Text

RB-2021-02 Draft Outlines
	ML21096A024
Person / Time
Site:	River Bend
Issue date:	02/19/2021
From:	Greg Werner; Operations Branch IV
To:	; Entergy Operations
References
	Download: ML21096A024 (42)
	v • d • e

ES-401 1 Form ES-401-1 Facility: River Bend Station RO Exam Date of Exam: 2-8-2021 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. 1 3 4 4 3 3 3 20 7 Emergency and N/A N/A 2 2 1 1 1 1 1 7 3 Abnormal Plant Evolutions Tier Totals 5 5 5 4 4 4 27 10 1 3 2 3 2 2 2 2 3 2 2 3 26 5 2.

Plant 2 1 1 1 1 1 1 1 1 2 1 1 12 3 Systems Tier Totals 4 3 4 3 3 3 3 4 4 3 4 38 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 2 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points, and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the outline. Systems or evolutions that do not apply at the facility should be deleted with justification. Operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

4. Select topics from as many systems and evolutions as possible. Sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher. 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 #

Knowledge of the interrelations between 295001 (APE 1) Partial or Complete Loss of X PARTIAL OR COMPLETE LOSS OF 3.8 39 Forced Core Flow Circulation / 1 & 4 FORCED CORE FLOW CIRCULATION and the following:

(CFR: 41.7 / 45.8)

AK2.06 Reactor Power Ability to determine and/or interpret the 295003 (APE 3) Partial or Complete Loss of X following as they apply to PARTIAL OR 3.4 40 AC Power / 6 COMPLETE LOSS OF A.C. POWER :

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Cause of partial or complete loss of A.C. power Knowledge of the operational 295004 (APE 4) Partial or Total Loss of DC X implications of the following concepts as 3.3 41 Power / 6 they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER :

(CFR: 41.8 to 41.10)

AK1.05 Loss of breaker protection G2.2.40 Ability to apply Technical 295005 (APE 5) Main Turbine Generator Trip / X Specifications for a system. l 3.4 42 3

(CFR: 41.10 / 43.2 / 43.5 / 45.3)

Knowledge of the reasons for the 295006 (APE 6) Scram / 1 X following responses as they apply to 4.1 43 SCRAM:

(CFR: 41.5 / 45.6)

AK3.02 Reactor power response G2.4.21 Knowledge of the parameters 295016 (APE 16) Control Room Abandonment X and logic used to assess the status of 4.0 44

/7 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)

Ability to operate and/or monitor the 295018 (APE 18) Partial or Complete Loss of X following as they apply to PARTIAL OR 3.3 45 CCW / 8 COMPLETE LOSS OF COMPONENT COOLING WATER:

(CFR: 41.7 / 45.6)

AA1.02 System loads Knowledge of the interrelations between 295019 (APE 19) Partial or Complete Loss of X PARTIAL OR COMPLETE LOSS OF 3.4 46 Instrument Air / 8 INSTRUMENT AIR and the following:

(CFR: 41.7 / 45.8)

AK2.05 Main Steam System Ability to operate and/or monitor the 295021 (APE 21) Loss of Shutdown Cooling / X following as they apply to LOSS OF 2.8 47 4 SHUTDOWN COOLING:

(CFR: 41.7 / 45.6)

AA1.06 Containment/ drywell temperature

ES-401 3 Form ES-401-1 Ability to determine and/or interpret the 295023 (APE 23) Refueling Accidents / 8 X following as they apply to REFUELING 3.6 48 ACCIDENTS:

(CFR: 41.10 / 43.5 / 45.13)

AA2.01 Area radiation levels Knowledge of the interrelations between 295024 High Drywell Pressure / 5 X HIGH DRYWELL PRESSURE and the 3.0 49 following:

(CFR: 41.7 / 45.8)

EK2.17 Auxiliary building isolation logic:

Plant-Specific Knowledge of the reasons for the 295025 (EPE 2) High Reactor Pressure / 3 X following responses as they apply to 3.9 50 HIGH REACTOR PRESSURE:

(CFR: 41.5 / 45.6)

EK3.09 Low-low set initiation Knowledge of the operational 295026 (EPE 3) Suppression Pool High Water X implications of the following concepts as 3.5 51 Temperature / 5 they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE:

