ML20153A832

ES-401-1

ML20153A832
Person / Time
Site:	Quad Cities
Issue date:	04/10/2020
From:	NRC/RGN-III
To:	Exelon Generation Co
Roach G
Shared Package
ML19121A185	List: ML20153A820 ML20153A823 ML20153A826 ML20153A827 ML20153A829 ML20153A830 ML20153A831 ML20153A832 ML20153A833 ML20153A834
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Download: ML20153A832 (17)

Text

ES-401 1

Form ES-401-1 Facility: Quad Cities Nuclear Power Station Date of Exam: March 16 - 27, 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 4

3 N/A 3

3 N/A 3

20 3

4 7

2 1

1 2

1 1

1 7

2 1

3 Tier Totals 5

5 5

4 4

4 27 5

5 10

2.

Plant Systems 1

2 2

2 2

2 3

3 3

3 2

2 26 3

2 5

2 1

1 1

1 1

1 1

1 1

2 1

12 0

2 1

3 Tier Totals 3

3 3

3 3

4 4

4 4

4 3

38 5

3 8

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

2 3

4 7

3 3

2 2

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 07 AA1.07 - Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: Nuclear boiler instrumentation system.

(CFR: 41.7 / 45.6) 3.1 1

295003 (APE 3) Partial or Complete Loss of AC Power / 6 04 AA2.04 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF A.C.

POWER: System lineups.

(CFR: 41.10 / 43.5 / 45.13) 3.5 2

295004 (APE 4) Partial or Total Loss of DC Power / 6 04.

46 Generic K/A 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 3

295005 (APE 5) Main Turbine Generator Trip /

3 03 AK1.03 - Knowledge of the operational implications of the following concepts as they apply to MAIN TURBINE GENERATOR TRIP: Pressure effects on reactor level.

(CFR: 41.8 to 41.10) 3.5 4

295006 (APE 6) Scram / 1 02 AK2.02 - Knowledge of the interrelations between SCRAM and the following: Reactor water level control system.

(CFR: 41.7 / 45.8) 3.8 5

295016 (APE 16) Control Room Abandonment

/ 7 02 AK3.02 - Knowledge of the reasons for the following responses as they apply to CONTROL ROOM ABANDONMENT:

Turbine Trip.

(CFR: 41.5 / 45.6) 3.7 6

295018 (APE 18) Partial or Complete Loss of CCW / 8 03 AA1.03 - Ability to operate and/or monitor the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Affected systems so as to isolate damaged portions.

(CFR: 41.7 / 45.6) 3.3 7

295019 (APE 19) Partial or Complete Loss of Instrument Air / 8 01 AA2.01 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: Instrument air system pressure.

(CFR: 41.10 / 43.5 / 45.13) 3.5 8

295021 (APE 21) Loss of Shutdown Cooling /

4 01.

32 Generic K/A 2.1.32 - Ability to explain and apply system limits and precautions.

(CFR: 41.10 / 43.2 / 45.12) 3.8 9

295023 (APE 23) Refueling Accidents / 8 03 AK1.03 - Knowledge of the operational implications of the following concepts as they apply to REFUELING ACCIDENTS:

Inadvertent criticality.

(CFR: 41.8 to 41.10) 3.7 10 295024 High Drywell Pressure / 5 15 EK2.15 - Knowledge of the interrelations between HIGH DRYWELL PRESSURE and the following: Containment spray logic:

Plant-Specific.

(CFR: 41.7 / 45.8) 3.8 11 295025 (EPE 2) High Reactor Pressure / 3 01 EK1.01 - Knowledge of the operational implications of the following concepts as they apply to HIGH REACTOR PRESSURE:

Pressure effects on reactor power.

(CFR: 41.8 to 41.10) 3.9 12

ES-401 3

Form ES-401-1 295026 (EPE 3) Suppression Pool High Water Temperature / 5 01 EK2.01 - Knowledge of the interrelations between SUPPRESSION POOL HIGH WATER TEMPERATURE and the following:

Suppression pool cooling.

(CFR: 41.7 / 45.8) 3.9 13 295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only) / 5 03 EK3.03 - Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL TEMPERATURE: Drywell spray operation: Mark-I&II.

(CFR: 41.5 / 45.6) 3.6 14 295030 (EPE 7) Low Suppression Pool Water Level / 5 02 EA1.02 - Ability to operate and/or monitor the following as they apply to LOW SUPPRESSION POOL WATER LEVEL:

RCIC: Plant-Specific.

