Text

2015 Fermi Power Plant Initial License Examination Forms 401-1 and -3
	ML15286A466
Person / Time
Site:	Fermi
Issue date:	10/13/2015
From:	; NRC/RGN-III
To:	;
	Zoia, C D
Shared Package
ML15267A800	List: ML15282A377; ML15286A461; ML15286A464; ML15286A465; ML15286A466; ML15286A468; NRC-15-0064, 2015 Fermi Power Plant Initial License Examination Form 301-5; NRC-15-0064, 2015 Fermi Power Plant Initial License Examination Forms 301-1; NRC-15-0064, 2015 Fermi Power Plant Initial License Examination Forms 301-2; NRC-15-0064, 2015 Fermi Power Plant Initial License Examination Forms 401-1 and -3; NRC-15-0064, 2015 Fermi Power Plant Initial License Examination Forms D-1; NRC-15-0064, 2015 Fermi Power Plant Initial License Examination Outline Submittal;
References
	NRC-15-0064
	Download: ML15286A466 (10)
	v • d • e

ES-401 BWR Examination Outline FORM ES-401-1 Facility Name: Fermi 2 Date of Exam: 8/24/2015 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 3 3 4 3 4 3 20 5 2 7 Emergency &

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

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

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

Note: 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.

Note: 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 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.

Note: 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.

Note: 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.

Note: 6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

Note: 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.

Note: 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.

Note: 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, Page 16 of 33

ES-401 2 Form ES-401-1 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 295001 Partial or Complete Loss of Forced 0 Knowledge of the reasons for the following responses as they apply to Partial or 3.7 1 Core Flow Circulation / 1 & 4 2 Complete Loss of Forced Core Flow Circulation: Reactor power response 0 Ability to operate and/or monitor the following as they apply to Partial or Complete 295003 Partial or Complete Loss of AC / 6 4.2 1 2 Loss of AC: Emergency generators 0 Ability to determine and/or interpret the following as they apply to Partial or Total Loss 295004 Partial or Total Loss of DC Pwr / 6 2.8 1 3 of DC Pwr: Battery voltage 02.

295005 Main Turbine Generator Trip / 3 Knowledge of conditions and limitations in the facility license. 3.6 1 38 0 Knowledge of the operational implications of the following concepts as they apply to 295006 SCRAM / 1 3.7 1 1 SCRAM: Decay heat generation and removal.

0 Knowledge of the interrelations between Control Room Abandonment and the 295016 Control Room Abandonment / 7 4.0 1 2 following: Local control stations: Plant-Specific 0 Knowledge of the reasons for the following responses as they apply to Partial or Total 295018 Partial or Total Loss of CCW / 8 3.3 1 6 Loss of CCW: Increasing cooling water flow to heat exchangers 0 Ability to operate and/or monitor the following as they apply to Partial or Total Loss of 295019 Partial or Total Loss of Inst. Air / 8 3.3 1 4 Inst. Air: Service air isolations valves: Plant-Specific 0 Ability to determine and/or interpret the following as they apply to Loss of Shutdown 295021 Loss of Shutdown Cooling / 4 3.5 1 3 Cooling: Reactor water level

02. Knowledge of less than or equal to one hour Technical Specification action statements 295023 Refueling Acc / 8 3.9 1 39 for systems.

0 Knowledge of the operational implications of the following concepts as they apply to 295024 High Drywell Pressure / 5 4.1 1 1 High Drywell Pressure: Drywell integrity: Plant-Specific Knowledge of the interrelations between High Reactor Pressure and the following:

295025 High Reactor Pressure / 3 0 9 Reactor power 3.9 1 295026 Suppression Pool High Water Knowledge of the reasons for the following responses as they apply to Suppression 0 1 3.8 1 Temp. / 5 Pool High Water Temp.: Emergency/normal depressurization 295027 High Containment Temperature / 5 0 Ability to determine and/or interpret the following as they apply to High Drywell 295028 High Drywell Temperature / 5 0 2 Temperature: Reactor pressure 3.8 1 04.

