ML15259A298

2015 Duane Arnold Energy Center Initial License Examination Forms ES-401-1 and ES-401-3

ML15259A298
Person / Time
Site:	Duane Arnold
Issue date:	08/20/2015
From:	NRC/RGN-III
To:	NextEra Energy Duane Arnold
Zoia, C D
Shared Package
ML15118A361	List: ML15259A293 ML15259A298 ML15259A300 ML15259A302 ML15259A305 ML15260A344
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ES-401 BWR Examination Outline Form ES-401-1 Facility: Duane Arnold Energy Center Date of Exam: 4/6/15 - 4/17/15 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G Total 1 2 3 4 5 6 1 2 3 4 *

1. 1 4 2 3 4 4 3 20 3 4 7 Emergency & N/A N/A 2 1 1 2 2 1 0 7 1 2 3 Abnormal Plant Evolutions Tier Totals 5 3 5 6 5 3 27 4 6 10 1 3 2 3 3 3 2 2 2 3 2 1 26 3 2 5 2.

Plant 2 1 2 2 1 0 1 1 0 1 1 2 12 0 1 2 3 Systems Tier Totals 4 4 5 4 3 3 3 2 3 3 4 38 4 4 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 10 7 Categories 2 3 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 outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).

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 associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; 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 shall be selected. 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 importance ratings (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 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.

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)

K K K A A E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 Ability to determine and/or interpret the following as 295001 Partial or Complete Loss of Forced 0 they apply to PARTIAL OR COMPLETE LOSS OF 3.1 1 Core Flow Circulation / 1 & 4 5 FORCED CORE FLOW CIRCULATION: Jet pump operability. CFR: 41.10 2.1.25: Ability to interpret reference materials, such 295003 Partial or Complete Loss of AC / 6 R 3.9 2 as graphs, curves, tables, etc. CFR: 41.10 Knowledge of the operational implications of the 0 following concepts as they apply to PARTIAL OR 295004 Partial or Total Loss of DC Pwr / 6 2.9 3 3 COMPLETE LOSS OF D.C. POWER: Electrical bus divisional separation. CFR: 41.8 to 41.10 Knowledge of the interrelations between MAIN 0

295005 Main Turbine Generator Trip / 3 TURBINE GENERATOR TRIP and the following: 3.2 4 8

A.C. electrical distribution. CFR: 41.7 Knowledge of the reasons for the following responses 0

295006 SCRAM / 1 as they apply to SCRAM : Recirculation pump speed 3.2 5 6

reduction. CFR: 41.5 Ability to operate and/or monitor the following as they 0

295016 Control Room Abandonment / 7 apply to CONTROL ROOM ABANDONMENT : A.C. 3.1 6 4

electrical distribution. CFR: 41.7 Ability to determine and/or interpret the following as 0 they apply to PARTIAL OR COMPLETE LOSS OF 295018 Partial or Total Loss of CCW / 8 3.1 7 2 COMPONENT COOLING WATER : Cooling water temperature. CFR: 41.10 2.2.44: Ability to interpret control room indications to verify the status and operation of a system, and 295019 Partial or Total Loss of Inst. Air / 8 R 4.2 8 understand how operator actions and directives affect plant and system conditions. CFR: 41.5 Knowledge of the operational implications of the 0 following concepts as they apply to LOSS OF 295021 Loss of Shutdown Cooling / 4 3.6 9 1 SHUTDOWN COOLING : Decay heat. CFR: 41.8 to 41.10 Knowledge of the interrelations between REFUELING 0

295023 Refueling Acc / 8 ACCIDENTS and the following: Fuel handling 3.3 10 1

equipment. CFR: 41.7 Knowledge of the reasons for the following responses 0

295024 High Drywell Pressure / 5 as they apply to HIGH DRYWELL PRESSURE : 3.7 11 8

Containment spray. CFR: 41.5 Ability to operate and/or monitor the following as they 0 apply to HIGH REACTOR PRESSURE:

295025 High Reactor Pressure / 3 3.8 12 2 Reactor/turbine pressure regulating system. CFR:

41.7 Ability to determine and/or interpret the following as 295026 Suppression Pool High Water 0 they apply to SUPPRESSION POOL HIGH WATER 3.9 13 Temp. / 5 3 TEMPERATURE: Reactor pressure. CFR: 41.10 295027 High Containment Temperature / 5 (Not Applicable to Plant Design)

Knowledge of the operational implications of the 0 following concepts as they apply to HIGH DRYWELL 295028 High Drywell Temperature / 5 3.5 14 1 TEMPERATURE : Reactor water level measurement.

CFR: 41.8 to 41.10

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)

K K K A A E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 Ability to operate and/or monitor the following as they 0

295030 Low Suppression Pool Wtr Lvl / 5 apply to LOW SUPPRESSION POOL WATER 3.5 15 5

LEVEL: HPCI. CFR: 41.7 Knowledge of the reasons for the following responses 0 as they apply to REACTOR LOW WATER LEVEL:

295031 Reactor Low Water Level / 2 3.9 16 1 Automatic depressurization system actuation. CFR:

41.5 Ability to operate and/or monitor the following as they 295037 SCRAM Condition Present 0 apply to SCRAM CONDITION PRESENT AND and Reactor Power Above APRM 4.5 17 4 REACTOR POWER ABOVE APRM DOWNSCALE Downscale or Unknown / 1 OR UNKNOWN : SBLC. CFR: 41.7 Ability to determine and/or interpret the following as 0

295038 High Off-site Release Rate / 9 they apply to HIGH OFF-SITE RELEASE RATE : Off- 3.3 18 1

site. CFR: 41.10 2.4.45: Ability to prioritize and interpret the 600000 Plant Fire On Site / 8 R significance of each annunciator or alarm. CFR: 4.1 19 41.10 Knowledge of the operational implications of the lfollowing concepts as they apply to GENERATOR 700000 Generator Voltage and Electric Grid 0 VOLTAGE AND ELECTRIC GRID DISTURBANCES: 3.3 20 Disturbances / 6 1 Definition of terms: volts, watts, amps, VARs, power factor. CFR: 41.4, 41.5, 41.7, 41.10 20 K/A Category Totals: 4 2 3 4 4 3 Group Point Total: 20

/7

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)

K K K A A E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 295002 Loss of Main Condenser Vac / 3 295007 High Reactor Pressure / 3 Ability to operate and/or monitor the following as they 0

295008 High Reactor Water Level / 2 apply to HIGH REACTOR WATER LEVEL: RCIC. 3.3 21 5

CFR: 41.7 Ability to determine and/or interpret the following as 0

295009 Low Reactor Water Level / 2 they apply to LOW REACTOR WATER LEVEL : 3.6 22 2

Steam flow/feed flow mismatch. CFR: 41.10 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 295013 High Suppression Pool Temp. / 5 Knowledge of the interrelations between 0

295014 Inadvertent Reactivity Addition / 1 INADVERTENT REACTIVITY ADDITION and the 3.2 23 4

following: Void concentration. CFR: 41.7 295015 Incomplete SCRAM / 1 295017 High Off-site Release Rate / 9 Knowledge of the operational implications of the 0 following concepts as they apply to INADVERTENT 295020 Inadvertent Cont. Isolation / 5 & 7 3.7 24 1 CONTAINMENT ISOLATION : Loss of normal heat sink. CFR: 41.8 to 41.10 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvl / 5 Ability to operate and/or monitor the following as they 295032 High Secondary Containment 0 apply to HIGH SECONDARY CONTAINMENT AREA 3.6 25 Area Temperature / 5 1 TEMPERATURE : Area temperature monitoring system. CFR: 41.7 295033 High Secondary Containment Area Radiation Levels / 9 Knowledge of the reasons for the following responses 295034 Secondary Containment 0 as they apply to SECONDARY CONTAINMENT 3.6 26 Ventilation High Radiation / 9 5 VENTILATION HIGH RADIATION : Manual SCRAM and depressurization: Plant-Specific. CFR: 41.5 295035 Secondary Containment High Differential Pressure / 5 295036 Secondary Containment High Sump/Area Water Level / 5 Knowledge of the reasons for the following responses 0 as they apply to HIGH PRIMARY CONTAINMENT 500000 High CTMT Hydrogen Conc. / 5 2.9 27 1 HYDROGEN CONCENTRATIONS: Initiation of containment atmosphere control system. CFR: 41.5 K/A Category Point Totals: 1 1 2 2 1 0 Group Point Total: 7 7/3

ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO)

K K K K K K A A A A System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 Knowledge of electrical power supplies to the following: Valves. CFR: 41.7 / 2.5 33 Knowledge of RHR/LPCI: INJECTION MODE /

203000 RHR/LPCI: Injection 0 0 (PLANT SPECIFIC) design feature(s) and/or Mode 2 6 interlocks which provide for the following:

Adequate pump net positive suction head (interlock suction valve open): Plant-Specific. 3.5 28 CFR: 41.7.

Knowledge of the operational implications of the following concepts as they apply to SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) : Heat removal mechanisms. CFR: 41.5 / 2.8 29 0 0 205000 Shutdown Cooling Knowledge of the physical connections and/or /

1 3 cause effect relationships between 3.6 30 SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) and the following: Reactor pressure. CFR: 41.2 to 41.9 Knowledge of the effect that a loss or malfunction of the following will have on the HIGH PRESSURE COOLANT INJECTION 4.2 31 1 0 SYSTEM: Reactor water level. CFR: 41.7 /

206000 HPCI /

2 1 Ability to monitor automatic operations of the HIGH PRESSURE COOLANT INJECTION 3.6 32 SYSTEM including: Turbine speed. CFR:

41.7 207000 Isolation (Emergency)

(System Not Applicable)

Condenser Ability to (a) predict the impacts of the following on the LOW PRESSURE CORE SPRAY SYSTEM; and (b) based on those 0

209001 LPCS predictions, use procedures to correct, 3.1 34 8

control, or mitigate the consequences of those abnormal conditions or operations:

Valve openings. CFR: 41.5 209002 HPCS (System Not Applicable) 0 Ability to manually operate and/or monitor in 211000 SLC 3.9 35 1 the control room: Tank level. CFR: 41.7 2.4.2: Knowledge of system set points, 212000 RPS R interlocks and automatic actions associated 4.5 36 with EOP entry conditions. CFR: 41.7 Knowledge of the physical connections and/or cause effect relationships between 0 INTERMEDIATE RANGE MONITOR (IRM) 215003 IRM 2.5 37 4 SYSTEM and the following: Process computer/ performance monitoring system (SPDS/ERIS/CRIDS/GDS). CFR: 41.2 to 41.9

ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO)

K K K K K K A A A A System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 Knowledge of electrical power supplies to the following: SRM channels/detectors. CFR:

41.7 2.6 38

/

0 0 215004 Source Range Monitor /

1 3 Knowledge of the operational implications of the following concepts as they apply to 2.8 39 SOURCE RANGE MONITOR (SRM)

SYSTEM: Changing detector position. CFR:

41.5 Knowledge of the effect that a loss or malfunction of the AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM will have on following:

Rod block monitor. CFR: 41.7 / 3.2 40 0 0 Ability to predict and/or monitor changes in 215005 APRM / LPRM /

7 4 parameters associated with operating the AVERAGE POWER RANGE 4.1 41 MONITOR/LOCAL POWER RANGE MONITOR SYSTEM controls including:

SCRAM and rod block trip setpoints. CFR:

41.5 Knowledge of REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) design feature(s) 0 217000 RCIC and/or interlocks which provide for the 2.9 42 3

following: Prevents pump over heating. CFR:

41.7 Knowledge of the operational implications of 0 the following concepts as they apply to 218000 ADS 3.8 43 1 AUTOMATIC DEPRESSURIZATION SYSTEM: ADS logic operation. CFR: 41.5 Knowledge of the effect that a loss or malfunction of the following will have on the 223002 PCIS/Nuclear Steam 0 PRIMARY CONTAINMENT ISOLATION 3.0 44 Supply Shutoff 5 SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF: Containment instrumentation.

