ML18120A179
| ML18120A179 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/26/2018 |
| From: | Chuck Zoia Operations Branch III |
| To: | NRC/RGN-III/DRS/OLB |
| Zoia C | |
| Shared Package | |
| ML17164A402 | List: |
| References | |
| Download: ML18120A179 (16) | |
Text
ES-401 1 Form ES-401-1 Facility: FERMI Date of Exam: Week of 2/26/2018 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 3 4 4 3 3 20 4 3 7 Emergency and N/A N/A 2 1 2 1 1 1 1 7 2 1 3 Abnormal Plant Evolutions Tier Totals 4 5 5 5 4 4 27 6 4 10 1 3 2 2 2 2 3 2 2 3 2 3 26 2 3 5 2.
Plant 2 1 1 1 2 1 1 1 1 1 1 1 12 2 1 3 Systems Tier Totals 4 3 3 4 3 4 3 3 4 3 4 38 4 4 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 #
295001 (APE 1) Partial or Complete Loss of 01 Knowledge of the operational implications of the 3.5 Forced Core Flow Circulation / 1 & 4 following concepts as they apply to PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION: Natural Circulation.
295003 (APE 3) Partial or Complete Loss of 02 Knowledge of the interrelations between PARTIAL 4.1 AC Power / 6 OR COMPLETE LOSS OF A.C. POWER and the following: Emergency Generators.
295004 (APE 4) Partial or Total Loss of DC 02 Knowledge of the reasons for the following 2.9 Power / 6 responses as they apply to PARTIAL OR COMPLETE LOSS OF D.C. POWER: Ground isolation/fault determination.
295005 (APE 5) Main Turbine Generator Trip 05 Ability to operate and/or monitor the following as 3.6
/3 they apply to MAIN TURBINE GENERATOR TRIP:
Reactor/turbine pressure regulating system.
295006 (APE 6) Scram / 1 06 Ability to determine and/or interpret the following 3.5 as they apply to SCRAM: Cause of reactor SCRAM.
295016 (APE 16) Control Room 1. Ability to perform specific system and integrated 4.3 Abandonment / 7 23 plant procedures during all modes of plant operation.
295018 (APE 18) Partial or Complete Loss of 03 Ability to determine and/or interpret the following 3.2 CCW / 8 as they apply to PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Cause for partial or complete loss.
295019 (APE 19) Partial or Complete Loss of 02 Knowledge of the reasons for the following 3.5 Instrument Air / 8 responses as they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR:
Standby air compressor operation.
295021 (APE 21) Loss of Shutdown Cooling / 02 Ability to operate and/or monitor the following as 3.5 4 they apply to LOSS OF SHUTDOWN COOLING:
RHR/shutdown cooling.
295023 (APE 23) Refueling Accidents / 8 05 Knowledge of the interrelations between 3.5 REFUELING ACCIDENTS and the following:
Secondary containment ventilation.
295024 High Drywell Pressure / 5 09 Knowledge of the interrelations between HIGH 2.9 DRYWELL PRESSURE and the following:
Suppression pool makeup.
295025 (EPE 2) High Reactor Pressure / 3 05 Knowledge of the operational implications of the 4.4 following concepts as they apply to HIGH REACTOR PRESSURE: Exceeding safety limits 295026 (EPE 3) Suppression Pool High 03 Knowledge of the reasons for the following 3.5 Water Temperature / 5 responses as they apply to SUPPRESSION POOL HIGH WATER TEMPERATURE: Suppression pool spray.
295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 295028 (EPE 5) High Drywell Temperature 02 Ability to operate and/or monitor the following as 3.9 (Mark I and Mark II only) / 5 they apply to HIGH DRYWELL TEMPERATURE:
Drywell ventilation system.
ES-401 3 Form ES-401-1 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) IR #
295030 (EPE 7) Low Suppression Pool Water 03 Ability to determine and/or interpret the following 3.7 Level / 5 as they apply to LOW SUPPRESSION POOL WATER LEVEL: Reactor pressure.
295031 (EPE 8) Reactor Low Water Level / 2 2. Ability to recognize system parameters that are 3.9 42 entry-level conditions for Technical Specifications.
295037 (EPE 14) Scram Condition Present 08 Ability to operate and/or monitor the following as 3.6 and Reactor Power Above APRM Downscale they apply to SCRAM CONDITION PRESENT or Unknown / 1 AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: Rod control and information system 295038 (EPE 15) High Offsite Radioactivity 4. Knowledge of specific bases for EOPs. 3.3 Release Rate / 9 18 600000 (APE 24) Plant Fire On Site / 8 04 Knowledge of the reasons for the following 2.8 responses as they apply to PLANT FIRE ON SITE:
Actions contained in the abnormal procedure for plant fire on site.