(CFR: 41.7 / 45.6) 3.4 15 295031 (EPE 8) Reactor Low Water Level / 2 01 EA2.01 - Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL: Reactor water level.

(CFR: 41.10 / 43.5 / 45.13) 4.6 16 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 02.

44 Generic K/A 2.2.44 - 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 17 295038 (EPE 15) High Offsite Radioactivity Release Rate / 9 02 EK1.02 - Knowledge of the operational implications of the following concepts as they apply to HIGH OFF-SITE RELEASE RATE: Protection of the general public.

(CFR: 41.8 to 41.10) 4.2 18 600000 (APE 24) Plant Fire On Site / 8 01 AK2.01 - Knowledge of the interrelations between PLANT FIRE ON SITE and the following: Sensors / detectors and valves.

2.6 19 700000 (APE 25) Generator Voltage and Electric Grid Disturbances / 6 02 AK3.02 - Knowledge of the reasons for the following responses as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Actions contained in abnormal operating procedure for voltage and grid disturbances.

(CFR: 41.4, 41.5, 41.7, 41.10 / 45.8) 3.6 20 K/A Category Totals:

4 4

3 3

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 AK3.04 - Knowledge of the reasons for the following responses as they apply to LOSS OF MAIN CONDENSER VACUUM:

Bypass valve closure.

(CFR: 41.5 / 45.6) 3.4 21 295007 (APE 7) High Reactor Pressure / 3 295008 (APE 8) High Reactor Water Level / 2 07 AA1.07 - Ability to operate and/or monitor the following as they apply to HIGH REACTOR WATER LEVEL: Main turbine:

Plant-Specific.

(CFR: 41.7 / 45.6) 3.4 22 295009 (APE 9) Low Reactor Water Level / 2 02 AA2.02 - Ability to determine and/or interpret the following as they apply to LOW REACTOR WATER LEVEL: Steam flow/feed flow mismatch.

(CFR: 41.10 / 43.5 / 45.13) 3.6 23 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 04.

45 Generic K/A 2.4.45 - Ability to prioritize and interpret the significance of each annunciator or alarm.

(CFR: 41.10 / 43.5 / 45.3 / 45.12) 4.1 24 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 04 AK1.04 - Knowledge of the operational implications of the following concepts as they apply to INADVERTENT CONTAINMENT ISOLATION: Bottom head thermal stratification.

(CFR: 41.8 to 41.10) 2.5 25 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 03 EK2.03 - Knowledge of the interrelations between HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS and the following: Secondary containment ventilation: Plant-Specific.

(CFR: 41.7 / 45.8) 3.7 26 295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9

ES-401 5

Form ES-401-1 295035 (EPE 12) Secondary Containment High Differential Pressure / 5 01 EK3.01 - Knowledge of the reasons for the following responses as they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: Blow-out panel operation: Plant-Specific.

(CFR: 41.5 / 45.6) 2.8 27 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

2 1

1 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 03 K6.03 - Knowledge of the effect that a loss or malfunction of the following will have on the RHR/LPCI: INJECTION MODE (PLANT SPECIFIC): Emergency generator.

(CFR: 41.7 / 45.7) 3.7 28 205000 (SF4 SCS) Shutdown Cooling 06 A1.06 - Ability to predict and/or monitor changes in parameters associated with operating the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) controls including: Reactor temperatures (moderator, vessel, flange).

(CFR: 41.5 / 45.5) 3.7 29 206000 (SF2, SF4 HPCIS)

High-Pressure Coolant Injection 14 A2.14 - 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: Flow controller failure: BWR-2,3,4.

(CFR: 41.5 / 45.6) 3.3 30 207000 (SF4 IC) Isolation (Emergency) Condenser 209001 (SF2, SF4 LPCS)

Low-Pressure Core Spray 06 A3.06 - Ability to monitor automatic operations of the LOW PRESSURE CORE SPRAY SYSTEM including: Lights and alarms.

(CFR: 41.7 / 45.7) 3.6 31 209002 (SF2, SF4 HPCS)

High-Pressure Core Spray 211000 (SF1 SLCS) Standby Liquid Control 02 A4.02 - Ability to manually operate and/or monitor in the control room: SBLC control switch.

(CFR: 41.7 / 45.5 to 45.8) 4.2 32 212000 (SF7 RPS) Reactor Protection 02

02.