295030 Low Suppression Pool Wtr Lvl / 5 Knowledge of the specific bases for EOPs. 3.3 1 18 Knowledge of the operational implications of the following concepts as they apply to 295031 Reactor Low Water Level / 2 0 1 Reactor Low Water Level: Adequate core cooling.

4.6 1 295037 SCRAM Condition Present and 0 Knowledge of the interrelations between SCRAM Condition Present and Reactor Reactor Power Above APRM Downscale or 4.0 1 5 Power Above APRM Downscale or Unknown and the following: CRD hydraulic system Unknown / 1 Knowledge of the reasons for the following responses as they apply to High Off-site 295038 High Off-site Release Rate / 9 0 2 Release Rate: System isolations 3.9 1 Ability to operate and/or monitor the following as they apply to Plant Fire On Site: Plant 600000 Plant Fire On Site / 8 0 5 and control room ventilation systems 3.0 1 700000 Generator Voltage and Electric Grid 0 Ability to determine and/or interpret the following as they apply to Generator Voltage 3.9 1 Disturbances / 6 9 and Electric Grid Disturbances: Operational status of emergency diesel generators K/A Category Totals: 3 3 4 3 4 3 Group Point Total: 20 ES-401, Page 17 of 33

ES-401 3 Form ES-401-1 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 0 Ability to determine and/or interpret the following as they apply to Loss of Main 295002 Loss of Main Condenser Vac / 3 2.9 1 1 Condenser Vac: Condenser vacuum/absolute pressure 02.

295007 High Reactor Pressure / 3 Knowledge of limiting conditions for operations and safety limits. 4.0 1 22 295008 High Reactor Water Level / 2 0 295009 Low Reactor Water Level / 2 0 0 Knowledge of the reasons for the following responses as they apply to High Drywell 295010 High Drywell Pressure / 5 3.4 1 2 Pressure: Increased drywell cooling 295011 High Containment Temp / 5 0 295012 High Drywell Temperature / 5 0 295013 High Suppression Pool Temp. / 5 0 0 Ability to operate and/or monitor the following as they apply to Inadvertent Reactivity 295014 Inadvertent Reactivity Addition / 1 3.5 1 3 Addition: RMCS: Plant-Specific 0

295015 Incomplete SCRAM / 1 Knowledge of the interrelations between Incomplete SCRAM and the following: RPS 4.0 1 4

295017 High Off-site Release Rate / 9 0 295020 Inadvertent Cont. Isolation / 5 & 7 0 295022 Loss of CRD Pumps / 1 0 295029 High Suppression Pool Wtr Lvl / 5 0 295032 High Secondary Containment Area 0

Temperature / 5 295033 High Secondary Containment Area 0 Knowledge of the operational implications of the following concepts as they apply to 3.9 1 Radiation Levels / 9 2 High Secondary Containment Area Radiation Levels: Personnel protection 295034 Secondary Containment Ventilation 0

High Radiation / 9 295035 Secondary Containment High 0

Differential Pressure / 5 295036 Secondary Containment High 0

Sump/Area Water Level / 5 0 Knowledge of the operational implications of the following concepts as they apply to 500000 High CTMT Hydrogen Conc. / 5 3.3 1 1 High CTMT Hydrogen Conc.: Containment integrity K/A Category Totals: 2 1 1 1 1 1 Group Point Total: 7 ES-401, Page 18 of 33

ES-401 4 Form ES-401-1 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 0 Knowledge of RHR/LPCI: Injection Mode design feature(s) and/or interlocks 203000 RHR/LPCI: Injection Mode 3.7 1 7 which provide for the following: Emergency generator load sequencing 0 Knowledge of the operational implications of the following concepts as they apply 205000 Shutdown Cooling 2.8 1 3 to Shutdown Cooling: Heat removal mechanisms 0 Knowledge of the effect that a loss or malfunction of the following will have on the 206000 HPCI 3.5 1 9 HPCI: Condensate storage and transfer system: BWR-2, 3, 4 207000 Isolation (Emergency) 0 Condenser 0 Ability to predict and/or monitor changes in parameters associated with operating 209001 LPCS 3.3 1 8 the LPCS controls including: System lineup 209002 HPCS 0 Ability to (a) predict the impacts of the following on the SLC; and (b) based on 0

