ML19309D233

Ile Form ES-401-1

ML19309D233
Person / Time
Site:	Clinton
Issue date:	09/24/2019
From:	Chuck Zoia Exelon Generation Co
To:	NRC/RGN-III/DRS/OLB
Zoia C
Shared Package
ML17214A846	List: ML19309D233 ML19309D531 ML19309D576 ML19309D644 ML19309D694 ML19309D735 ML19309E449 ML19309E481
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Download: ML19309D233 (17)

Text

ES-401 1

Form ES-401-1 Facility: Clinton Nuclear Power Station Date of Exam: September 9 - 20, 2019 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

3 N/A 3

4 N/A 4

20 4

3 7

2 2

1 1

1 1

1 7

2 1

3 Tier Totals 5

4 4

4 5

5 27 6

4 10

2.

Plant Systems 1

3 2

2 3

2 2

2 2

3 2

3 26 2

3 5

2 1

1 1

1 1

1 1

1 2

1 1

12 0

2 1

3 Tier Totals 4

3 3

4 3

3 3

3 5

3 4

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

Actual core flow.

(CFR: 41.10 / 43.5 / 45.13) 3.3 1

295003 (APE 3) Partial or Complete Loss of AC Power / 6 04.

09 G2.4.9 - Knowledge of low power /

shutdown implications in accident (e.g, loss of coolant accident or loss of residual heat removal) mitigation strategies.

(CFR: 41.10 / 43.5 / 45.13) 3.8 2

295004 (APE 4) Partial or Total Loss of DC Power / 6 04 AK1.04 - Knowledge of the operational implications of the following concepts as they apply to PARTIAL OR COMPLETE LOSS OF DC POWER: Effect of battery discharge rate on capacity.

(CFR: 41.8 to 41.10) 2.8 3

295005 (APE 5) Main Turbine Generator Trip /

3 05 AK2.05 - Knowledge of the interrelations between MAIN TURBINE GENERATOR TRIP and the following: Extraction steam system.

(CFR: 41.7 / 45.8) 2.6 4

295006 (APE 6) Scram / 1 02 AK3.02 - Knowledge of the reasons for the following responses as they apply to SCRAM: Reactor power response.

(CFR: 41.5 / 45.6) 4.1 5

295016 (APE 16) Control Room Abandonment

/ 7 04 AA1.04 - Ability to operate and/or monitor the following as they apply to CONTROL ROOM ABANDONMENT: AC electrical distribution.

(CFR: 41.7 / 45.6) 3.1 6

295018 (APE 18) Partial or Complete Loss of CCW / 8 05 AA2.05 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: System pressure.

(CFR: 41.10 / 43.5 / 45.13) 2.9 7

295019 (APE 19) Partial or Complete Loss of Instrument Air / 8 04.

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

(CFR: 41.10 / 43.5 / 45.3,12) 4.2 8

295021 (APE 21) Loss of Shutdown Cooling /

4 04 AK1.04 - Knowledge of the operational implications of the following concepts as they apply to LOSS OF SHUTDOWN COOLING: Natural circulation.

(CFR: 41.8 to 41.10) 3.6 9

295023 (APE 23) Refueling Accidents / 8 03 AK2.03 - Knowledge of the interrelations between REFUELING ACCIDENTS and the following: Radiation monitoring equipment.

(CFR: 41.7 / 45.8) 3.4 10 295024 High Drywell Pressure / 5 04 EK3.04 - Knowledge of the reasons for the following responses as they apply to HIGH DRYWELL PRESSURE: Emergency depressurization.

(CFR: 41.5 / 45.6) 3.7 11 295025 (EPE 2) High Reactor Pressure / 3 01 EA1.01 - Ability to operate and/or monitor the following as they apply to HIGH REACTOR PRESSURE: Main steam line drains.

(CFR: 41.7 / 45.6) 2.9 12 295026 (EPE 3) Suppression Pool High Water Temperature / 5 02 EA2.02 - Ability to determine and/or interpret the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Suppression pool level.

(CFR: 41.10 / 43.5 / 45.13) 3.8 13

ES-401 3

Form ES-401-1 295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 04.

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

(CFR: 41.10 / 43.5 / 45.13) 4.6 14 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only) / 5 295030 (EPE 7) Low Suppression Pool Water Level / 5 01 EK1.01 - Knowledge of the operational implications of the following as they apply to LOW SUPPRESSION POOL WATER LEVEL: Steam condensation.