(CFR: 41.8 to 41.10)

EK1.02 Steam condensation Ability to operate and/or monitor the 295027 (EPE 4) High Containment X following as they apply to HIGH 3.5 52 Temperature (Mark III Containment Only) / 5 CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY) :

(CFR: 41.7 / 45.6)

EA1.03 Emergency Depressurization Mark III 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only) / 5 Knowledge of the interrelations between 295030 (EPE 7) Low Suppression Pool Water X LOW SUPPRESSION POOL WATER 3.5 53 Level / 5 LEVEL and the following:

(CFR: 41.7 / 45.8)

EK2.07 Downcomer/ horizontal vent submergence Knowledge of the operational 295031 (EPE 8) Reactor Low Water Level / 2 X implications of the following concepts as 3.8 54 they apply to REACTOR LOW WATER LEVEL:

(CFR: 41.8 to 41.10)

EK1.02 Natural circulation Knowledge of the reasons for the 295037 (EPE 14) Scram Condition Present X following responses as they apply to 4.3 55 and Reactor Power Above APRM Downscale SCRAM CONDITION PRESENT AND or Unknown / 1 REACTO POWER ABOVE APRM DOWNSCALE OR UNKNOWN :

(CFR: 41.5 / 45.6)

EK3.02 SBLC injection

ES-401 4 Form ES-401-1 Knowledge of the interrelations between 295038 (EPE 15) High Offsite Radioactivity X HIGH OFF-SITE 3.1 56 Release Rate / 9 RELEASE RATE and the following:

(CFR: 41.7 / 45.8)

EK2.01 Radwaste G2.4.49 Ability to perform without 600000 (APE 24) Plant Fire On Site / 8 X reference to procedures those actions 4.6 57 that require immediate operation of system components and controls.

(CFR: 41.10 / 43.2 / 45.6)

Ability to determine and/or interpret the 700000 (APE 25) Generator Voltage and X following as they apply to GENERATOR 3.6 58 Electric Grid Disturbances / 6 VOLTAGE AND ELECTRIC GRID DISTURBANCES:

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

AA2.04 VARs outside capability curve K/A Category Totals: 3 4 4 3 3 3 Group Point Total: 20

ES-401 5 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 G2.1.30 Ability to locate and operate 295007 (APE 7) High Reactor Pressure / 3 X components, including local controls. 4.4 59 (CFR: 41.7 / 45.7) 295008 (APE 8) High Reactor Water Level / 2 295009 (APE 9) Low Reactor Water Level / 2 Ability to operate and/or monitor the 295010 (APE 10) High Drywell Pressure / 5 X following as they apply to HIGH 3.6 60 DRYWELL PRESSURE :

(CFR: 41.7 / 45.6)

AA1.02 Drywell floor and equipment drain sumps 295011 (APE 11) High Containment Temperature (Mark III Containment only) / 5 Knowledge of the reasons for the 295012 (APE 12) High Drywell Temperature / X following responses as they apply to 3.5 61 5 HIGH DRYWELL TEMPERATURE :

(CFR: 41.5 / 45.6)

AK3.01 Increased drywell cooling Knowledge of the operational 295013 (APE 13) High Suppression Pool X implications of the following concepts 2.5 62 Temperature. / 5 as they apply to HIGH SUPPRESSION POOL TEMPERATURE:

(CFR: 41.8 to 41.10)

AK1.01 Pool stratification 295014 (APE 14) Inadvertent Reactivity Addition / 1 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 Ability to determine and/or interpret the 295029 (EPE 6) High Suppression Pool Water X following as they apply to HIGH 3.5 63 Level / 5 SUPPRESSION POOL WATER LEVEL:

(CFR: 41.10 / 43.5 / 45.13)

EA2.02 Reactor pressure 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

ES-401 6 Form ES-401-1 Knowledge of the operational 295035 (EPE 12) Secondary Containment X implications of the following concepts 3.9 64 High Differential Pressure / 5 as they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE:

(CFR: 41.8 to 41.10)

EK1.01 Secondary containment integrity 295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5 Knowledge of the interrelations 500000 (EPE 16) High Containment Hydrogen X between HIGH CONTAINMENT 2.7 65 Concentration / 5 HYDROGEN CONCENTRATIONS the following:

(CFR: 41.7 / 45.8)