39 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) 3.3 33 Generic K/A 2.2.39 - Knowledge of less than or equal to one hour Technical Specification action statements for systems.

(CFR: 41.7 / 41.10 / 43.2 / 45.13) 3.9 34 215003 (SF7 IRM)

Intermediate-Range Monitor 03 03 K1.03 - Knowledge of the physical connections and/or cause effect relationships between INTERMEDIATE RANGE MONITOR (IRM) SYSTEM and the following: Rod control and information system: Plant-Specific.

(CFR: 41.2 to 41.9 / 45.7 to 45.8) 3.1 35 K6.03 - Knowledge of the effect that a loss or malfunction of the following will have on the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM: Detector drive motor.

(CFR: 41.7 / 45.7) 2.8 36 215004 (SF7 SRMS) Source-Range Monitor 01 K2.01 - Knowledge of electrical power supplies to the following: SRM channels/detectors.

(CFR: 41.7) 2.6 37

ES-401 7

Form ES-401-1 01 A1.01 - Ability to predict and/or monitor changes in parameters associated with operating the SOURCE RANGE MONITOR (SRM) SYSTEM controls including: Detector position.

(CFR: 41.5 / 45.5) 3.0 38 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor 06 08 K3.06 - Knowledge of the effect that a loss or malfunction of the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM will have on following: IRM: Plant-Specific.

(CFR: 41.7 / 45.4) 3.5 39 A2.08 - 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: Faulty or erratic operation of detectors/systems.

(CFR: 41.5 / 45.6) 3.2 40 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling 02 06 K4.02 - Knowledge of REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) design feature(s) and/or interlocks which provide for the following: Prevent over filling reactor vessel.

(CFR: 41.7) 3.3 41 A3.06 - Ability to monitor automatic operations of the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) including: Lights and alarms.

(CFR: 41.7 / 45.7) 3.5 42 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 43 223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff 05 K6.05 - Knowledge of the effect that a loss or malfunction of the following will have on the PRIMARY CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF: Containment instrumentation.

(CFR: 41.7 / 45.7) 3.0 44 239002 (SF3 SRV) Safety Relief Valves 04 A1.04 - Ability to predict and/or monitor changes in parameters associated with operating the RELIEF/SAFETY VALVES controls including: Reactor pressure.

(CFR: 41.5 / 45.5) 3.8 45 259002 (SF2 RWLCS) Reactor Water Level Control 01 A2.01. - Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of any number of main steam flow inputs.

(CFR: 41.5 / 45.6) 3.3 46 261000 (SF9 SGTS) Standby Gas Treatment 03 A3.03 - Ability to monitor automatic operations of the STANDBY GAS TREATMENT SYSTEM including: Valve operation.

(CFR: 41.7 / 45.7) 3.0 47 262001 (SF6 AC) AC Electrical Distribution 04 A4.04 - Ability to manually operate and/or monitor in the control room: Synchronizing and paralleling of different A.C. supplies.

(CFR: 41.7 / 45.5 to 45.8) 3.6 48

ES-401 8

Form ES-401-1 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC)

02.

12 Generic K/A 2.2.12 - Knowledge of surveillance procedures.

(CFR: 41.10 / 45.13) 3.7 49 263000 (SF6 DC) DC Electrical Distribution 04 K1.04 - Knowledge of the physical connections and/or cause effect relationships between D.C. ELECTRICAL DISTRIBUTION and the following: Ground detection.

(CFR: 41.2 to 41.9 / 45.7 to 45.8) 2.6 50 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG 03 K3.03 - Knowledge of the effect that a loss or malfunction of the EMERGENCY GENERATORS (DIESEL/JET) will have on following: Major loads powered from electrical buses fed by the emergency generator(s).

(CFR: 41.7 / 45.4) 4.1 51 300000 (SF8 IA) Instrument Air 01 K2.01 - Knowledge of electrical power supplies to the following: Instrument air compressor.

(CFR: 41.7) 2.8 52 400000 (SF8 CCS) Component Cooling Water 01 K4.01 - Knowledge of CCWS design feature(s) and or interlocks which provide for the following: Automatic start of standby pump.

(CFR: 41.7) 3.4 53 510000 (SF4 SWS*) Service Water (Normal and Emergency)

N/A - Revision 2 to K/A Catalog used.

