ML21144A320

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ES-401-1
ML21144A320
Person / Time
Site: Clinton Constellation icon.png
Issue date: 04/13/2021
From: Gregory Roach
Operations Branch III
To:
NRC/RGN-III/DRS/OLB
Roach G
Shared Package
ML20136A301 List:
References
Download: ML21144A320 (16)
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Text

ES-401 1 Form ES-401-1 Facility: Clinton Power Station Date of Exam: April 2021 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 3 4 4 3 3 3 20 4 3 7 Emergency and N/A N/A 2 1 1 1 2 1 1 7 2 1 3 Abnormal Plant Evolutions Tier Totals 4 5 5 5 4 4 27 6 4 10 1 2 3 3 3 2 2 3 3 1 2 2 26 2 3 5 2.

Plant 2 1 1 1 1 1 1 1 1 2 1 1 12 1 2 3 Systems Tier Totals 3 4 4 4 3 3 4 4 3 3 3 38 3 5 8

3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 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 #

AA1.02 Ability to operate and/or monitor the 295001 (APE 1) Partial or Complete Loss of X following as they apply to Partial Or 3.3 1 Forced Core Flow Circulation / 1 & 4 Complete Loss Of Forced Core Flow Circulation: RPS (CFR: 41.7 / 45.6)

AA2.02 Ability to determine and/or interpret 295003 (APE 3) Partial or Complete Loss of X the following as they apply to Partial Or 4.2 2 AC Power / 6 Complete Loss Of A.C. Power: Reactor power / pressure / and level (CFR: 41.10 / 43.5 / 45.13) 2.2.37 Ability to determine operability and/or 295004 (APE 4) Partial or Total Loss of DC X availability of safety related equipment. 3.6 3 Power / 6 (CFR: 41.7 / 43.5 / 45.12)

AK1.03 Knowledge of the operational 295005 (APE 5) Main Turbine Generator Trip / X implications of the following concepts as 3.5 4 3 they apply to Main Turbine Generator Trip:

Pressure effects on reactor level (CFR: 41.8 to 41.10)

AK2.04 Knowledge of the interrelations 295006 (APE 6) Scram / 1 X between SCRAM and the following: Turbine 3.6 5 trip logic (CFR: 41.7 / 45.8) 2.4.34 Knowledge of RO tasks performed 295016 (APE 16) Control Room Abandonment X outside the main control room during an 4.2 6

/7 emergency and the resultant operational effects. (CFR: 41.10 / 43.5 / 45.13)

AK2.01 Knowledge of the interrelations 295018 (APE 18) Partial or Complete Loss of X between Partial Or Complete Loss Of 3.3 7 CCW / 8 Component Cooling Water and the following: System loads (CFR: 41.7 / 45.8)

AK3.03 Knowledge of the reasons for the 295019 (APE 19) Partial or Complete Loss of X following responses as they apply to Partial 3.2 8 Instrument Air / 8 Or Complete Loss Of Instrument Air:

Service air isolations (CFR: 41.5 / 45.6)

AA1.02 Ability to operate and/or monitor the 295021 (APE 21) Loss of Shutdown Cooling / X following as they apply to Loss Of Shutdown 3.5 9 4 Cooling: RHR/shutdown cooling (CFR: 41.7 / 45.6)

AA2.02 Ability to determine and/or interpret 295023 (APE 23) Refueling Accidents / 8 X the following as they apply to Refueling 3.4 10 Accidents: Fuel pool level (CFR: 41.10 / 43.5 / 45.13) 2.1.28 Knowledge of the purpose and 295024 High Drywell Pressure / 5 X function of major system components and 4.1 11 controls. (CFR: 41.7)

EK1.04 Knowledge of the operational 295025 (EPE 2) High Reactor Pressure / 3 X implications of the following concepts as 3.6 12 they apply to High Reactor Pressure: Decay heat generation (CFR: 41.8 to 41.10)

EK2.04 Knowledge of the interrelations 295026 (EPE 3) Suppression Pool High Water X between Suppression Pool High Water 2.5 13 Temperature / 5 Temperature and the following:

SPDS/ERIS/CRIDS/GDS (CFR: 41.7 / 45.8)

EK3.01 Knowledge of the reasons for the 295027 (EPE 4) High Containment X following responses as they apply to High 3.7 14 Temperature (Mark III Containment Only) / 5 Containment Temperature (Mark III Containment Only): Emergency depressurization: Mark-III (CFR: 41.5 / 45.6)