EK2.04 Drywell recirculating fan K/A Category Point Totals: 2 1 1 1 1 1 Group Point Total: 7

ES-401 7 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 A3 A4 G* K/A Topic(s) IR #

203000 (SF2, SF4 RHR/LPCI) X Ability to (a) predict the impacts of the 3.2 1 RHR/LPCI: Injection Mode following on the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.03 Valve closures 205000 (SF4 SCS) Shutdown Cooling X Knowledge of the effect that a loss or 2.7 2 malfunction of the following will have on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE):

(CFR: 41.7 / 45.7)

K6.02 D.C. electrical power 205000 (SF4 SCS) Shutdown Cooling X Ability to manually operate and/or monitor 3.8 3 in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.06 Reactor water level 206000 (SF2, SF4 HPCIS)

High-Pressure Coolant Injection 207000 (SF4 IC) Isolation (Emergency) Condenser 209001 (SF2, SF4 LPCS) X G2.4.4 Ability to recognize abnormal 4.5 4 Low-Pressure Core Spray indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

(CFR: 41.10 / 43.2 / 45.6) 209002 (SF2, SF4 HPCS) X Knowledge of the operational implications 2.6 5 High-Pressure Core Spray of the following concepts as they apply to HIGH PRESSURE CORE SPRAY SYSTEM (HPCS):

(CFR: 41.5 / 45.3)

K5.02 Heat removal (transfer) mechanism:

BWR-5,6 209002 (SF2, SF4 HPCS) X Ability to predict and/or monitor changes 3.6 6 High-Pressure Core Spray in parameters associated with operating the HIGH-PRESSURE CORE SPRAY SYSTEM (HPCS) controls including:

(CFR: 41.5 / 45.5)

A1.01 HPCS flow: BWR-5,6 211000 (SF1 SLCS) Standby Liquid X Knowledge of the effect that a loss or 3.2 7 Control malfunction of the following will have on the STANDBY LIQUID CONTROL SYSTEM:

(CFR: 41.7 / 45.7)

K6.03 A.C Power

ES-401 8 Form ES-401-1 211000 (SF1 SLCS) Standby Liquid X G2.1.20 Ability to interpret and execute 4.6 8 Control procedure steps.

(CFR: 41.10 / 43.5 / 45.12) 212000 (SF7 RPS) Reactor Protection X Knowledge of the effect that a loss or 3.0 9 malfunction of the REACTOR PROTECTION SYSTEM will have on following:

(CFR: 41.7 / 45.4)

K3.11 Recirculation system 212000 (SF7 RPS) Reactor Protection X Ability to monitor automatic operations of 4.2 10 the REACTOR PROTECTION SYSTEM including:

(CFR: 41.7 / 45.7)

A3.06 Main turbine trip 215003 (SF7 IRM) X Knowledge of the physical connections 3.0 11 Intermediate-Range Monitor and/or cause-effect relationships between INTERMEDIATE RANGE MONITOR (IRM) SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.07 Reactor vessel 215004 (SF7 SRMS) Source-Range X Knowledge of SOURCE RANGE MONITOR 3.7 12 Monitor (SRM) SYSTEM design feature(s) and/or interlocks which provide for the following:

(CFR: 41.7)

K4.01 Rod withdrawal blocks 215005 (SF7 PRMS) Average Power X Ability to monitor automatic operations of 3.2 13 Range Monitor/Local Power Range the AVERAGE POWER RANGE MONITOR/LOCAL Monitor POWER RANGE MONITOR SYSTEM including:

(CFR: 41.7 / 45.7)

A3.04 Annunciator and alarm signals 217000 (SF2, SF4 RCIC) Reactor X Knowledge of the effect that a loss or 3.7 14 Core Isolation Cooling malfunction of the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) will have on following:

(CFR: 41.7 / 45.4)

K3.01 Reactor water level 218000 (SF3 ADS) Automatic X Ability to monitor automatic operations of 4.2 15 Depressurization the AUTOMATIC DEPRESSURIZATION SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 ADS valve operation

ES-401 9 Form ES-401-1 223002 (SF5 PCIS) Primary X Ability to predict and/or monitor changes 3.5 16 Containment Isolation/Nuclear Steam in parameters associated with operating the PRIMARY Supply Shutoff CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF controls including:

(CFR: 41.5 / 45.5)

A1.01 System indicating lights and alarms 239002 (SF3 SRV) Safety Relief X Ability to (a) predict the impacts of the 3.0 17 Valves following on the PRIMARY CONTAINMENT ISOLATION SYSTEM/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:

(CFR: 41.5 / 45.6)

A2.01 Stuck open vacuum breakers 259002 (SF2 RWLCS) Reactor Water X Knowledge of the physical connections 3.8 18 Level Control and/or cause effect relationships between REACTOR WATER LEVEL CONTROL SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.03 Reactor Water Level 261000 (SF9 SGTS) Standby Gas X Ability to (a) predict the impacts of the 2.7 19 Treatment following on the STANDBY GAS TREATMENT SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.07 A.C. electrical failure 262001 (SF6 AC) AC Electrical X Knowledge of the operational implications 3.1 20 Distribution of the following concepts as they apply to A.C. ELECTRICAL DISTRIBUTION:

(CFR: 41.5 / 45.3)

K5.01 Principle involved with paralleling two A.C. sources 262002 (SF6 UPS) Uninterruptable X Knowledge of the effect that a loss or 3.1 21 Power Supply (AC/DC) malfunction of the UNINTERRUPTABLE POWER SUPPLY (A.C./D.C.) will have on following:

(CFR: 41.7 / 45.4)

K3.01 Water Level COntrol: Plant-Specific 263000 (SF6 DC) DC Electrical X Knowledge of electrical power supplies to 3.1 22 Distribution the following:

(CFR: 41.7)

K2.01 Major D.C. loads

ES-401 10 Form ES-401-1 264000 (SF6 EGE) Emergency X Knowledge of the physical connections 3.2 23 Generators (Diesel/Jet) EDG and/or cause effect relationships between EMERGENCY GENERATORS (DIESEL/JET) and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.05 Emergency generator fuel oil supply system 264000 (SF6 EGE) Emergency X G2.4.9 Knowledge of low power/shutdown 3.8 24 Generators (Diesel/Jet) EDG implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

(CFR: 41.10 / 43.5 / 45.13) 300000 (SF8 IA) Instrument Air X Knowledge of electrical power supplies to 2.8 25 the following:

(CFR: 41.7)

K2.01 Instrument air compressor 400000 (SF8 CCS) Component X Knowledge of CCWS design feature(s) and 3.4 26 Cooling Water or interlocks which provide for the following:

(CFR: 41.7)

K4.01 Automatic start of standby pump 510000 (SF4 SWS*) Service Water (Normal and Emergency)

K/A Category Point Totals: 3 2 3 2 2 2 2 3 2 2 3 Group Point Total: 26

ES-401 11 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 201003 (SF1 CRDM) Control Rod and Drive X

Knowledge of the operational 3.3 27 Mechanism implications of the following concepts as they apply to CONTROL ROD AND DRIVE MECHANISM:

(CFR: 41.5 / 45.3)

K5.07 How control rod movements affect core reactivity 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 X

Knowledge of 2.9 28 RECIRCULATION System design feature(s) and/or interlocks which provide for the following:

(CFR: 41.7)

K4.05 Seal cooling 202002 (SF1 RSCTL) Recirculation Flow Control X

Ability to monitor automatic 3.6 29 operations of the RECIRCULATION FLOW CONTROL SYSTEM including:

(CFR: 41.7 / 45.7)

A3.01 Flow control valve operation: BWR-5,6 204000 (SF2 RWCU) Reactor Water Cleanup X

Knowledge of the effect that a 3.5 30 loss or malfunction of the following will have on the REACTOR WATER CLEANUP SYSTEM:

(CFR: 41.7 / 45.7)

K6.08 PCIS/NSSSS 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 X

Ability to predict and/or 2.9 31 monitor changes in parameters associated with operating the NUCLEAR BOILER INSTRUMENTATION controls including:

(CFR: 41.5 / 45.5)

A1.03 Surveillance testing 219000 (SF5 RHR SPC) RHR/LPCI:

Torus/Suppression Pool Cooling Mode

ES-401 12 Form ES-401-1 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 X

Ability to (a) predict the 3.3 32 impacts of the following on the FUEL HANDLING EQUIPMENT; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.01 Interlock failure 239001 (SF3, SF4 MRSS) Main and Reheat Steam X