K/A Category Point Totals:

2 2

2 2

2 3

3 3

3 2

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

Timer malfunction test switch:

Plant-Specific.

(CFR: 41.7 / 45.5 to 45.8) 2.8 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 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

01.

27 Generic K/A 2.1.27 - Knowledge of system purpose and/or function.

(CFR: 41.7) 3.9 55 215002 (SF7 RBMS) Rod Block Monitor 216000 (SF7 NBI) Nuclear Boiler Instrumentation 18 K1.18 - Knowledge of the physical connections and/or cause effect relationships between NUCLEAR BOILER INSTRUMENTATION and the following: Analog trip system:

Plant-Specific.

(CFR: 41.2 to 41.9 / 45.7 to 45.8) 3.0 56 219000 (SF5 RHR SPC) RHR/LPCI:

Torus/Suppression Pool Cooling Mode 223001 (SF5 PCS) Primary Containment and Auxiliaries 09 K2.09 - Knowledge of electrical power supplies to the following:

Drywell cooling fans: Plant-Specific.

(CFR: 41.7) 2.7 57 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 03 K3.03 - Knowledge of the effect that a loss or malfunction of the FUEL HANDLING EQUIPMENT will have on following: Fuel handling operations.

(CFR: 41.7 / 45.4) 3.1 58 239001 (SF3, SF4 MRSS) Main and Reheat Steam 10 K4.10 - Knowledge of MAIN AND REHEAT STEAM SYSTEM design feature(s) and/or interlocks which provide for the following: Moisture removal from steam lines prior to admitting steam.

(CFR: 41.7) 2.9 59 239003 (SF9 MSVLCS) Main Steam Isolation Valve Leakage Control

ES-401 10 Form ES-401-1 241000 (SF3 RTPRS) Reactor/Turbine Pressure Regulating 03 K5.03 - Knowledge of the operational Implications of the following concepts as they apply to REACTOR/TURBINE PRESSURE REGULATING SYSTEM: Reactor power vs. reactor pressure.

(CFR: 41.5 / 45.3) 3.5 60 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 01 K6.01 - Knowledge of the effect that a loss or malfunction of the following will have on the MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS: Gland seal.

(CFR: 41.7 / 45.7) 2.8 61 256000 (SF2 CDS) Condensate 08 A1.08-Ability to predict and/or monitor changes in parameters associated with operating the REACTOR CONDENSATE SYSTEM controls including:

System water quality.

(CFR: 41.5 / 45.5) 2.7 62 259001 (SF2 FWS) Feedwater 05 A2.05 - Ability to (a) predict the impacts of the following on the REACTOR FEEDWATER SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of applicable plant air systems.

(CFR: 41.5 / 45.6) 3.0 63 268000 (SF9 RW) Radwaste 271000 (SF9 OG) Offgas 02 A3.02 - Ability to monitor automatic operations of the OFFGAS SYSTEM including: System flows.

(CFR: 41.7 / 45.7) 2.9 64 272000 (SF7, SF9 RMS) Radiation Monitoring 286000 (SF8 FPS) Fire Protection 288000 (SF9 PVS) Plant Ventilation 01 A4.01 - Ability to manually operate and/or monitor in the control room:

Start and stop fans.

3.1 65 290001 (SF5 SC) Secondary Containment 290003 (SF9 CRV) Control Room Ventilation 290002 (SF4 RVI) Reactor Vessel Internals 51001 (SF8 CWS*) Circulating Water N/A - Revision 2 to K/A Catalog used.

K/A Category Point Totals:

1 1

1 1

1 1

1 1

1 2

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 295003 (APE 3) Partial or Complete Loss of AC Power / 6 295004 (APE 4) Partial or Total Loss of DC Power / 6 02.

36 Generic K/A 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) 4.2 76 295005 (APE 5) Main Turbine Generator Trip /

3 04.

35 Generic K/A 2.4.35 - Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

(CFR: 41.10 / 43.5 / 45.13) 4.0 77 295006 (APE 6) Scram / 1 295016 (APE 16) Control Room Abandonment

/ 7 295018 (APE 18) Partial or Complete Loss of CCW / 8 03 AA2.03 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Cause for partial or complete loss.

(CFR: 41.10 / 43.5 / 45.13) 3.5 78 295019 (APE 19) Partial or Complete Loss of Instrument Air / 8 02 AA2.02 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: Status of safety-related instrument air system loads (see AK2.1 -

AK2.19).

