ML20308A415

Ile Form ES-401-1

ML20308A415
Person / Time
Site:	Dresden
Issue date:	07/13/2020
From:	Exelon Generation Co
To:	Chuck Zoia NRC/RGN-III/DRS/OLB
Zoia C
Shared Package
ML19121A250	List: ML20295A408 ML20295A434 ML20295A440 ML20308A402 ML20308A412 ML20308A415 ML20308A418 ML20308A424
References
Download: ML20308A415 (18)

Text

ES-401 1

Form ES-401-1 Facility: Dresden Date of Exam: June 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

2 1

3 Tier Totals 4

4 5

5 5

4 27 6

4 10

2.

Plant Systems 1

2 2

2 2

3 3

2 2

3 3

2 26 2

3 5

2 1

1 1

1 1

1 1

1 2

1 1

12 1

1 1

3 Tier Totals 3

3 3

3 4

4 3

3 5

4 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 05 AK3.05 - Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:

Reduced loop operating requirements:

Plant-specific.

(CFR: 41.5 / 45.6) 3.2 1

295003 (APE 3) Partial or Complete Loss of AC Power / 6 03 AA1.03 - Ability to operate and/or monitor as they apply to PARTIAL OR COMPLETE LOSS OF AC 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 01 AA2.01 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF DC POWER: Cause of partial or complete loss of DC power.

(CFR:41.10 / 43.5 / 45.13) 3.2 3

295005 (APE 5) Main Turbine Generator Trip /

3 01.

20 G2.1.20 - Ability to interpret and execute procedure steps.

(CFR: 41.10 / 43.5 / 45.12) 3.5 4

295006 (APE 6) Scram / 1 02 AK1.02 - Knowledge of the operational implications of the following concepts as they apply to SCRAM: Shutdown margin.

(CFR: 41.8 to 41.10) 3.4 5

295016 (APE 16) Control Room Abandonment

/ 7 03 AK2.03 - Knowledge of the interrelations between the CONTROL ROOM ABANDONMENT and the following: Control Room HVAC.

(CFR: 41.7 / 45.8) 2.9 6

295018 (APE 18) Partial or Complete Loss of CCW / 8 04 AK3.04 - Knowledge of the reasons for the following responses as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Starting standby pump.

(CFR: 41.5 / 45.6) 3.3 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 02 AA2.02 - Ability to determine and/or interpret the following as they apply to LOSS OF SHUTDOWN COOLING:

RHR/shutdown cooling system flow.

(CFR: 41.10 / 43.5 / 45.13) 3.4 9

295023 (APE 23) Refueling Accidents / 8 04.

31 G2.4.31 - Knowledge of annunciator alarms, indications, or response procedures.

(CFR: 41.10 / 45.3) 4.2 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: Plant-specific.

(CFR: 41.8 to 41.10) 4.1 11 295025 (EPE 2) High Reactor Pressure / 3 02 EK2.02 - Knowledge of the interrelations between HIGH REACTOR PRESSURE and the following: Isolation condenser: Plant-specific (CFR: 41.7 / 45.8) 4.2 12 295026 (EPE 3) Suppression Pool High Water Temperature / 5 05 EK3.05 - Knowledge of the reasons for the following responses as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Reactor Scram.

(CFR: 41.5 / 45.6) 3.9 13

ES-401 3

Form ES-401-1 295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only) / 5 02 EA1.02 - Ability to operate and/or monitor the following as they apply to HIGH DRYWELL TEMPERATURE: Drywell ventilation system.

(CFR: 41.7 / 45.6) 3.9 14 295030 (EPE 7) Low Suppression Pool Water Level / 5 04 EA2.04 - Ability to determine and/or interpret the following as they apply to LOW SUPPRESSION POOL WATER LEVEL:

Drywell/suppression chamber differential pressure.

(CFR: 41.10 / 43.5 / 45.13) 3.5 15 295031 (EPE 8) Reactor Low Water Level / 2 02.

44 G2.2.44 - 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.

(CFR: 41.5 / 43.5 / 45.12) 4.2 16 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 03 EK1.03 - Knowledge of the operational implications of the following concepts as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: Boron effects on reactor power (SBLC).

(CFR: 41.8 to 41.10) 4.2 17 295038 (EPE 15) High Offsite Radioactivity Release Rate / 9 05 EK2.05 - Knowledge of the interrelations between HIGH OFF-SITE RELEASE RATE and the following: Site emergency plan.