Not Applicable 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only) / 5 EA1.02 Ability to operate and/or monitor the 295030 (EPE 7) Low Suppression Pool Water X following as they apply to Low Suppression 3.4 15 Level / 5 Pool Water Level: RCIC (CFR: 41.7 / 45.6)

ES-401 3 Form ES-401-1 EA2.02 Ability to determine and/or interpret 295031 (EPE 8) Reactor Low Water Level / 2 X the following as they apply to Reactor Low 4.0 16 Water Level: Reactor power (CFR: 41.10 / 43.5 / 45.13)

EK3.02 Knowledge of the reasons for the 295037 (EPE 14) Scram Condition Present X following responses as they apply to 4.3 17 and Reactor Power Above APRM Downscale SCRAM CONDITION PRESENT AND or Unknown / 1 REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: SBLC injection (CFR: 41.5 / 45.6)

EK1.02 Knowledge of the operational 295038 (EPE 15) High Offsite Radioactivity X implications of the following concepts as 4.2 18 Release Rate / 9 they apply to High Off-Site Release Rate:

Protection of the general public (CFR: 41.8 to 41.10)

AK2.01 Knowledge of the interrelations 600000 (APE 24) Plant Fire On Site / 8 X between Plant Fire On Site and the 2.6 19 following: Sensors / detectors and valves AK3.02 Knowledge of the reasons for the 700000 (APE 25) Generator Voltage and X following responses as they apply to 3.6 20 Electric Grid Disturbances / 6 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)

K/A Category Totals: 3 4 4 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 #

AK3.06 Knowledge of the reasons for the 295002 (APE 2) Loss of Main Condenser X following responses as they apply to Loss 2.9 21 Vacuum / 3 Of Main Condenser Vacuum: Air ejector flow (CFR: 41.5 / 45.6) 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 AA1.01 Ability to operate and/or monitor 295011 (APE 11) High Containment X the following as they apply to High 3.6 22 Temperature (Mark III Containment only) / 5 Containment Temperature: Containment ventilation/cooling system (CFR: 41.7 / 45.6) 295012 (APE 12) High Drywell Temperature /

5 AA1.01 Ability to operate and/or monitor 295013 (APE 13) High Suppression Pool X the following as they apply to High 3.9 23 Temperature. / 5 Suppression Pool Temperature:

Suppression pool cooling (CFR: 41.7 / 45.6) 295014 (APE 14) Inadvertent Reactivity Addition / 1 AA2.02 Ability to determine and/or interpret 295015 (APE 15) Incomplete Scram / 1 X the following as they apply to Incomplete 4.1 24 Scram: Control rod position (CFR: 41.10 / 43.5 / 45.13) 2.2.44 Ability to interpret control room 295017 (APE 17) Abnormal Offsite Release X indications to verify the status and 4.2 25 Rate / 9 operation of a system and understand how operator actions and directives affect plant and system conditions.

(CFR: 41.5 / 43.5 / 45.12) 295020 (APE 20) Inadvertent Containment Isolation / 5 & 7 295022 (APE 22) Loss of Control Rod Drive Pumps / 1 EK1.01 Knowledge of the operational 295029 (EPE 6) High Suppression Pool Water X implications of the following concepts as 3.4 26 Level / 5 they apply to High Suppression Pool Water Level: Containment integrity (CFR: 41.8 to 41.10) 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

ES-401 5 Form ES-401-1 EK2.03 Knowledge of the interrelations 500000 (EPE 16) High Containment Hydrogen X between High Containment Hydrogen 3.3 27 Concentration / 5 Concentrations the following:

Containment Atmosphere Control System (CFR: 41.7 / 45.8)

K/A Category Point Totals: 1 1 1 2 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) X 2.4.31 Knowledge of annunciator alarms, 4.2 28 RHR/LPCI: Injection Mode indications, or response procedures.