(CFR: 41.8 to 41.10) 3.8 15 295031 (EPE 8) Reactor Low Water Level / 2 15 EK2.15 - Knowledge of the interrelations between REACTOR LOW WATER LEVEL and the following: AC distribution: Plant-specific.

(CFR: 41.7 / 45.8) 3.2 16 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 02 EK3.02 - Knowledge of the reasons for the following responses as they apply to SCRAM CONDITION PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: SBLC injection.

(CFR: 41.5 / 45.6) 4.3 17 295038 (EPE 15) High Offsite Radioactivity Release Rate / 9 03 EA1.03 - Ability to operate and/or monitor the following as they apply to HIGH OFF-SITE RELEASE RATE: Process liquid radiation monitoring system.

(CFR: 41.7 / 45.6) 3.7 18 600000 (APE 24) Plant Fire On Site / 8 06 AA2.06 - Ability to determine and interpret the following as they apply to PLANT FIRE ON SITE: Need for pressurizing control room (recirculating mode) 2.5 19 700000 (APE 25) Generator Voltage and Electric Grid Disturbances / 6 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 / 45.12,13) 4.4 20 K/A Category Totals:

3 3

3 3

4 4

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 02 AK1.02 - Knowledge of the operational implications of the following concepts as they apply to HIGH REACTOR PRESSURE: Decay heat generation.

(CFR: 41.8 to 41.10) 3.1 21 295008 (APE 8) High Reactor Water Level / 2 08 AK2.08 - Knowledge of the interrelations between HIGH REACTOR WATER LEVEL and the following: Main turbine: Plant-Specific.

(CFR: 41.7 / 45.8) 3.4 22 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 01 AK3.01 - Knowledge of the reasons for the following responses as they apply to HIGH CONTAINMENT TEMPERATURE (MARK III CONTAINMENT ONLY): Increased containment cooling: Mark-III.

(CFR: 41.5 / 45.6) 3.6 23 295012 (APE 12) High Drywell Temperature /

5 295013 (APE 13) High Suppression Pool Temperature. / 5 295014 (APE 14) Inadvertent Reactivity Addition / 1 295015 (APE 15) Incomplete Scram / 1 04 AA1.04 - Ability to operate and/or monitor the following as they apply to INCOMPLETE SCRAM: Rod control and information system: Plant-specific.

(CFR: 41.7 / 45.6) 3.4 24 295017 (APE 17) Abnormal Offsite Release Rate / 9 295020 (APE 20) Inadvertent Containment Isolation / 5 & 7 03 AA2.03 - Ability to determine and/or interpret the following as they apply to INADVERTENT CONTAINMENT ISOLATION: Reactor power.

(CFR: 41.10 / 43.5 / 45.13) 3.7 25 295022 (APE 22) Loss of Control Rod Drive Pumps / 1 04.

08 G2.4.8 - Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

(CFR: 41.10 / 43.5 / 45.13) 3.8 26 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 01 EK1.01 - Knowledge of the operational implications of the following concepts as they apply to SECONDARY CONTAINMENT VENTILATION HIGH RADIATION: Personnel protection.

(CFR: 41.8 to 41.10) 3.8 27

ES-401 5

Form ES-401-1 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

1 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 04 K3.04 - Knolwedge of the effect that a loss or malfunction of the RHR/LPCI:

INJECTION MODE (PLANT SPECIFIC) will have on following: Adequate core cooling.

(CFR: 41.7 / 45.4) 4.6 28 205000 (SF4 SCS) Shutdown Cooling 02 K4.02 - Knowledge of SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) design feature(s) and/or interlock(s) which provide for the following:

High pressure isolation: Plant-Specific.

(CFR: 41.7) 3.7 29 206000 (SF2, SF4 HPCIS)

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

Low-Pressure Core Spray 04 K5.04 - Knowledge of the operational implications of the following concepts as they apply to LOW PRESSURE CORE SPRAY SYSTEM: Heat removal (transfer) mechanisms.

(CFR: 41.5 / 45.3) 2.8 30 209002 (SF2, SF4 HPCS)

High-Pressure Core Spray 01 K6.01 - Knowledge of the effect that a loss or malfunction of the following will have on the HIGH PRESSURE CORE SPRAY SYSTEM (HPCS): Electrical power: BWR-5,6 (CFR: 41.7 / 45.7) 3.6 31 211000 (SF1 SLCS) Standby Liquid Control 01 03 K1.01 - Knowledge of the physical connections and/or cause-effect relationships between STANDBY LIQUID CONTROL SYSTEM and the following:

Core spray line break detection: Plant-Specific.