(CFR: 41.7 / 45.8) 3.7 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:

2.8 19 700000 (APE 25) Generator Voltage and Electric Grid Disturbances / 6 03 AA1.03 - Ability to operate and/or monitor the following as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCS: Voltage regulator controls.

(CFR: 41.5, 41.10 / 45.5, 45.7, 45.8) 3.8 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 295007 (APE 7) High Reactor Pressure / 3 295008 (APE 8) High Reactor Water Level / 2 295009 (APE 9) Low Reactor Water Level / 2 03 AA2.03 - Ability to determine and/or interpret the following as they apply to LOW REACTOR WATER LEVEL: Reactor water cleanup blowdown rate.

(CFR: 41.10 / 43.5 / 45.13) 2.9 21 295010 (APE 10) High Drywell Pressure / 5 295011 (APE 11) High Containment Temperature (Mark III Containment only) / 5 295012 (APE 12) High Drywell Temperature /

5 04.

01 G2.4.1 - Knowledge of EOP entry conditions and immediate action steps.

(CFR: 41.10 / 43.5 / 45.13) 4.6 22 295013 (APE 13) High Suppression Pool Temperature. / 5 295014 (APE 14) Inadvertent Reactivity Addition / 1 295015 (APE 15) Incomplete Scram / 1 02 AK1.02 - Knowledge of the operational implications of the following concepts as they apply to INCOMPLETE SCRAM:

Cooldown effects on reactor power.

(CFR: 41.8 to 41.10) 3.9 23 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 03 AK2.03 - Knowledge of the interrelations between LOSS OF CRD PUMPS and the following: Accumulator pressures.

(CFR: 41.7 / 45.8) 3.4 24 295029 (EPE 6) High Suppression Pool Water Level / 5 01 EK3.01 - Knowledge of the reasons for the following responses as they apply to HIGH SUPPRESSION POOL WATER LEVEL:

Emergency depressurization.

(CFR: 41.5 / 45.6) 3.5 25 295032 (EPE 9) High Secondary Containment Area Temperature / 5 295033 (EPE 10) High Secondary Containment Area Radiation Levels / 9 03 EA1.03 - Ability to operate and/or monitor the following as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS: Secondary containment ventilation.

(CFR: 41.7 / 45.6) 3.8 26 295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9 295035 (EPE 12) Secondary Containment High Differential Pressure / 5 01 EA2.01 - Ability to determine and/or interpret the following as they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: Secondary containment pressure: Plant-specific.

(CFR: 41.8 to 41.10) 3.8 27

ES-401 5

Form ES-401-1 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 1

1 1

2 1

Group Point Total:

7

ES-401 6

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)

RHR/LPCI: Injection Mode 08 04 K6.08 - Knowledge of the effect that a loss or malfunction of the following will have on the RHR/LPCI: INJECTION MODE (Plant-specific): ECCS room cooling.

(CFR: 41.7 / 45.7)

A4.04 - Ability to manually operate and/or monitor in the control room: Heat exchanger cooling flow.

(CFR: 41.7 / 45.5 to 45.8) 2.9 3.6 28 29 205000 (SF4 SCS) Shutdown Cooling 03 A1.03 - Ability to predict and/or monitor changes in parameters associated with operating the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) controls including: Recirculation loop temperatures.

(CFR: 41.5 / 45.5) 3.3 30 206000 (SF2, SF4 HPCIS)

High-Pressure Coolant Injection 16 08 A2.16 - Ability to (a) predict the impacts of the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations: High drywell pressure: BWR-2,3,4 (CFR: 41.5 / 45.6)

A3.08 - Ability to monitor automatic operations of the HIGH PRESSURE COOLANT INJECTION SYSTEM including:

Condensate storage tank level: BWR-2,3,4 (CFR: 41.7 / 45.7) 4.0 3.7 31 32 207000 (SF4 IC) Isolation (Emergency) Condenser 01 A3.01 - Ability to monitor automatic operations of the ISOLATION (EMERGENCY) CONDENSER including:

Isolation condenser level: BWR-2,3 (CFR: 41.7 / 45.7) 3.5 33 209001 (SF2, SF4 LPCS)

Low-Pressure Core Spray 01 A4.01 - Ability to manually operate and/or monitor in the control room: Core spray pump (CFR: 41.7 / 45.5 to 45.8) 3.8 34 209002 (SF2, SF4 HPCS)

High-Pressure Core Spray 211000 (SF1 SLCS) Standby Liquid Control

01.