CFR: 41.7 Ability to predict and/or monitor changes in 0 parameters associated with operating the 239002 SRVs 3.7 45 6 RELIEF/SAFETY VALVES controls including:

Reactor power. CFR: 41.5 Ability to (a) predict the impacts of the following on the REACTOR WATER LEVEL CONTROL SYSTEM ; and (b) based on those 259002 Reactor Water Level 0 predictions, use procedures to correct, 3.3 46 Control 2 control, or mitigate the consequences of those abnormal conditions or operations:

Loss of any number of reactor feedwater flow inputs. CFR: 41.5 Ability to monitor automatic operations of the 0

261000 SGTS STANDBY GAS TREATMENT SYSTEM 3.0 47 3

including: Valve operation. CFR: 41.7 Ability to manually operate and/or monitor in 262001 AC Electrical 0 the control room: Voltage, current, power, and 3.3 48 Distribution 5 frequency on A.C. buses. CFR: 41.7

ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (RO)

K K K K K K A A A A System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 Ability to monitor automatic operations of the 0 UNINTERRUPTABLE POWER SUPPLY 262002 UPS (AC/DC) 2.8 49 1 (A.C./D.C.) including: Transfer from preferred to alternate source. CFR: 41.7 Knowledge of the physical connections and/or cause effect relationships between D.C.

263000 DC Electrical 0 ELECTRICAL DISTRIBUTION and the 3.3 50 Distribution 1 following: A.C. electrical distribution. CFR:

41.2 to 41.9 Knowledge of the effect that a loss or malfunction of the EMERGENCY 0

264000 EDGs GENERATORS (DIESEL/JET) will have on 3.9 51 2

following: A.C. electrical distribution. CFR:

41.7 Knowledge of the effect that a loss or malfunction of the INSTRUMENT AIR 0

300000 Instrument Air SYSTEM will have on the following: Systems 3.3 52 2

having pneumatic valves and controls. CFR:

41.7 Knowledge of CCWS design feature(s) and or 400000 Component Cooling 0 interlocks which provide for the following: 3.4 53 Water 1 Automatic start of standby pump. CFR: 41.7 26/

K/A Category Point Totals: 3 2 3 3 3 2 2 2 3 2 1 Group Point Total: 26 5

ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 0 Knowledge of electrical power supplies to the 201001 CRD Hydraulic 3.6 54 2 following: Scram valve solenoids. CFR: 41.7 201002 RMCS 201003 Control Rod and Drive Mechanism 201004 RSCS (System Not Applicable) 201005 RCIS (System Not Applicable) 201006 RWM 2.2.25: Knowledge of the bases in Technical 202001 Recirculation R Specifications for limiting conditions for 3.2 55 operations and safety limits. CFR: 41.5 / 41.7 202002 Recirculation Flow Control Knowledge of REACTOR WATER CLEANUP SYSTEM design feature(s) and/or interlocks 0

204000 RWCU which provide for the following: Over 2.9 56 3

temperature protection for system components. CFR: 41.7 Knowledge of the effect that a loss or 0 malfunction of the ROD POSITION 214000 RPIS 3.1 57 3 INFORMATION SYSTEM will have on following: RMCS. CFR: 41.7 215001 Traversing In-core Probe Ability to manually operate and/or monitor in 0

215002 RBM the control room: Trip bypasses: BWR-3,4,5. 2.8 58 3

CFR: 41.7 Knowledge of the effect that a loss or 0 malfunction of the following will have on the 216000 Nuclear Boiler Inst. 2.8 59 3 NUCLEAR BOILER INSTRUMENTATION:

Temperature compensation. CFR: 41.7 219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.