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

A1.03 - Ability to predict and/or monitor changes in parameters associated with operating the STANDBY LIQUID CONTROL SYSTEM controls including: Pump discharge pressure.

(CFR: 41.5 / 45.5) 3.0 3.6 32 33 212000 (SF7 RPS) Reactor Protection 03 A2.03 - Ability to (a) predict the impacts of the following on the REACTOR PROTECTION SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Surveillance testing.

(CFR: 41.5 / 45.6) 3.3 34 215003 (SF7 IRM)

Intermediate-Range Monitor 02 A3.02 - Ability to monitor automatic operations of the INTERMEDIATE RANGE MONITOR (IRM) SYSTEM including:

Annunciator and alarm signals.

(CFR: 41.7 / 45.7) 3.3 35

ES-401 7

Form ES-401-1 215004 (SF7 SRMS) Source-Range Monitor 01 A4.01 - Ability to manually operate and/or monitor in the control room: SRM count rate and period.

(CFR: 41.7 / 45.5 to 45.8) 3.9 36 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor 01.

19 G2.1.19 - Ability to use plant computers to evaluate system or component status.

(CFR: 41.10 / 45.12) 3.9 37 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling 07 K1.07 - Knowledge of the physical connections and/or cause-effect relationships between REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) and the following: Leak detection.

(CFR: 41.2 to 41.9 / 45.7 to 45.8) 3.1 38 218000 (SF3 ADS) Automatic Depressurization 01 04 K2.01 - Knowledge of electrical power supplies to the following: ADS logic.

(CFR: 41.7)

A3.04 - Ability to monitor automatic operations of the AUTOMATIC DEPRESSURIZATION SYSTEM including:

Primary containment pressure.

(CFR: 41.7 / 45.7) 3.1 3.7 39 40 223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff 23 K3.23 - Knowledge of the effect that a loss or malfunction of the PRIMARY CONTAINMENT ISOLATION SYSTEM /

NUCLEAR STEAM SUPPLY SHUT-OFF will have on the following: High pressure core spray: Plant-Specific.

(CFR: 41.7 / 45.4) 3.6 41 239002 (SF3 SRV) Safety Relief Valves 08 02.

38 K4.08 - Knowledge of RELIEF / SAFETY VALVES design feature(s) and/or interlock(s) which provides for the following:

Opening of the SRV from either an electrical or mechanical signal.

(CFR: 41.7)

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

(CFR: 41.7 / 41.10 / 43.1 / 45.13) 3.6 3.6 42 43 259002 (SF2 RWLCS) Reactor Water Level Control 07 K5.07 - Knowledge of the operational implications of the following concepts as they apply to REACTOR WATER LEVEL CONTROL SYSTEM: Turbine speed control mechanisms: TDRFP.

(CFR: 41.5 / 45.3) 2.7 44 261000 (SF9 SGTS) Standby Gas Treatment 04 K6.04 - Knowledge of the effect that a loss or malfunction of the following will have on the STANDBY GAS TREATMENT SYSTEM: Process radiation monitoring.

(CFR: 41.7 / 45.7) 2.9 45 262001 (SF6 AC) AC Electrical Distribution 01 A1.01 - Ability to predict and/or monitor changes in parameters associated with operating the AC ELECTRICAL DISTRIBUTION controls including: Effect on instrumentation and controls of switching power supplies.

(CFR: 41.5 / 45.5) 3.1 46

ES-401 8

Form ES-401-1 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC) 02 A2.02 - Ability to (a) predict the impacts of the following on the UNINTERRUPTIBLE POWER SUPPLY (AC/DC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Over voltage (CFR: 41.5 / 45.6) 2.5 47 263000 (SF6 DC) DC Electrical Distribution 01 01 K2.01 - Knowledge of electrical power supplies to the following: Major DC loads.

(CFR: 41.7)

A3.01 - Ability to monitor automatic operations of the DC ELECTRICAL DISTRIBUTION including: Meters, dials, recorders, alarms, and indicating lights.