31 G2.1.31 - Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.

(CFR: 41.10 / 45.12) 4.6 35 212000 (SF7 RPS) Reactor Protection 06 02 K1.06 - Knowledge of the physical connections and/or cause-effect relationships between REACTOR PROTECTION SYSTEM and the following:

Control rod drive hydraulic system.

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K5.02 - Knowledge of the operational implications of the following concepts as they apply to REACTOR PROTECTION SYSTEM: Specific logic arrangements.

(CFR: 41.5 / 45.3) 3.5 3.3 36 37 215003 (SF7 IRM)

Intermediate-Range Monitor 01 K2.01 - Knowledge of electrical power supplies to the following: IRM channels/

detectors.

(CFR: 41.7) 2.5 38

ES-401 7

Form ES-401-1 215004 (SF7 SRMS) Source-Range Monitor 01 K3.01 - Knowledge of the effect that loss or malfunction of the SOURCE RANGE MONITOR (SRM) SYSTEM will have on following: RPS.

(CFR: 41.7 / 45.4) 3.4 39 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor 01 K4.01 - Knowledge of AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM design feature(s) and/or interlocks which provide for the following: Rod withdrawal blocks.

(CFR: 41.7) 3.7 40 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling 218000 (SF3 ADS) Automatic Depressurization 01 K5.01 - Knowledge of the operational implications of the following concepts as they apply to AUTOMATIC DEPRESSURIZATION SYSTEM: ADS logic operation.

(CFR: 41.5 / 45.3) 3.8 41 223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff 04 K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLERA STEAM SUPPLY SHUT-OFF: Nuclear boiler instrumentation.

(CFR: 41.7 / 45.7) 3.3 42 239002 (SF3 SRV) Safety Relief Valves 06 A1.06 - Ability to predict and/or monitor changes in parameters associated with operating the RELIEF/SAFETY VALVES controls including: Reactor power.

(CFR: 41.5 / 45.5) 3.7 43 259002 (SF2 RWLCS) Reactor Water Level Control 02 02 K1.02 - Knowledge of the physical connections and/or cause-effect relationships between REACTOR WATER LEVEL CONTROL SYSTEM and the following: Main steam flow.

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

A2.02 - Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM: and (b) based on those predictions, use procedure to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of any number of reactor feedwater flow inputs.

(CFR: 41.5 / 45.6) 3.5 3.3 44 45 261000 (SF9 SGTS) Standby Gas Treatment 01 A3.01 - Ability to monitor automatic operations of the STANDBY GAS TREATMENT SYSTEM including: System flow (CFR: 41.7 / 45.7) 3.2 46 262001 (SF6 AC) AC Electrical Distribution 02 A4.02 - Ability to manually operate and/or monitor in the control room: Synchroscope, including understanding of running and incoming voltages.

(CFR: 41.7 / 45.5 to 45.8) 3.4 47 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC)

01.

29 G2.1.29 - Knowledge of how to conduct system lineups, such as valves, breakers, switches, etc.

(CFR: 41.10 / 45.1 / 45.12) 4.1 48 263000 (SF6 DC) DC Electrical Distribution 04 K1.04 - Knowledge of the physical connections and/or cause-effect relationships between DC ELECTRICAL DISTRIBUTION and the following: Ground detection.

(CFR: 41.2 to 41.9 / 45.7 to 45.8) 2.6 49

ES-401 8

Form ES-401-1 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG 01 05 K3.01 - Knowledge of the effect that a loss or malfunction of the EMERGENCY GENERATORS (DIESEL/JET) will have on the following: Emergency core cooling systems.

(CFR: 41.7 / 45.4)

K5.05 - Knowledge of the operational implications of the following concepts as they apply to EMERGENCY GENERATORS (DIESEL/JET): Paralleling AC power sources (CFR: 41.5 / 45.3) 4.2 3.4 50 51 300000 (SF8 IA) Instrument Air 01 K4.01 - Knowledge of (INSTRUMENT AIR SYSTEM) design feature(s) and/or interlocks which provide for the following:

Manual/automatic transfers of control.

(CFR: 41.7) 2.8 52 400000 (SF8 CCS) Component Cooling Water 04 K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the CCWS: Pumps.

(CFR: 41.7 / 45.7) 3.0 53 510000 (SF4 SWS*) Service Water (Normal and Emergency)

K/A Category Point Totals:

3 1

2 2

3 3

2 2

3 3

2 Group Point Total:

26

ES-401 9

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 03 A3.03 - Ability to monitor automatic operation of the REACTOR MANUAL CONTROL SYSTEM including: Rod drift alarm.