226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI: Torus/Pool Spray Mode Ability to predict and/or monitor changes in parameters associated with operating the 0

233000 Fuel Pool Cooling/Cleanup FUEL POOL COOLING AND CLEAN-UP 3.1 60 3

controls including: Pool temperature. CFR:

41.5 Knowledge of the physical connections and/or 0 cause effect relationships between FUEL 234000 Fuel Handling Equipment 3.2 61 1 HANDLING EQUIPMENT and the following:

Fuel. CFR: 41.2 to 41.9 239001 Main and Reheat Steam 239003 MSIV Leakage Control (System Not Applicable) 241000 Reactor/Turbine Pressure Regulator 245000 Main Turbine Gen. / Aux.

256000 Reactor Condensate 259001 Reactor Feedwater

ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 2.4.21: Knowledge of the parameters and logic used to assess the status of safety functions, such as reactivity control, core cooling and 268000 Radwaste R 4.0 62 heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc. CFR: 41.7 Ability to monitor automatic operations of the 0

271000 Offgas OFFGAS SYSTEM including: System 2.9 63 5

indicating lights and alarms. CFR: 41.7 Knowledge of electrical power supplies to the 0

272000 Radiation Monitoring following: Reactor building ventilation 2.6 64 5

monitors: Plant-Specific. CFR: 41.7 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT Knowledge of the effect that a loss or 0 malfunction of the CONTROL ROOM HVAC 290003 Control Room HVAC 2.8 65 4 will have on following: Control room pressure.

CFR: 41.7 290002 Reactor Vessel Internals K/A Category Point Totals: 1 2 2 1 0 1 1 0 1 1 2 Group Point Total: 12 12/3

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

K K K A A E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 Ability to determine and/or interpret the following as 295001 Partial or Complete Loss of Forced 0 they apply to PARTIAL OR COMPLETE LOSS OF 3.3 76 Core Flow Circulation / 1 & 4 6 FORCED CORE FLOW CIRCULATION : Nuclear boiler instrumentation. CFR: 41.10 / 43.5 295003 Partial or Complete Loss of AC / 6 Ability to determine and/or interpret the following as 0

295004 Partial or Total Loss of DC Pwr / 6 they apply to PARTIAL OR COMPLETE LOSS OF 2.9 77 3

D.C. POWER: Battery voltage. CFR: 41.10 / 43.5 295005 Main Turbine Generator Trip / 3 295006 SCRAM / 1 295016 Control Room Abandonment / 7 2.1.20: Ability to interpret and execute procedure 295018 Partial or Total Loss of CCW / 8 S 4.6 78 steps. CFR: 41.10 / 43.5 295019 Partial or Total Loss of Inst. Air / 8 295021 Loss of Shutdown Cooling / 4 295023 Refueling Acc / 8 295024 High Drywell Pressure / 5 295025 High Reactor Pressure / 3 295026 Suppression Pool High Water Temp. / 5 295027 High Containment Temperature / 5 (Not applicable; applies to Mark III Containments) 2.2.38: Knowledge of conditions and limitations in the 295028 High Drywell Temperature / 5 S 4.5 79 facility license. CFR: 41.7 / 41.10 / 43.1 295030 Low Suppression Pool Wtr Lvl / 5 295031 Reactor Low Water Level / 2 295037 SCRAM Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 2.2.44: Ability to interpret control room indications to verify the status and operation of a system, and 295038 High Off-site Release Rate / 9 S 4.4 80 understand how operator actions and directives affect plant and system conditions. CFR: 41.5 / 43.5 2.4.35: Knowledge of local auxiliary operator tasks 600000 Plant Fire On Site / 8 S during an emergency and the resultant operational 4.0 81 effects. CFR: 41.10 / 43.5 Ability to determine and/or interpret the following as 700000 Generator Voltage and Electric Grid 0 they apply to GENERATOR VOLTAGE AND 3.6 82 Disturbances / 6 4 ELECTRIC GRID DISTURBANCES: VARs outside capability curve. CFR: 41.5 and 43.5 K/A Category Totals: 3 4 Group Point Total: 7 20/7

ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)

K K K A A E/APE # / Name / Safety Function G K/A Topic(s) IR #

1 2 3 1 2 295002 Loss of Main Condenser Vac / 3 295007 High Reactor Pressure / 3 295008 High Reactor Water Level / 2 295009 Low Reactor Water Level / 2 295010 High Drywell Pressure / 5 295011 High Containment Temp / 5 295012 High Drywell Temperature / 5 295013 High Suppression Pool Temp. / 5 2.1.23: Ability to perform specific system and 295014 Inadvertent Reactivity Addition / 1 S integrated plant procedures during all modes of 4.4 83 plant operation. CFR: 41.10 / 43.5 Ability to determine and/or interpret the following as 0

295015 Incomplete SCRAM / 1 they apply to INCOMPLETE SCRAM : Reactor 4.3 84 1

power. CFR: 41.10 / 43.5 295017 High Off-site Release Rate / 9 295020 Inadvertent Cont. Isolation / 5 & 7 295022 Loss of CRD Pumps / 1 295029 High Suppression Pool Wtr Lvl / 5 295032 High Secondary Containment Area Temperature / 5 295033 High Secondary Containment Area Radiation Levels / 9 295034 Secondary Containment Ventilation High Radiation / 9 295035 Secondary Containment High Differential Pressure / 5 2.4.49: Ability to perform without reference to 295036 Secondary Containment High procedures those actions that require immediate S 4.4 85 Sump/Area Water Level / 5 operation of system components and controls. CFR:

41.10 / 43.2 500000 High CTMT Hydrogen Conc. / 5 K/A Category Point Totals: 1 2 Group Point Total: 3 7/3

ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (SRO)

K K K K K K A A A A System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 203000 RHR/LPCI: Injection Mode Ability to (a) predict the impacts of the following on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) ; and (b) based on those predictions, 0

205000 Shutdown Cooling use procedures to correct, control, or 2.7 86 2

mitigate the consequences of those abnormal conditions or operations: Low shutdown cooling suction pressure. CFR:

41.5 206000 HPCI 207000 Isolation (Emergency)

Condenser 209001 LPCS 209002 HPCS 2.4.18: Knowledge of the specific bases for 211000 SLC S 4.0 87 EOPs. CFR: 41.10 / 43.1 Ability to (a) predict the impacts of the following on the REACTOR PROTECTION SYSTEM ; and (b) based on those 1

212000 RPS (DELL) predictions, use procedures to correct, 3.8 88 5

control, or mitigate the consequences of those abnormal conditions or operations:

Load rejection. CFR: 41.5 215003 IRM 215004 Source Range Monitor 2.2.40: Ability to apply Technical 215005 APRM / LPRM S Specifications for a system. CFR: 41.10 / 4.7 89 43.2 / 43.5 Ability to (a) predict the impacts of the following on the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) ;

0 and (b) based on those predictions, use 217000 RCIC 3.7 90 1 procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: System initiation signal. CFR: 41.5 218000 ADS 223002 PCIS/Nuclear Steam Supply Shutoff 239002 SRVs 259002 Reactor Water Level Control 261000 SGTS 262001 AC Electrical Distribution 262002 UPS (AC/DC)

ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 1 (SRO)

K K K K K K A A A A System # / Name G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 263000 DC Electrical Distribution 264000 EDGs 300000 Instrument Air 400000 Component Cooling Water K/A Category Point Totals: 3 2 Group Point Total: 5 26/5

ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic 201002 RMCS 201003 Control Rod and Drive Mechanism 201004 RSCS (System Not Applicable) 201005 RCIS (System Not Applicable) 201006 RWM 202001 Recirculation 202002 Recirculation Flow Control 204000 RWCU 214000 RPIS 215001 Traversing In-core Probe 215002 RBM 216000 Nuclear Boiler Inst.