(CFR: 41.7 / 45.7) 3.1 3.2 48 49 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG 08 05 K4.08 - Knowledge of EMERGENCY GENERATORS (DIESEL/JET) design feature(s) and/or interlock(s) which provide for the following: Automatic startup (CFR: 41.7)

A4.05 - Ability to manually operate and/or monitor in the control room: Transfer of emergency generator (with load) to grid.

(CFR: 41.7 / 45.5 to 45.8) 3.8 3.6 50 51 300000 (SF8 IA) Instrument Air 04.

47 G2.4.47 - Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.

(CFR: 41.10 / 43.5 / 45.12) 4.2 52 400000 (SF8 CCS) Component Cooling Water 04 K1.04 - Knowledge of the physical connections and/or cause-effect relationships between CCWS and the following: Reactor coolant system, in order to determine source(s) of RCS leakage into CCWS.

(CFR: 41.2 to 41.9 / 45.7 to 45.8) 2.9 53 510000 (SF4 SWS*) Service Water (Normal and Emergency)

K/A Category Point Totals:

3 2

2 3

2 2

2 2

3 2

3 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 07 A3.07 - Ability to monitor automatic operations of the CONTROL ROD DRIVE HYDRAULIC SYSTEM including: HCU accumulator pressure/level.

(CFR: 41.7 / 45.7) 3.3 54 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 02 A4.02 - Ability to manually operate and/or monitor in the control room: Rod display module (lights and push buttons): BWR-6 (CFR: 41.7 / 45.5 to 45.8) 3.7 55 201006 (SF7 RWMS) Rod Worth Minimizer 202001 (SF1, SF4 RS) Recirculation 02.

42 G2.2.42 - Ability to recognize system parameters that are entry-level conditions for Technical Specifications.

(CFR: 41.7 / 41.10 / 43.2 / 43.3 / 45.3) 3.9 56 202002 (SF1 RSCTL) Recirculation Flow Control 204000 (SF2 RWCU) Reactor Water Cleanup 02 K1.02 - Knowledge of the physical connections and/or cause-effect relationships between REACTOR WATER CLEANUP SYSTEM and the following:

Recirculation system: Plant-specific.

(CFR: 41.2 to 41.9 / 45.7 to 45.8) 2.9 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 219000 (SF5 RHR SPC) RHR/LPCI:

Torus/Suppression Pool Cooling Mode 02 K2.02 - Knowledge of electrical power supplies to the following: Pumps.

(CFR: 41.7) 3.1 58 223001 (SF5 PCS) Primary Containment and Auxiliaries 226001 (SF5 RHR CSS) RHR/LPCI: Containment Spray Mode 03 K3.03 - Knowledge of the effect that a loss or malfunction of the RHR/LPCI:

CONTAINMENT SPRAY SYSTEM MODE will have on following:

Containment/drywell/suppression chamber components, continued operation with elevated pressure and/or temperature and/or level.

(CFR: 41.7 / 45.4) 2.9 59 230000 (SF5 RHR SPS) RHR/LPCI:

Torus/Suppression Pool Spray Mode 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup 07 K4.07 - Knowledge of FUEL POOL COOLING AND CLEAN-UP design feature(s) and/or interlock(s) which provide for the following: Supplemental heat removal capability.

(CFR: 41.7) 2.7 60 234000 (SF8 FH) Fuel-Handling Equipment 239001 (SF3, SF4 MRSS) Main and Reheat Steam 03 K5.03 - Knowledge of the operational implications of the following concepts as they apply to MAIN AND REHEAT STEAM SYSTEM: Definition and causes of thermal stress.

(CFR: 41.5 / 45.3) 2.7 61 239003 (SF9 MSVLCS) Main Steam Isolation Valve Leakage Control

ES-401 10 Form ES-401-1 241000 (SF3 RTPRS) Reactor/Turbine Pressure Regulating 11 K6.11 - Knowledge of the effect that a loss or malfunction of the following will have on the REACTOR/TURBINE PRESSURE REGULATING SYSTEM:

Main stop/throttle valves.

(CFR: 41.7 / 45.7) 3.4 62 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 256000 (SF2 CDS) Condensate 04 A1.04 - Ability to predict and/or monitor changes in parameters associated with operating the REACTOR CONDENSATE SYSTEM controls, including: Hotwell level.

(CFR: 41.5 / 45.5) 2.9 63 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 64 268000 (SF9 RW) Radwaste 271000 (SF9 OG) Offgas 272000 (SF7, SF9 RMS) Radiation Monitoring 286000 (SF8 FPS) Fire Protection 288000 (SF9 PVS) Plant Ventilation 01 A3.01 - Ability to monitor automatic operations of the PLANT VENTILATION SYSTEMS including: Isolation/initiation signals.