(CFR: 41.7 / 45.7) 3.2 54 201003 (SF1 CRDM) Control Rod and Drive Mechanism 02 A4.02 - Ability to manually operate and/or monitor in the control room: CRD mechanism position: Plant-specific.

(CFR: 41.7 / 45.5 to 45.8) 3.5 55 201004 (SF7 RSCS) Rod Sequence Control 201005 (SF1, SF7 RCIS) Rod Control and Information 201006 (SF7 RWMS) Rod Worth Minimizer 04.

46 G2.4.46 - Ability to verify that the alarms are consistent with the plant conditions.

(CFR: 41.10 / 43.5 / 45.3 / 45.12) 4.2 56 202001 (SF1, SF4 RS) Recirculation 202002 (SF1 RSCTL) Recirculation Flow Control 204000 (SF2 RWCU) Reactor Water Cleanup 06 K1.06 - Knowledge of the physical connections and/or cause-effect relationships between REACTOR WATER CLEANUP SYSTEM and the following:

Main condenser.

(CFR: 41.2 to 41.9 / 45.7 to 45.8) 2.8 57 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 01 K2.01 - Knowledge of electrical power supplies to the following: Analog trip system: Plant-specific.

(CFR: 41.7) 2.8 58 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 03 K3.03 - Knowledge of the effect that a loss or malfunction of the RHR/LPCI:

TORUS/SUPPRESSION POOL SPRAY MODE will have on the following: Drywell pressure.

(CFR: 41.7 / 45.4) 3.4 59 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup 234000 (SF8 FH) Fuel-Handling Equipment 239001 (SF3, SF4 MRSS) Main and Reheat Steam 07 K4.07 - Knowledge of MAIN AND REHEAT STEAM SYSTEM design feature(s) and/or interlocks which provide for the following: Over pressure control.

(CFR: 41.7) 3.7 60 239003 (SF9 MSVLCS) Main Steam Isolation Valve Leakage Control 241000 (SF3 RTPRS) Reactor/Turbine Pressure Regulating 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 06 K5.06 - Knowledge of the operational implications of the following concepts as they apply to MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS: Turbine shaft sealing.

(CFR: 41.5 / 45.3) 2.5 61 256000 (SF2 CDS) Condensate

ES-401 10 Form ES-401-1 259001 (SF2 FWS) Feedwater 09 K6.09 - Knowledge of the effect that loss or malfunction of the following will have on the REACTOR FEEDWATER SYSTEM:

Reactor feedwater pump lube oil system (CFR: 41.7 / 45.7) 2.8 62 268000 (SF9 RW) Radwaste 271000 (SF9 OG) Offgas 13 A1.13 - Ability to predict and/or monitor changes in parameters associated with operating the OFFGAS SYSTEM controls including: Hydrogen gas concentration.

(CFR: 41.5 / 45.5) 3.2 63 272000 (SF7, SF9 RMS) Radiation Monitoring 09 A2.09 - Ability to (a) predict the impacts of the following on the RADIATION MONITORING SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Low fuel pool level.

(CFR: 41.5 / 45.6) 3.1 64 286000 (SF8 FPS) Fire Protection 02 A3.02 - Ability to monitor automatic operations of the FIRE PROTECTION SYSTEM including: Fire main pressure.

(CFR: 41.7 / 45.7) 3.1 65 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 K/A Category Point Totals:

1 1

1 1

1 1

1 1

2 1

1 Group Point Total:

12

ES-401 11 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 03 AA2.03 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:

Actual core flow.

(CFR: 41.10 / 43.5 / 45.13) 3.3 76 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 04.

49 G2.4.49 - 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) 4.4 77 295006 (APE 6) Scram / 1 06 AA2.06 - Ability to determine and/or interpret the following as they apply to SCRAM: Cause of reactor SCRAM.

(CFR: 41.10 / 43.5 / 45.13) 3.8 78 295016 (APE 16) Control Room Abandonment

/ 7 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 04.

06 G2.4.6 - Knowledge of EOP mitigation strategies.

(CFR: 41.10 / 43.5 / 45.13) 4.7 79 295023 (APE 23) Refueling Accidents / 8 295024 High Drywell Pressure / 5 295025 (EPE 2) High Reactor Pressure / 3 05 EA2.05 - Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE: Decay heat generation.

(CFR: 41.10 / 43.5 / 45.13) 3.6 80 295026 (EPE 3) Suppression Pool High Water Temperature / 5 295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only) / 5 295030 (EPE 7) Low Suppression Pool Water Level / 5 04.