Ability to manually operate 3.8 33 and/or monitor in the control room:

(CFR: 41.7 / 45.5 to 45.8)

A4.04 System pressure 239003 (SF9 MSVLCS) Main Steam Isolation Valve X

Ability to monitor automatic 2.6 34 Leakage Control operations of the MSIV LEAKAGE CONTROL SYSTEM including:

(CFR: 41.7 / 45.7)

A3.09 Reactor building temperature: BWR-4,5,6(P-Spec) 241000 (SF3 RTPRS) Reactor/Turbine Pressure X

Knowledge of the effect that a 3.3 35 Regulating loss or malfunction of the REACTOR/TURBINE PRESSURE REGULATING SYSTEM will have on following:

(CFR: 41.7 / 45.4)

K3.07 Main stop/throttle valves 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 256000 (SF2 CDS) Condensate 259001 (SF2 FWS) Feedwater X

Knowledge of electrical power 3.3 36 supplies to the following:

(CFR: 41.7)

K2.01 Reactor feedwater pump(s): Motor-Driven-Only 268000 (SF9 RW) Radwaste

ES-401 13 Form ES-401-1 271000 (SF9 OG) Offgas X

Knowledge of the physical 2.7 37 connections and/or cause effect relationships between OFFGAS SYSTEM and the following:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.04 Condensate system 272000 (SF7, SF9 RMS) Radiation Monitoring 286000 (SF8 FPS) Fire Protection 288000 (SF9 PVS) Plant Ventilation 290001 (SF5 SC) Secondary Containment 290003 (SF9 CRV) Control Room Ventilation 290002 (SF4 RVI) Reactor Vessel Internals X

Ability to (a) predict the 3.6 38 impacts of the following on the REACTOR VESSEL INTERNALS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

(CFR: 41.5 / 45.6)

A2.02 Over pressurization transient 51001 (SF8 CWS*) Circulating Water K/A Category Point Totals: 1 1 1 1 1 1 1 1 2 1 1 Group Point Total: 12

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: River Bend Station (RO Exam) Date of Exam: 2/8/2021 Category K/A # Topic RO SRO-only IR # IR #

Knowledge of facility requirements for controlling 2.1.13 2.5 66 vital/controlled access.

(CFR: 41.10 / 43.5 / 45.9 / 45.10)

Ability to verify the controlled procedure copy.

2.1.21 3.5 67 (CFR: 41.10 / 45.10 / 45.13)

1. Conduct of Knowledge of industrial safety procedures (such Operations 2.1.26 3.4 68 as rotating equipment, electrical, high temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

(CFR: 41.10 / 45.12)

Subtotal 3 Knowledge of the process for managing 2.2.17 2.6 69 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)

2. Equipment Knowledge of the process used to track inoperable 2.2.43 3.0 70 Control alarms.

(CFR: 41.10 / 43.5 / 45.13)

Ability to determine Technical Specification Mode 2.2.35 3.6 71 of Operation.

(CFR: 41.7 / 41.10 / 43.2 / 45.13)

Subtotal 3 Knowledge of radiation exposure limits under 2.3.4 3.2 72 normal or emergency conditions.

(CFR: 41.12 / 43.4 / 45.10)

Ability to comply with radiation work permit 2.3.7 3.5 73

3. Radiation requirements during normal or abnormal Control conditions.

(CFR: 41.12 / 45.10) 2.3.

Subtotal 2 Ability to identify post-accident instrumentation.

2.4.3 3.7 74 (CFR: 41.6 / 45.4)

Knowledge of EOP entry conditions and immediate 2.4.1 4.6 75

4. Emergency action steps.

Procedures/Plan (CFR: 41.10 / 43.5 / 45.13) 2.4.

Subtotal 2 Tier 3 Point Total 10 10 7

ES-401 1 Form ES-401-1 Facility: Riverbend Station (SRO Exam) Date of Exam: 2/8/2021 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. 1 20 3 4 7 Emergency and N/A N/A 2 7 2 1 3 Abnormal Plant Evolutions Tier Totals 27 5 5 10 1 26 3 2 5 2.

Plant 2 12 1 2 3 Systems Tier Totals 38 4 4 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)