(CFR: 41.10 / 45.3) 205000 (SF4 SCS) Shutdown Cooling X K1.06 Knowledge of the physical connections 3.2 29 and/or cause-effect relationships between Shutdown Cooling System (RHR Shutdown Cooling Mode) and the following: A.C.

electrical power (CFR: 41.2 to 41.9 / 45.7 to 45.8) 206000 (SF2, SF4 HPCIS) Not Applicable High-Pressure Coolant Injection 207000 (SF4 IC) Isolation Not Applicable (Emergency) Condenser 209001 (SF2, SF4 LPCS) X K2.03 Knowledge of electrical power supplies 2.9 30 Low-Pressure Core Spray to the following: Initiation logic (CFR: 41.7) 209002 (SF2, SF4 HPCS) X K3.02 Knowledge of the effect that a loss or 3.3 31 High-Pressure Core Spray malfunction of the High Pressure Core Spray System (HPCS) will have on following:

Standby liquid control system (CFR: 41.7 / 45.4) 211000 (SF1 SLCS) Standby Liquid X K4.10 Knowledge of Standby Liquid Control 2.8 32 Control System design feature(s) and/or interlocks which provide for the following: Over pressure protection (CFR 41.7) 212000 (SF7 RPS) Reactor Protection X K5.02 Knowledge of the operational 3.3 33 implications of the following concepts as they apply to Reactor Protection System: Specific logic arrangements (CFR: 41.5 / 45.3) 215003 (SF7 IRM) X K6.04 Knowledge of the effect that a loss or 3.0 34 Intermediate-Range Monitor malfunction of the following will have on the Intermediate Range Monitor (IRM) System:

Detectors (CFR: 41.7 / 45.7) 215004 (SF7 SRMS) Source-Range X A1.06 Ability to predict and/or monitor 3.1 35 Monitor changes in parameters associated with operating the Source Range Monitor (SRM)

System controls including: Lights and alarms (CFR: 41.5 / 45.5)

K1.01 Knowledge of the physical connections X 3.6 36 and/or cause-effect relationships between Source Range Monitor (SRM) System and the following: Reactor protection system (CFR: 41.2 to 41.9 / 45.7 to 45.8) 215005 (SF7 PRMS) Average Power X A2.03 Ability to (a) predict the impacts of the 3.6 37 Range Monitor/Local Power Range following on the Average Power Range Monitor/Local Power Range Monitor System; Monitor and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Inoperative trip (all causes)

(CFR: 41.5 / 45.6)

X K3.01 Knowledge of the effect that a loss or 4.0 38 malfunction of the Average Power Range Monitor/Local Power Range Monitor System will have on following: RPS (CFR: 41.7 / 45.4) 217000 (SF2, SF4 RCIC) Reactor X A3.01 Ability to monitor automatic operations 3.5 39 Core Isolation Cooling of the Reactor Core Isolation Cooling System (RCIC) including: Valve operation (CFR 41.7 / 45.7)

X K4.06 Knowledge of reactor core isolation 3.5 40 cooling system (RCIC) design feature(s) and/or interlocks which provide for the following: Manual initiation (CFR: 41.7)

ES-401 7 Form ES-401-1 218000 (SF3 ADS) Automatic X A4.12 Ability to manually operate and/or 4.2 41 Depressurization monitor in the control room: Reactor vessel water level (CFR: 41.7 / 45.5 to 45.8) 223002 (SF5 PCIS) Primary X 2.2.40 Ability to apply Technical 3.4 42 Containment Isolation/Nuclear Steam Specifications for a system.

(CFR: 41.10 / 43.2 / 43.5 / 45.3)

Supply Shutoff 239002 (SF3 SRV) Safety Relief X K2.01 Knowledge of electrical power supplies 2.8 43 Valves to the following: SRV solenoids (CFR: 41.7) 259002 (SF2 RWLCS) Reactor Water X K3.06 Knowledge of the effect that a loss or 2.8 44 Level Control malfunction of the Reactor Water Level Control System will have on following: Main turbine (CFR: 41.7 / 45.4) 261000 (SF9 SGTS) Standby Gas X K4.04 Knowledge of Standby Gas Treatment 2.7 45 Treatment System design feature(s) and/or interlocks which provide for the following: Radioactive particulate filtration (CFR 41.7) 262001 (SF6 AC) AC Electrical X K5.02 Knowledge of the operational 2.6 46 Distribution implications of the following concepts as they apply to A.C. Electrical Distribution: Breaker control (CFR: 41.5 / 45.3)

X A1.02 Ability to predict and/or monitor 3.1 47 changes in parameters associated with operating the A.C. Electrical Distribution controls including: Effects of loads when energizing a bus (CFR: 41.5 / 45.5) 262002 (SF6 UPS) Uninterruptable X K6.01 Knowledge of the effect that a loss or 2.7 48 Power Supply (AC/DC) malfunction of the following will have on the Uninterruptable Power Supply (A.C./D.C.) :