18 G2.4.18 - Knowledge of the specific bases for EOPs.

(CFR: 41.10 / 43.1 / 45.13) 4.0 81 295031 (EPE 8) Reactor Low Water Level / 2 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 295038 (EPE 15) High Offsite Radioactivity Release Rate / 9 01 EA2.01 - Ability to determine and/or interpret the following as they apply to HIGH OFF-SITE RELEASE RATE: Off-site.

(CFR: 41.10 / 43.5 / 45.13) 4.3 82 600000 (APE 24) Plant Fire On Site / 8

ES-401 12 Form ES-401-1 700000 (APE 25) Generator Voltage and Electric Grid Disturbances / 6 K/A Category Totals:

4 3

Group Point Total:

7

ES-401 13 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 01 AA2.01 - Ability to determine and/or interpret the following as they apply to LOSS OF MAIN CONDENSER VACUUM:

Condenser vacuum/absolute pressure.

(CFR: 41.10 / 43.5 / 45.13) 3.1 83 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 295012 (APE 12) High Drywell Temperature /

5 295013 (APE 13) High Suppression Pool Temperature. / 5 01.

07 G2.1.7 - Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

(CFR: 41.5 / 43.5 / 45.12, 45.13) 4.7 84 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 295029 (EPE 6) High Suppression Pool Water Level / 5 295032 (EPE 9) High Secondary Containment Area Temperature / 5 02 EA2.02 - Ability to determine and/or interpret the following as they apply to HIGH SECONDARY CONTAINMENT AREA TEMPERATURE: Equipment operability.

(CFR: 41.10 / 43.5 / 45.13) 3.5 85 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:

2 1

Group Point Total:

3

ES-401 14 Form ES-401-1

ES-401 15 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

02.

38 G2.2.38 - Knowledge of conditions and limitations in the facility license.

(CFR: 41.7, 41.10 / 43.1 / 45.13) 4.5 86 209001 (SF2, SF4 LPCS)

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

High-Pressure Core Spray 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 04 A2.04 - Ability to (a) predict the impacts of the following on the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: SCRAM trip signals.

(CFR: 41.5 / 45.6) 3.9 87 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling 218000 (SF3 ADS) Automatic Depressurization 223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff

01.

32 G2.1.32 - Ability to explain and apply system limits and precautions.

(CFR: 41.10 / 43.2 / 45.12) 4.0 88 239002 (SF3 SRV) Safety Relief Valves 259002 (SF2 RWLCS) Reactor Water Level Control 261000 (SF9 SGTS) Standby Gas Treatment 10 A2.10 - Ability to (a) predict the impacts of the 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: Low reactor water level:

Plant-specific.

(CFR: 41.5 / 45.6) 3.2 89 262001 (SF6 AC) AC Electrical Distribution

02.

37 G2.2.37 - Ability to determine operability and/or availability of safety related equipment (CFR: 41.7 / 43.5 / 45.12) 4.6 90 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC)

ES-401 16 Form ES-401-1 263000 (SF6 DC) DC Electrical Distribution 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG 300000 (SF8 IA) Instrument Air 400000 (SF8 CCS) Component Cooling Water 510000 (SF4 SWS*) Service Water (Normal and Emergency)

K/A Category Point Totals:

2 3

Group Point Total:

5

ES-401 17 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 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 04 A2.04 - Ability to (a) predict the impacts of the following on the RECIRCULATION FLOW CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Recirculation pump speed mismatch between loops (CFR: 41.5 / 45.6) 3.2 91 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 02 A3.02 - Ability to monitor automatic operations of the FUEL HANDLING EQUIPMENT including: Interlock operation.

(CFR: 41.7 / 45.7) 3.7 92 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 271000 (SF9 OG) Offgas 272000 (SF7, SF9 RMS) Radiation Monitoring 286000 (SF8 FPS) Fire Protection 288000 (SF9 PVS) Plant Ventilation 290001 (SF5 SC) Secondary Containment

ES-401 18 Form ES-401-1 290003 (SF9 CRV) Control Room Ventilation 02.

25 G2.2.25 - Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits.

(CFR: 41.5, 41.7 / 43.2) 4.2 93 290002 (SF4 RVI) Reactor Vessel Internals 51001 (SF8 CWS*) Circulating Water K/A Category Point Totals:

0 0

0 0

0 0

0 1

1 0

1 Group Point Total:

3