(CFR: 41.10 / 43.5 / 45.13) 3.7 79 295021 (APE 21) Loss of Shutdown Cooling /

4 295023 (APE 23) Refueling Accidents / 8 295024 High Drywell Pressure / 5 295025 (EPE 2) High Reactor Pressure / 3 02 EA2.02 - Ability to determine and/or interpret the following as they apply to HIGH REACTOR PRESSURE: Reactor power.

(CFR: 41.10 / 43.5 / 45.13) 4.2 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 295031 (EPE 8) Reactor Low Water Level / 2 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 01.

23 Generic K/A 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))

4.4 81

ES-401 12 Form ES-401-1 295038 (EPE 15) High Offsite Radioactivity Release Rate / 9 600000 (APE 24) Plant Fire On Site / 8 04.

30 Generic K/A 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 82 700000 (APE 25) Generator Voltage and Electric Grid Disturbances / 6 K/A Category Totals:

0 0

0 0

3 4

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 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 04.

06 2.4.6 - Knowledge of EOP mitigation strategies.

(CFR: 41.10 / 43.5 / 45.13) 4.7 83 295013 (APE 13) High Suppression Pool Temperature. / 5 295014 (APE 14) Inadvertent Reactivity Addition / 1 295015 (APE 15) Incomplete Scram / 1 295017 (APE 17) Abnormal Offsite Release Rate / 9 03 AA2.03 - Ability to determine and/or interpret the following as they apply to HIGH OFF-SITE RELEASE RATE:

Radiation levels: Plant-Specific.

(CFR: 41.10 / 43.5 / 45.13) 3.1 84 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 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 85 K/A Category Point Totals:

0 0

0 0

2 1

Group Point Total:

3

ES-401 14 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

01.

20 2.1.20 - Ability to interpret and execute procedure steps.

(CFR: 41.10 / 43.5 / 45.12) 4.6 86 205000 (SF4 SCS) Shutdown Cooling 03 A2.03 - Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

A.C. failure (CFR: 41.5 / 45.6) 3.2 87 206000 (SF2, SF4 HPCIS)

High-Pressure Coolant Injection 207000 (SF4 IC) Isolation (Emergency) Condenser 209001 (SF2, SF4 LPCS)

Low-Pressure Core Spray 06 A2.06 - Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Inadequate system flow.

(CFR: 41.5 / 45.6) 3.2 88 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 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling 218000 (SF3 ADS) Automatic Depressurization 223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff 239002 (SF3 SRV) Safety Relief Valves

02.

37 Generic K/A 2.2.37 - Ability to determine operability and/or availability of safety related equipment.

(CFR: 41.7 / 43.5 / 45.12) 4.6 89 259002 (SF2 RWLCS) Reactor Water Level Control 261000 (SF9 SGTS) Standby Gas Treatment

ES-401 15 Form ES-401-1 262001 (SF6 AC) AC Electrical Distribution 04 A2.04 - Ability to (a) predict the impacts of the following on the A.C. ELECTRICAL DISTRIBUTION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Types of loads that, if deenergized, would degrade or hinder plant operation.

(CFR: 41.5 / 45.6) 3.8 90 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC) 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)

N/A - Revision 2 to K/A Catalog used.

K/A Category Point Totals:

0 0

0 0

0 0

0 3

0 0

2 Group Point Total:

5

ES-401 16 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

01.

07 Generic K/A 2.1.7 - 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 91 202002 (SF1 RSCTL) Recirculation Flow Control 204000 (SF2 RWCU) Reactor Water Cleanup 214000 (SF7 RPIS) Rod Position Information 01 A2.01 - Ability to (a) predict the impacts of the following on the ROD POSITION INFORMATION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Failed reed switches.

(CFR: 41.5 / 45.6) 3.3 92 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 12 A2.12 - Ability to (a) predict the impacts of the following on the RHR/LPCI:

TORUS/SUPPRESSION POOL SPRAY MODE; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Valve logic failure.

(CFR: 41.5 / 45.6) 3.3 93 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

ES-401 17 Form ES-401-1 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 290003 (SF9 CRV) Control Room Ventilation 290002 (SF4 RVI) Reactor Vessel Internals 51001 (SF8 CWS*) Circulating Water N/A - Revision 2 to K/A Catalog used.

K/A Category Point Totals:

0 0

0 0

0 0

0 2

0 0

1 Group Point Total:

3