) Inadvertent Reactivity Addition / 1 295015 (APE 15) Incomplete Scram / 1 295017 (APE 17) Abnormal Offsite Release Rate / 9 04 AA2.04 - Ability to determine and/or interpret the following as they apply to HIGH OFF-SITE RELEASE RATE: Source of off-site release (CFR 41.10 / 43.5 / 45.13) 4.3 84 295020 (APE 20) Inadvertent Containment Isolation / 5 & 7 295022 (APE 22) Loss of Control Rod Drive Pumps / 1 2.1 32 2.1.32 - Ability to explain and apply system limits and precautions (CFR 41.10 / 43.2 / 45.12) 4.0 85 295029 (EPE 6) High Suppression Pool Water Level / 5 295032 (EPE 9) High Secondary Containment Area Temperature / 5 295033 (EPE 10) High Secondary Containment Area Radiation Levels / 9 295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9 295035 (EPE 12) Secondary Containment High Differential Pressure / 5 295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5 500000 (EPE 16) High Containment Hydrogen Concentration / 5 K/A Category Point Totals:

1 2

Group Point Total:

3

ES-401 12 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 1 (SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR 203000 (SF2, SF4 RHR/LPCI)

RHR/LPCI: Injection Mode 205000 (SF4 SCS) Shutdown Cooling 206000 (SF2, SF4 HPCIS)

High-Pressure Coolant Injection 207000 (SF4 IC) Isolation (Emergency) Condenser Not Applicable 209001 (SF2, SF4 LPCS)

Low-Pressure Core Spray 209002 (SF2, SF4 HPCS)

High-Pressure Core Spray Not Applicable 211000 (SF1 SLCS) Standby Liquid Control 212000 (SF7 RPS) Reactor Protection 215003 (SF7 IRM)

Intermediate-Range Monitor 215004 (SF7 SRMS) Source-Range Monitor 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling 16 A2.16 (SF4) - Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low condensate storage tank level (CFR 41.5 / 45.6) 3.4 86 218000 (SF3 ADS) Automatic Depressurization 2.4 50 2.4.50 - Ability to verify system alarm setpoints and operate controls identified in the alarm response manual (CFR 41.10 / 43.5 / 45.3) 4.0 87 223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff 03 A2.03 - Ability to (a) predict the impacts of the following on the PRIMARY CONTAINMENT ISOLATION / NUCLEAR STEAM SUPPLY SHUT-OFF; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System logic failures (CFR 41.5 / 45.6) 3.3 88 239002 (SF3 SRV) Safety Relief Valves 259002 (SF2 RWLCS) Reactor Water Level Control 261000 (SF9 SGTS) Standby Gas Treatment 2.2 25 2.2.25 - Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits (CFR 41.5 and 7 /

43.2) 4.2 89 262001 (SF6 AC) AC Electrical Distribution 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC) 263000 (SF6 DC) DC Electrical Distribution

ES-401 13 Form ES-401-1 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG 02 A2.02 - Ability to (a) predict the impacts of the following on the EMERGENCY GENERATORS (DIESEL/JET); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Unloading prior to securing emergency generator (CFR 41.5 / 45.6) 3.1 90 300000 (SF8 IA) Instrument Air 400000 (SF8 CCS) Component Cooling Water 510000 (SF4 SWS*) Service Water (Normal and Emergency)

Not Applicable K/A Category Point Totals:

3 2 Group Point Total:

5

ES-401 14 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 2 (SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

K/A Topic(s)

IR 201001 (SF1 CRDH) CRD Hydraulic 201002 (SF1 RMCS) Reactor Manual Control 201003 (SF1 CRDM) Control Rod and Drive Mechanism 2.1 7

2.1.7 - Ability to evaluate plant performance and make operational judgements based on operating characteristics, reactor behavior, and instrument interpretation (CFR 41.5 /

43.5 / 45.12 and 13) 4.7 91 201004 (SF7 RSCS) Rod Sequence Control 201005 (SF1, SF7 RCIS) Rod Control and Information 201006 (SF7 RWMS) Rod Worth Minimizer 202001 (SF1, SF4 RS) Recirculation 202002 (SF1 RSCTL) Recirculation Flow Control 204000 (SF2 RWCU) Reactor Water Cleanup 214000 (SF7 RPIS) Rod Position Information 215001 (SF7 TIP) Traversing In-Core Probe 215002 (SF7 RBMS) Rod Block Monitor 216000 (SF7 NBI) Nuclear Boiler Instrumentation 219000 (SF5 RHR SPC) RHR/LPCI:

Torus/Suppression Pool Cooling Mode 223001 (SF5 PCS) Primary Containment and Auxiliaries 226001 (SF5 RHR CSS) RHR/LPCI: Containment Spray Mode 230000 (SF5 RHR SPS) RHR/LPCI:

Torus/Suppression Pool Spray Mode 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup 234000 (SF8 FH) Fuel-Handling Equipment 239001 (SF3, SF4 MRSS) Main and Reheat Steam 239003 (SF9 MSVLCS) Main Steam Isolation Valve Leakage Control 241000 (SF3 RTPRS) Reactor/Turbine Pressure Regulating 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 256000 (SF2 CDS) Condensate 259001 (SF2 FWS) Feedwater 268000 (SF9 RW) Radwaste 01 A2.01 - Ability to (a) predict the impacts of the following on the RADWASTE; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System rupture (CFR 41.5

/ 45.6) 3.5 92 271000 (SF9 OG) Offgas 272000 (SF7, SF9 RMS) Radiation Monitoring 286000 (SF8 FPS) Fire Protection 2.1 23 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 and 6) 4.4 93

ES-401 15 Form ES-401-1 288000 (SF9 PVS) Plant Ventilation 290001 (SF5 SC) Secondary Containment 290003 (SF9 CRV) Control Room Ventilation 290002 (SF4 RVI) Reactor Vessel Internals 51001 (SF8 CWS*) Circulating Water Not Applicable K/A Category Point Totals:

1 2 Group Point Total:

3

ES-401 16 Form ES-401-3 Facility: Monticello Nuclear Generating Plant Date of Exam: October 19 - 30, 2020 Category K/A #

Topic RO SRO-only IR IR

1. Conduct of Operations 2.1.1 Knowledge of conduct of operations requirements (CFR 41.10 / 45.13) 3.8 66 2.1.2 Knowledge of operator responsibilities during all modes of plant operation (41.10 / 45.13) 4.1 67 2.1.3 Knowledge of shift or short-term relief turnover practices (CFR 41.10 / 45.13) 3.7 68 2.1.6 Ability to manage the control room crew during plant transients (CFR 41.10 / 43.5 / 45.12 and 13) 4.8 94 2.1.45 Ability to identify and interpret diverse indications to validate response of another indication (CFR 41.7 / 43.5

/ 45.4) 4.3 95 Subtotal 3

2

2. Equipment Control 2.2.6 Knowledge of the process for making changes to procedures (CFR 41.10 / 43.3 / 45.13) 3.0 69 2.2.15 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc. (CFR 41.10 /

43.3 / 45.13) 3.9 70 2.2.7 Knowledge of the process for conducting special or infrequent tests (CFR 41.10 / 43.3 / 45.13) 3.6 96 2.2.18 Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.(CFR 41.10 / 43.5 /

45.13) 3.9 97 Subtotal 2

2

3. Radiation Control 2.3.7 Ability to comply with radiation work permit requirements during normal or abnormal conditions (CFR 41.12 /

45.10) 3.5 71 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR 41.12 / 43.4 / 45.9 and 10) 3.4 72 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions (CFR 41.12 / 43.4 / 45.10) 3.7 98 Subtotal 2

1

4. Emergency Procedures/Plan 2.4.31 Knowledge of annunciator alarms, indications, or response procedures (CFR 41.10 / 45.3) 4.2 73 2.4.43 Knowledge of emergency communications systems and techniques (CFR 41.10 / 45.13) 3.2 74 2.4.45 Ability to prioritize and interpret the significance of each annunciator or alarm (CFR 41.10 / 43.5 / 45.3 and 12) 4.1 75 2.4.22 Knowledge of the bases for prioritizing safety functions during abnormal/emergency operations (CFR 41.7 and 10 / 43.5 / 45.12) 4.4 99 2.4.44 Knowledge of emergency plan protective action recommendations (CFR 41.10 and 12 / 43.5 / 45.11) 4.4 100 Subtotal 3

2 Tier 3 Point Total 10 7

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