211000 SLC those predictions, use procedures to correct, control, or mitigate the 3.1 1 6 consequences of those abnormal conditions or operations: Valve openings 0 Ability to monitor automatic operations of the RPS including: SCRAM instrument 212000 RPS 3.9 1 5 volume level Knowledge of the physical connections and/or cause-effect relationships 0 0 3.6; 215003 IRM between IRM and the following: Reactor manual control; Ability to manually 2 2 3 operate and/or monitor in the control room: IRM range switches 3.6 0 01. Knowledge of electrical power supplies to the following: SRM channels/detectors; 2.6; 215004 Source Range Monitor 2 1 32 Ability to explain and apply system limits and precautions. 3.8 Knowledge of the physical connections and/or cause-effect relationships 1 0 between APRM / LPRM and the following: Reactor manual control system: Plant- 3.3; 215005 APRM / LPRM 2 0 7 Specific; Knowledge of the effect that a loss or malfunction of the APRM / LPRM 3.2 will have on following: Rod block monitor: Plant-Specific 0 Knowledge of RCIC design feature(s) and/or interlocks which provide for the 217000 RCIC 3.0 1 4 following: Prevents turbine damage: Plant-Specific Knowledge of electrical power supplies to the following: ADS logic; Knowledge of 0 0 3.1; 218000 ADS the operational implications of the following concepts as they apply to ADS: ADS 2 1 1 logic operation 3.8 223002 PCIS/Nuclear Steam Supply 0 Knowledge of the effect that a loss or malfunction of the following will have on the 3.3 1 Shutoff 4 PCIS/Nuclear Steam Supply Shutoff: Nuclear boiler instrumentation Knowledge of SRVs design feature(s) and/or interlocks which provide for the following: Prevents siphoning of water into SRV discharge piping and limits loads 0 0 3.1; 239002 SRVs on subsequent actuation of SRV's; Ability to predict and/or monitor changes in 2 3 5 parameters associated with operating the SRVs controls including: Reactor 3.7 water level Ability to (a) predict the impacts of the following on the Reactor Water Level 0 Control; and (b) based on those predictions, use procedures to correct, control, 259002 Reactor Water Level Control 3.3 1 6 or mitigate the consequences of those abnormal conditions or operations: Loss of controller signal output 0

261000 SGTS Ability to monitor automatic operations of the SGTS including: Valve operation 3.0 1 3

0 Ability to manually operate and/or monitor in the control room: Voltage, current, 262001 AC Electrical Distribution 3.3 1 5 power, and frequency on A.C. buses Ability to interpret control room indications to verify the status and operation of a 02.

262002 UPS (AC/DC) system, and understand how operator actions and directives affect plant and 4.2 1 44 system conditions.

0 Knowledge of the physical connections and/or cause-effect relationships 263000 DC Electrical Distribution 2.6 1 4 between DC Electrical Distribution and the following: Ground detection 0 Knowledge of the effect that a loss or malfunction of the EDGs will have on 264000 EDGs 4.2 1 1 following: Emergency core cooling systems 0 Knowledge of electrical power supplies to the following: Instrument air 300000 Instrument Air 2.8 1 1 compressor 0 Knowledge of the effect that a loss or malfunction of the Component Cooling 400000 Component Cooling Water 2.9 1 1 Water will have on following: Loads cooled by CCWS K/A Category Totals: 3 3 3 3 2 2 2 2 2 2 2 Group Point Total: 26 ES-401, Page 19 of 33

ES-401-1 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (RO)