A.C. electrical power (CFR: 41.7 / 45.7) 263000 (SF6 DC) DC Electrical X A1.01 Ability to predict and/or monitor 2.5 49 Distribution changes in parameters associated with operating the D.C. Electrical Distribution controls including: Battery charging/

discharging rate (CFR: 41.5 / 45.5) 264000 (SF6 EGE) Emergency X A2.01 Ability to (a) predict the impacts of the 3.5 50 Generators (Diesel/Jet) EDG following on the Emergency Generators (Diesel/Jet) and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:

Parallel operation of emergency generator (CFR: 41.5 / 45.6) 300000 (SF8 IA) Instrument Air X A2.01 Ability to (a) predict the impacts of the 2.9 51 following on the INSTRUMENT AIR SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation:

Air dryer and filter malfunctions (CFR: 41.5 / 45.6)

X K2.01 Knowledge of electrical power supplies 2.8 52 to the following: Instrument air compressor (CFR: 41.7) 400000 (SF8 CCS) Component X A4.01 Ability to manually operate and / or 3.1 53 Cooling Water monitor in the control room: CCW indications and control (CFR: 41.7 / 45.5 to 45.8) 510000 (SF4 SWS*) Service Water Not Applicable (Normal and Emergency)

K/A Category Point Totals: 2 3 3 3 2 2 3 3 1 2 2 Group Point Total: 26

ES-401 8 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 2 (RO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

201001 (SF1 CRDH) CRD Hydraulic 201002 (SF1 RMCS) Reactor Manual Not Applicable Control 201003 (SF1 CRDM) Control Rod and 2.1.7 Ability to evaluate plant performance X and make operational judgements based on 4.4 54 Drive Mechanism operating characteristics, reactor behavior, and instrument interpretation.

(CFR: 41.5 / 43.5 / 45.12 / 45.13) 201004 (SF7 RSCS) Rod Sequence Not Applicable Control 201005 (SF1, SF7 RCIS) Rod Control K1.05 Knowledge of the physical X connections and/or cause-effect 3.5 55 and Information relationships between Rod Control And Information System (RCIS) and the following: Rod action control system:

BWR-6 (CFR: 41.2 to 41.9 / 45.7 to 45.8) 201006 (SF7 RWMS) Rod Worth Not Applicable Minimizer 202001 (SF1, SF4 RS) Recirculation K2.03 Knowledge of electrical power X supplies to the following: Recirculation 2.7 56 system valves (CFR: 41.7) 202002 (SF1 RSCTL) Recirculation Flow Control 204000 (SF2 RWCU) Reactor Water K3.01 Knowledge of the effect that a loss or X malfunction of the Reactor Water Cleanup 3.2 57 Cleanup System will have on following: Reactor water quality (CFR: 41.7 / 45.4) 214000 (SF7 RPIS) Rod Position Not Applicable Information 215001 (SF7 TIP) Traversing In-Core Probe 215002 (SF7 RBMS) Rod Block Monitor Not Applicable 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: K4.02 Knowledge of RHR/LPCI:

X Containment Spray System Mode design 2.8 58 Containment Spray Mode feature(s) and/or interlocks which provide for the following: Redundancy (CFR 41.7) 230000 (SF5 RHR SPS) RHR/LPCI: Not Applicable Torus/Suppression Pool Spray Mode 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup 234000 (SF8 FH) Fuel-Handling K5.03 Knowledge of the operational X implications of the following concepts as 2.9 59 Equipment they apply to Fuel Handling Equipment:

Water as a shield against radiation (CFR: 41.5 / 45.3) 239001 (SF3, SF4 MRSS) Main and K6.08 Knowledge of the effect that a loss or X malfunction of the following will have on the 3.3 60 Reheat Steam Main And Reheat Steam System: Main condenser vacuum (CFR: 41.7 / 45.7)

ES-401 9 Form ES-401-1 239003 (SF9 MSVLCS) Main Steam Not Applicable Isolation Valve Leakage Control 241000 (SF3 RTPRS) Reactor/Turbine A1.02 Ability to predict and/or monitor X changes in parameters associated with 4.1 61 Pressure Regulating operating the Reactor/Turbine Pressure Regulating System controls including:

Reactor power (CFR: 41.5 / 45.5) 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 256000 (SF2 CDS) Condensate 259001 (SF2 FWS) Feedwater A3.10 Ability to monitor automatic operation X of the Reactor Feedwater System including: 3.4 62 Pump trips (CFR: 41.7 / 45.7) 268000 (SF9 RW) Radwaste 271000 (SF9 OG) Offgas 272000 (SF7, SF9 RMS) Radiation A2.01 Ability to (a) predict the impacts of the X following on the Radiation Monitoring 3.7 63 Monitoring System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Fuel element failure (CFR: 41.5 / 45.6) 286000 (SF8 FPS) Fire Protection 288000 (SF9 PVS) Plant Ventilation A3.01 Ability to monitor automatic X operations of the Plant Ventilation Systems 3.8 64 including: Isolation/initiation signals (CFR: 41.7 / 45.7) 290001 (SF5 SC) Secondary A4.02 Ability to manually operate and/or X monitor in the control room: Reactor 3.3 65 Containment building area temperatures (CFR: 41.7 / 45.5 to 45.8) 290003 (SF9 CRV) Control Room Ventilation 290002 (SF4 RVI) Reactor Vessel Internals 51001 (SF8 CWS*) Circulating Water Not Applicable Group Point Total:

K/A Category Point Totals: 1 1 1 1 1 1 1 1 2 1 1 12

ES-401 10 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

295001 (APE 1) Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 295003 (APE 3) Partial or Complete Loss of AC Power / 6 AA2.02 Ability to determine and/or interpret 295004 (APE 4) Partial or Total Loss of DC X the following as they apply to Partial Or 3.9 76 Power / 6 Complete Loss Of D.C. Power: Extent of partial or complete loss of D.C. power (CFR: 41.10 / 43.5 / 45.13) 295005 (APE 5) Main Turbine Generator Trip /

3 295006 (APE 6) Scram / 1 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 2.4.30 Knowledge of events related to 295021 (APE 21) Loss of Shutdown Cooling / X system operation/status that must be 4.1 77 4 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)

AA2.01 Ability to determine and/or interpret 295023 (APE 23) Refueling Accidents / 8 X the following as they apply to Refueling 4.0 78 Accidents: Area Radiation levels (CFR: 41.10 / 43.5 / 45.13) 295024 High Drywell Pressure / 5 295025 (EPE 2) High Reactor Pressure / 3 2.2.25 Knowledge of the bases in Technical 295026 (EPE 3) Suppression Pool High Water X Specifications for limiting conditions for 4.2 80 Temperature / 5 operations and safety limits.

(CFR: 41.5 / 41.7 / 43.2)

EA2.02 Ability to determine and/or interpret 295027 (EPE 4) High Containment X the following as they apply to High 3.7 81 Temperature (Mark III Containment Only) / 5 Containment Temperature (Mark III Containment Only): Containment pressure (CFR: 41.10 / 43.5 / 45.13)

Not Applicable 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only) / 5 295030 (EPE 7) Low Suppression Pool Water Level / 5 EA2.03 Ability to determine and/or interpret 295031 (EPE 8) Reactor Low Water Level / 2 X the following as they apply to REACTOR 4.2 79 LOW WATER LEVEL: Reactor Pressure (CFR: 41.10 / 43.5 / 45.13) 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 2.4.50 Ability to verify system alarm 295038 (EPE 15) High Offsite Radioactivity X setpoints and operate controls identified in 4.0 82 Release Rate / 9 the alarm response manual.

(CFR: 41.10 / 43.5 / 45.3)

ES-401 11 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 12 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 AA2.01 Ability to determine and/or interpret 295008 (APE 8) High Reactor Water Level / 2 X the following as they apply to High Reactor 3.9 83 Water Level: Reactor water level (CFR: 41.10 / 43.5 / 45.13) 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 AA2.01 Ability to determine and/or interpret 295014 (APE 14) Inadvertent Reactivity X the following as they apply to Inadvertent 4.2 84 Addition / 1 Reactivity Addition: Reactor power (CFR: 41.10 / 43.5 / 45.13) 295015 (APE 15) Incomplete Scram / 1 295017 (APE 17) Abnormal Offsite Release Rate / 9 295020 (APE 20) Inadvertent Containment Isolation / 5 & 7 295022 (APE 22) Loss of Control Rod Drive Pumps / 1 295029 (EPE 6) High Suppression Pool Water Level / 5 295032 (EPE 9) High Secondary Containment Area Temperature / 5 295033 (EPE 10) High Secondary Containment Area Radiation Levels / 9 295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9 295035 (EPE 12) Secondary Containment High Differential Pressure / 5 2.4.18 Knowledge of the specific bases for 295036 (EPE 13) Secondary Containment X EOPs (CFR: 41.10 / 43.1 / 45.13) 4.0 85 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 13 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) Not Applicable High-Pressure Coolant Injection 207000 (SF4 IC) Isolation Not Applicable (Emergency) Condenser 209001 (SF2, SF4 LPCS) X 2.4.9 Knowledge of low power/shutdown 4.2 86 Low-Pressure Core Spray implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.