(CFR: 41.7 / 45.7) 3.8 65 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 295003 (APE 3) Partial or Complete Loss of AC Power / 6 03 AA2.03 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF AC POWER: Battery status: Plant-specific.

(CFR: 41.10 / 43.5 / 45.13) 3.5 76 295004 (APE 4) Partial or Total Loss of DC Power / 6 295005 (APE 5) Main Turbine Generator Trip /

3 295006 (APE 6) Scram / 1 295016 (APE 16) Control Room Abandonment

/ 7 01.

23 G2.1.23 - Ability to perform specific system and integrated plant procedures during all modes of plant operation.

(CFR: 41.10 / 43.5 / 45.2 / 45.6) 4.4 77 295018 (APE 18) Partial or Complete Loss of CCW / 8 01 AA2.01 - Ability to determine and/or interpret the following as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER:

Component temperatures.

(CFR: 41.10 / 43.5 / 45.13) 3.4 78 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 295024 High Drywell Pressure / 5 295025 (EPE 2) High Reactor Pressure / 3 02.

22 G2.2.22 - Knowledge of limiting conditions for operations and safety limits.

(CFR: 41.5 / 43.2 / 45.2) 4.7 79 295026 (EPE 3) Suppression Pool High Water Temperature / 5 03 EA2.03 - Ability to determine and/or interpret the following as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Reactor pressure.

(CFR: 41.10 / 43.5 / 45.13) 4.0 80 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 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 81 295031 (EPE 8) Reactor Low Water Level / 2 02 EA2.02 - Ability to determine and/or interpret the following as they apply to REACTOR LOW WATER LEVEL: Reactor power.

(CFR: 41.10 / 43.5 / 45.13)1 4.2 82 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 295038 (EPE 15) High Offsite Radioactivity Release Rate / 9

ES-401 12 Form ES-401-1 600000 (APE 24) Plant Fire On Site / 8 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 04.

20 G2.4.20 - Knowledge of the operational implications of EOP warnings, cautions, and notes.

(CFR: 41.10 / 43.5 / 45.13) 4.3 84 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 295014 (APE 14) Inadvertent Reactivity Addition / 1 295015 (APE 15) Incomplete Scram / 1 295017 (APE 17) High 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) 3.9 85 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 K/A Category Point Totals:

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 205000 (SF4 SCS) Shutdown Cooling 206000 (SF2, SF4 HPCIS)

High-Pressure Coolant Injection 207000 (SF4 IC) Isolation (Emergency) Condenser 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 02 A2.02 - Ability to (a) predict the impacts of the following on the SOURCE RANGE MONITOR (SRM) SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: SRM inop condition.

(CFR: 41.5 / 45.6) 3.7 86 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor 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 87 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling 01.

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

(CFR: 41.10 / 43.5 / 45.12) 4.6 88 218000 (SF3 ADS) Automatic Depressurization 223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff 239002 (SF3 SRV) Safety Relief Valves 259002 (SF2 RWLCS) Reactor Water Level Control 261000 (SF9 SGTS) Standby Gas Treatment 05 A2.05 - Abiliity to (a) predict the impacts of the following on 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: Fan trips.

(CFR: 41.5 / 45.6) 3.1 89 262001 (SF6 AC) AC Electrical Distribution 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC)

ES-401 15 Form ES-401-1 263000 (SF6 DC) DC Electrical Distribution 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG 300000 (SF8 IA) Instrument Air 01.

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

(CFR: 41.10 / 43.2 / 45.12) 4.0 90 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 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 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 prediction, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Recirculation pump speed mismatch between loops:

Plant-specific.

(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 System and Auxiliaries 02.

40 G2.2.40 - Ability to apply Technical Specifications for a system.

(CFR: 41.10 / 43.2 / 43.5 / 45.3) 4.7 92 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 271000 (SF9 OG) Offgas

ES-401 17 Form ES-401-1 272000 (SF7, SF9 RMS) Radiation Monitoring 11 A2.11 - 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: Leakage and/or breaks from contaminated systems to atmosphere or to other process systems.

(CFR: 41.5 / 45.6) 3.7 93 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 K/A Category Point Totals:

2 1

Group Point Total:

3