. . K K K K A A A A System # / Name 1 2 3 4 5 6 1 2 3 4 G K/A Topic(s) IR #

201001 CRD Hydraulic 0 0 Ability to predict and/or monitor changes in parameters associated with 201002 RMCS

1 operating the RMCS controls including: CRD drive water flow 2.8 1 0 Knowledge of the effect that a loss or malfunction of the Control Rod and Drive 201003 Control Rod and Drive Mechanism 1 Mechanism will have on following: Reactor power 3.2 1 201004 RSCS 0 201005 RCIS 0 0 Knowledge of RWM design feature(s) and/or interlocks which provide for the 201006 RWM 3 following: Select blocks/errors: P-Spec(Not-BWR6) 3.3 1 0 Knowledge of electrical power supplies to the following: Recirculation system 202001 Recirculation 3 valves 2.7 1 202002 Recirculation Flow Control 0 0 Ability to monitor automatic operations of the RWCU including: Response to 204000 RWCU 3 system isolations 3.6 1 214000 RPIS 0 215001 Traversing In-core Probe 0 215002 RBM 0 1 Knowledge of the operational implications of the following concepts as they 216000 Nuclear Boiler Inst. 4 apply to Nuclear Boiler Inst.: Density 2.6 1 219000 RHR/LPCI: Torus/Pool Cooling 0

Mode 223001 Primary CTMT and Aux. 0 226001 RHR/LPCI: CTMT Spray Mode 0 Knowledge of the physical connections and/or cause-effect relationships 0

230000 RHR/LPCI: Torus/Pool Spray Mode 1 between RHR/LPCI: Torus/Pool Spray Mode and the following: Suppression 3.6 1 pool 233000 Fuel Pool Cooling/Cleanup 0 234000 Fuel Handling Equipment 0 239001 Main and Reheat Steam 0 239003 MSIV Leakage Control 0 1 Knowledge of the effect that a loss or malfunction of the following will have on 241000 Reactor/Turbine Pressure Regulator 2 the Reactor/Turbine Pressure Regulator: Control/governor valves 3.3 1 245000 Main Turbine Gen. / Aux. 0 256000 Reactor Condensate 0 259001 Reactor Feedwater 0 0 Ability to manually operate and/or monitor in the control room: Sump 268000 Radwaste

1 integrators 3.4 1 0 Ability to monitor automatic operations of the Offgas including: System 271000 Offgas 3 temperatures 2.8 1 272000 Radiation Monitoring 0 286000 Fire Protection 0 01.

288000 Plant Ventilation Knowledge of system purpose and/or function. 3.9 1 27 Ability to (a) predict the impacts of the following on the Secondary CTMT; and 0 (b) based on those predictions, use procedures to correct, control, or mitigate 290001 Secondary CTMT 4 the consequences of those abnormal conditions or operations: High airborne 3.4 1 radiation 290003 Control Room HVAC 0 290002 Reactor Vessel Internals 0 K/A Category Totals: 1 1 1 1 1 1 1 1 2 1 1 Group Point Total: 12 ES-401, Page 20 of 33

ES-401 2 Form ES-401-1 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 295001 Partial or Complete Loss of Forced 0

Core Flow Circulation / 1 & 4 0 Ability to determine and/or interpret the following as they apply to Partial 295003 Partial or Complete Loss of AC / 6 3.7 1 1 or Complete Loss of AC: Cause of partial or complete loss of A.C. power 02.

295004 Partial or Total Loss of DC Pwr / 6 Ability to apply Technical Specifications for a system. 4.7 1 40 295005 Main Turbine Generator Trip / 3 0 295006 SCRAM / 1 0 0 Ability to determine and/or interpret the following as they apply to Control 295016 Control Room Abandonment / 7 3.5 1 6 Room Abandonment: Cooldown rate

04. Ability to prioritize and interpret the significance of each annunciator or 295018 Partial or Total Loss of CCW / 8 4.3 1 45 alarm.

295019 Partial or Total Loss of Inst. Air / 8 0 295021 Loss of Shutdown Cooling / 4 0 0 Ability to determine and/or interpret the following as they apply to 295023 Refueling Acc / 8 4.0 1 1 Refueling Accidents: Area radiation levels 0 Ability to determine and/or interpret the following as they apply to High 295024 High Drywell Pressure / 5 4.4 1 1 Drywell Pressure: Drywell pressure 295025 High Reactor Pressure / 3 0 295026 Suppression Pool High Water Temp.