(CFR: 41.10 / 43.5 / 45.13) 209002 (SF2, SF4 HPCS)

High-Pressure Core Spray 211000 (SF1 SLCS) Standby Liquid X A2.05 Ability to (a) predict the impacts of the 3.4 87 Control following on the Standby Liquid Control System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of SBLC tank heaters (CFR: 41.5 / 45.6) 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 X 2.4.46 Ability to verify that the alarms are 4.2 88 Containment Isolation/Nuclear Steam consistent with the plant conditions.

(CFR: 41.10 / 43.5 / 45.3 / 45.12)

Supply Shutoff 239002 (SF3 SRV) Safety Relief X A2.03 Ability to (a) predict the impacts of the 4.2 89 Valves following on the RELIEF/SAFETY VALVES; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Stuck Open SRV (CFR: 41.5 / 45.6) 259002 (SF2 RWLCS) Reactor Water X 2.1.20 Ability to interpret and execute 4.6 90 Level Control procedure steps.

(CFR: 41.10 / 43.5 / 45.12) 261000 (SF9 SGTS) Standby Gas Treatment 262001 (SF6 AC) AC Electrical Distribution 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC) 263000 (SF6 DC) DC Electrical Distribution

ES-401 14 Form ES-401-1 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG 300000 (SF8 IA) Instrument Air 400000 (SF8 CCS) Component Cooling Water 510000 (SF4 SWS*) Service Water Not Applicable (Normal and Emergency)

K/A Category Point Totals: 2 3 Group Point Total: 5

ES-401 15 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 A2.04 Ability to (a) predict the impacts of the X following on the Control Rod Drive Hydraulic 3.9 91 System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Scram conditions (CFR: 41.5 / 45.6) 201002 (SF1 RMCS) Reactor Manual Not Applicable Control 201003 (SF1 CRDM) Control Rod and Drive Mechanism 201004 (SF7 RSCS) Rod Sequence Not Applicable Control 201005 (SF1, SF7 RCIS) Rod Control and Information 201006 (SF7 RWMS) Rod Worth Not Applicable Minimizer 202001 (SF1, SF4 RS) Recirculation 202002 (SF1 RSCTL) Recirculation Flow Control 204000 (SF2 RWCU) Reactor Water Cleanup 214000 (SF7 RPIS) Rod Position Not Applicable Information 215001 (SF7 TIP) Traversing In-Core Probe 215002 (SF7 RBMS) Rod Block Not Applicable Monitor 216000 (SF7 NBI) Nuclear Boiler Instrumentation 219000 (SF5 RHR SPC) RHR/LPCI:

Torus/Suppression Pool Cooling Mode 223001 (SF5 PCS) Primary 2.1.23 Ability to perform specific system and X integrated plant procedures during all modes 4.4 92 Containment and Auxiliaries of plant operation.

(CFR: 41.10 / 43.5 / 45.2 / 45.6) 226001 (SF5 RHR CSS) RHR/LPCI:

Containment Spray Mode 230000 (SF5 RHR SPS) RHR/LPCI: Not Applicable 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 Not Applicable Isolation Valve Leakage Control 241000 (SF3 RTPRS)

Reactor/Turbine Pressure Regulating 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 256000 (SF2 CDS) Condensate

ES-401 16 Form ES-401-1 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 2.4.45 Ability to prioritize and interpret the X significance of each annunciator or alarm. 4.3 93 Ventilation (CFR: 41.10 / 43.5 / 45.3 / 45.12) 290002 (SF4 RVI) Reactor Vessel Internals 51001 (SF8 CWS*) Circulating Water Not Applicable K/A Category Point Totals: 1 2 Group Point Total: 3

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