219000 RHR/LPCI: Torus/Pool Cooling Mode 223001 Primary CTMT and Aux.

226001 RHR/LPCI: CTMT Spray Mode 230000 RHR/LPCI: Torus/Pool Spray Mode 233000 Fuel Pool Cooling/Cleanup 2.1.32: Ability to explain and apply system 234000 Fuel Handling Equipment S 4.0 91 limits and precautions. CFR: 41.10 / 43.2 239001 Main and Reheat Steam 239003 MSIV Leakage Control Ability to (a) predict the impacts of the following on the REACTOR/TURBINE PRESSURE REGULATING SYSTEM; and (b) based on those predictions, use 241000 Reactor/Turbine Pressure 1 procedures to correct, control, or mitigate 3.4 92 Regulator 6 the consequences of those abnormal conditions or operations: Low turbine inlet pressure (loss of pressure signal). CFR:

41.5 245000 Main Turbine Gen. / Aux.

256000 Reactor Condensate 259001 Reactor Feedwater 268000 Radwaste 2.2.42: Ability to recognize system parameters that are entry-level conditions 271000 Offgas S 4.6 93 for Technical Specifications. CFR: 41.7 /

41.10 / 43.2 / 43.3 272000 Radiation Monitoring 286000 Fire Protection 288000 Plant Ventilation 290001 Secondary CTMT 290003 Control Room HVAC 290002 Reactor Vessel Internals

ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 K/A Category Point Totals: 1 2 Group Point Total: 3 12/3 ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Duane Arnold Energy Center Date of Exam: 4/6/15 - 4/17/15 Category K/A # Topic RO SRO-Only IR # IR #

Ability to explain and apply system limits and precautions.

2.1.32 3.8 66 CFR: 41.10 Knowledge of conservative decision making practices. CFR:

2.1.39 3.6 67

1. 41.10 Conduct Knowledge of procedures and limitations involved in core of Operations 2.1.36 4.1 94 alterations. CFR: 41.10 / 43.6 Ability to interpret and execute procedure steps. CFR: 41.10 /

2.1.20 4.6 95 43.5 Subtotal 2 2 Knowledge of the process for managing maintenance activities during power operations, such as risk assessments, 2.2.17 2.6 68 work prioritization, and coordination with the transmission system operator. CFR: 41.10 Ability to manipulate the console controls as required to 2.2.2 operate the facility between shutdown and designated power 4.6 69 levels. CFR: 41.6 / 41.7 2.

Knowledge of limiting conditions for operations and safety Equipment 2.2.22 4.0 70 limits. CFR: 41.5 Control Ability to interpret control room indications to verify the status and operation of a system, and understand how operator 2.2.44 4.4 96 actions and directives affect plant and system conditions.

CFR: 41.5 / 43.5 Knowledge of conditions and limitations in the facility license.

2.2.38 4.5 97 CFR: 41.7 / 41.10 / 43.1 Subtotal 3 2 Knowledge of radiation exposure limits under normal or 2.3.4 3.2 71 emergency conditions. CFR: 41.12 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation 2.3.13 monitor alarms, containment entry requirements, fuel handling 3.4 72 3.

responsibilities, access to locked high-radiation areas, aligning Radiation filters, etc. CFR: 41.12 Control Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, 2.3.5 2.9 98 personnel monitoring equipment, etc. CFR: 41.11 / 41.12 /

43.4 Subtotal 2 1

4. Knowledge of procedures relating to a security event (non-Emergency 2.4.28 3.2 73 safeguards information). CFR: 41.10

Procedures /

Knowledge of the specific bases for EOPs. CFR: 41.10 Plan 2.4.18 3.3 74 2.4.19 Knowledge of EOP layout, symbols, and icons. CFR: 41.10 3.4 75 Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating 2.4.16 4.4 99 procedures, abnormal operating procedures, and severe accident management guidelines. CFR: 41.10 / 43.5 Knowledge of local auxiliary operator tasks during an 2.4.35 emergency and the resultant operational effects. CFR: 41.10 / 4.0 100 43.5 Subtotal 3 2 Tier 3 Point Total 10 7