0

/5 295027 High Containment Temperature / 5 0 295028 High Drywell Temperature / 5 0 295030 Low Suppression Pool Wtr Lvl / 5 0 295031 Reactor Low Water Level / 2 0 295037 SCRAM Condition Present Ability to determine and/or interpret the following as they apply to SCRAM 0

and Reactor Power Above APRM Condition Present and Reactor Power Above APRM Downscale or 4.4 1 3

Downscale or Unknown / 1 Unknown: SBLC tank level 295038 High Off-site Release Rate / 9 0 600000 Plant Fire On Site / 8 0 700000 Generator Voltage and Electric Grid 0

Disturbances / 6 K/A Category Totals: 0 0 0 0 5 2 Group Point Total: 7 ES-401, Page 17 of 33

ES-401 3 Form ES-401-1 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 0 295007 High Reactor Pressure / 3 0 295008 High Reactor Water Level / 2 0 295009 Low Reactor Water Level / 2 0 295010 High Drywell Pressure / 5 0 295011 High Containment Temp / 5 0 295012 High Drywell Temperature / 5 0 01.

295013 High Suppression Pool Temp. / 5 Ability to interpret reference materials, such as graphs, curves, tables, etc. 4.2 1 25 295014 Inadvertent Reactivity Addition / 1 0 295015 Incomplete SCRAM / 1 0 295017 High Off-site Release Rate / 9 0 0 Ability to determine and/or interpret the following as they apply to Inadvertent Cont.

295020 Inadvertent Cont. Isolation / 5 & 7 Isolation: Cause of isolation 3.8 1 6

295022 Loss of CRD Pumps / 1 0 295029 High Suppression Pool Wtr Lvl / 5 0 295032 High Secondary Containment Area 0

Temperature / 5 295033 High Secondary Containment Area 0

Radiation Levels / 9 295034 Secondary Containment Ventilation 04. Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures. 4.7 1 High Radiation / 9 04 295035 Secondary Containment High 0

Differential Pressure / 5 295036 Secondary Containment High 0

Sump/Area Water Level / 5 500000 High CTMT Hydrogen Conc. / 5 0 K/A Category Totals: 0 0 0 0 1 2 Group Point Total: 3 ES-401, Page 18 of 33

ES-401 4 Form ES-401-1 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 Ability to (a) predict the impacts of the following on the RHR/LPCI: Injection 0 Mode; and (b) based on those predictions, use procedures to correct, control, 203000 RHR/LPCI: Injection 3.0 1 8 or mitigate the consequences of those abnormal conditions or operations:

Inadequate room cooling 205000 Shutdown Cooling Mode 0

04. Ability to perform without reference to procedures those actions that require 206000 HPCI immediate operation of system components and controls. 4.4 1 49 207000 Isolation (Emergency) 0 Condenser

04. Knowledge of the operational implications of EOP warnings, cautions, and 209001 LPCS notes. 4.3 1 20 209002 HPCS 0 211000 SLC 0 212000 RPS 0 215003 IRM 0 215004 Source Range Monitor 0 215005 APRM / LPRM 0 217000 RCIC 0 218000 ADS 0 223002 PCIS/Nuclear Steam Supply 0

Shutoff 239002 SRVs 0 259002 Reactor Water Level Control 0 Ability to (a) predict the impacts of the following on the SGTS; and (b) based 0

261000 SGTS on those predictions, use procedures to correct, control, or mitigate the 3.1 1 2 consequences of those abnormal conditions or operations: High system flow 262001 AC Electrical Distribution 0 262002 UPS (AC/DC) 0 263000 DC Electrical Distribution 0 264000 EDGs 0 Ability to (a) predict the impacts of the following on the Instrument Air; and (b) 0 based on those predictions, use procedures to correct, control, or mitigate the 300000 Instrument Air 2.8 1 1 consequences of those abnormal conditions or operations: Air dryer and filter malfunctions 400000 Component Cooling Water 0 K/A Category Totals: 0 0 0 0 0 0 0 3 0 0 2 Group Point Total: 5 ES-401, Page 19 of 33

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant Systems - Tier 2/Group 2 (SRO)

K K K K K K A A A A System # / Name 4 G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 Ability to (a) predict the impacts of the following on the CRD Hydraulic System; 0 and (b) based on those predictions, use procedures to correct, control, or 201001 CRD Hydraulic 9 mitigate the consequences of those abnormal conditions or operations: Loss of 3.1 1 applicable plant air systems 201002 RMCS 0 201003 Control Rod and Drive Mechanism 0 201004 RSCS 0 201005 RCIS 0 201006 RWM 0 202001 Recirculation 0 202002 Recirculation Flow Control 0 204000 RWCU 0 214000 RPIS 0 215001 Traversing In-core Probe 0 215002 RBM 0 216000 Nuclear Boiler Inst. 0 219000 RHR/LPCI: Torus/Pool Cooling 04.

Knowledge of the emergency action level thresholds and classifications. 4.6 1 Mode 41 223001 Primary CTMT and Aux. 0 226001 RHR/LPCI: CTMT Spray Mode 0 230000 RHR/LPCI: Torus/Pool Spray Mode 0 233000 Fuel Pool Cooling/Cleanup 0 234000 Fuel Handling Equipment 0 239001 Main and Reheat Steam 0 239003 MSIV Leakage Control 0 241000 Reactor/Turbine Pressure Regulator 0 245000 Main Turbine Gen. / Aux. 0 256000 Reactor Condensate 0 259001 Reactor Feedwater 0 268000 Radwaste 0 271000 Offgas 0 272000 Radiation Monitoring 0 286000 Fire Protection 0 288000 Plant Ventilation 0 290001 Secondary CTMT 0 Ability to (a) predict the impacts of the following on the Control Room HVAC; 0 and (b) based on those predictions, use procedures to correct, control, or 290003 Control Room HVAC 1 mitigate the consequences of those abnormal conditions or operations: 3.2 1 Initiation/reconfiguration 290002 Reactor Vessel Internals 0 K/A Category Totals: 0 0 0 0 0 0 0 2 0 0 1 Group Point Total: 3 ES-401, Page 20 of 33

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility Name:Fermi 2 Date of Exam:8/24/2015 RO SRO-Only Category K/A # Topic IR # IR #

2.1. 41 Knowledge of the refueling process. 3.7 1 Knowledge of individual licensed operator responsibilities related to shift staffing, such as 2.1. 04 medical requirements, no-solo operation, maintenance of active license status, 3.3 1 10CFR55, etc.

2.1. 34 Knowledge of primary and secondary plant chemistry limits. 2.7 1

1. Ability to evaluate plant performance and make operational judgments based on Conduct of 2.1. 07 operating characteristics, reactor behavior, and instrument interpretation. 4.4 1 Operations 2.1. 42 Knowledge of new and spent fuel movement procedures. 3.4 1 2.1.

Subtotal 3 2 2.2. 23 Ability to track Technical Specification limiting conditions for operations. 4.6 1 Knowledge of the bases in Technical Specifications for limiting conditions for operations 2.2. 25 and safety limits. 4.2 1 Ability to analyze the effect of maintenance activities, such as degraded power sources,

2. 2.2. 36 on the status of limiting conditions for operations. 3.1 1 Equipment 2.2. 14 Knowledge of the process for controlling equipment configuration or status. 3.9 1 Control 2.2.

2.2.

Subtotal 2 2 2.3. 04 Knowledge of radiation exposure limits under normal or emergency conditions. 3.2 1 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, 2.3. 15 portable survey instruments, personnel monitoring equipment, etc. 2.9 1 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms,

3. 2.3. 05 portable survey instruments, personnel monitoring equipment, etc. 2.9 1 Radiation 2.3.

Control 2.3.

2.3.

Subtotal 2 1 2.4. 11 Knowledge of abnormal condition procedures. 4.2 1 2.4. 01 Knowledge of EOP entry conditions and immediate action steps. 4.6 1

4. 2.4. 43 Knowledge of emergency communications systems and techniques. 3.2 1 Emergency Procedures 2.4. 46 Ability to verify that the alarms are consistent with the plant conditions. 4.2 1

/ Plan 2.4. 27 Knowledge of fire in the plant procedures. 3.9 1 2.4.

Subtotal 3 2 Tier 3 Point Total 10 7 ES-401, Page 26 of 33