700000 (APE 25) Generator Voltage and 03 Knowledge of the operational implications of the 3.3 Electric Grid Disturbances / 6 following concepts as they apply to GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Under-excitation.
K/A Category Totals: 3 3 4 4 3 3 Group Point Total: 20
ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #
295002 (APE 2) Loss of Main Condenser 4. Ability to recognize abnormal indications for 4.5 Vacuum / 3 04 system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.
295007 (APE 7) High Reactor Pressure / 3 02 Knowledge of the operational implications of the 3.1 following concepts as they apply to HIGH REACTOR PRESSURE: Decay heat generation.
295008 (APE 8) High Reactor Water Level / 2 03 Knowledge of the interrelations between HIGH 3.6 REACTOR WATER LEVEL and the following:
Reactor water level control.
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 295014 (APE 14) Inadvertent Reactivity Addition / 1 295015 (APE 15) Incomplete Scram / 1 295017 (APE 17) Abnormal Offsite Release Rate / 9 295020 (APE 20) Inadvertent Containment Isolation / 5 & 7 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 01 Knowledge of the interrelations between 3.9 Ventilation High Radiation / 9 SECONDARY CONTAINMENT VENTILATION HIGH RADIATION and the following: Process radiation monitoring system.
295035 (EPE 12) Secondary Containment 02 Knowledge of the reasons for the following 3.3 High Differential Pressure / 5 responses as they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: Secondary containment ventilation response.
295036 (EPE 13) Secondary Containment 02 Ability to operate and/or monitor the following as 3.5 High Sump/Area Water Level / 5 they apply to SECONDARY CONTAINMENT HIGH SUMP/AREA WATER LEVEL: Affected systems so as to isolate damaged portions.
ES-401 5 Form ES-401-1 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G IR #
500000 (EPE 16) High Containment Hydrogen 04 Ability to determine and / or interpret the following 3.3 Concentration / 5 as they apply to HIGH PRIMARY CONTAINMENT HYDROGEN CONCENTRATIONS: Combustible limits for wetwell.
K/A Category Point Totals: 1 2 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, RHR/LPCI) RHR/LPCI: 07 Ability to monitor automatic operations of the 4.2 Injection Mode RHR/LPCI: INJECTION MODE (PLANT SPECIFIC) including: Loop selection.
205000 (SF4 SCS) Shutdown Cooling 12 Ability to manually operate and/or monitor in the 3.4 control room: Recirculation loop temperatures.
206000 (SF2, SF4 HPCIS) 1. Ability to interpret and execute procedure steps. 4.6 High-Pressure Coolant Injection 20 207000 (SF4 IC) Isolation (Emergency) Condenser 209001 (SF2, SF4 LPCS) 10 Knowledge of the physical connections and/or 3.7 Low-Pressure Core Spray cause effect relationships between LOW PRESSURE CORE SPRAY SYSTEM and the following: Emergency Generator.
209002 (SF2, SF4 HPCS)
High-Pressure Core Spray 211000 (SF1 SLCS) Standby Liquid 02 Knowledge of electrical power supplies to the 3.1 Control following: Explosive valves.
212000 (SF7 RPS) Reactor Protection 02 Knowledge of the effect that a loss or 3.7 malfunction of the REACTOR PROTECTION SYSTEM will have on following: Primary containment isolation system/nuclear steam supply shut-off.
215003 (SF7 IRM) 01 Knowledge of INTERMEDIATE RANGE 3.7 Intermediate-Range Monitor MONITOR (IRM) SYSTEM design feature(s) and/or interlocks which provide for the following:
Rod withdrawal blocks.
215004 (SF7 SRMS) Source-Range 01 Knowledge of the operational implications of the 2.6 Monitor following concepts as they apply to SOURCE RANGE MONITOR (SRM) SYSTEM: Detector Operation.
215005 (SF7 PRMS) Average Power 04 Knowledge of the effect that a loss or 3.1 Range Monitor/Local Power Range malfunction of the following will have on the Monitor AVERAGE POWER RANGE MONITOR/LOCAL POWER RANGE MONITOR SYSTEM: Trip units.
217000 (SF2, SF4 RCIC) Reactor 05 Ability to predict and/or monitor changes in 3.7 Core Isolation Cooling parameters associated with operating the REACTOR CORE ISOLATION COOLING SYSTEM (RCIC) controls including: RCIC Turbine Speed.
218000 (SF3 ADS) Automatic 06 Ability to (a) predict the impacts of the following 4.2 Depressurization on the AUTOMATIC DEPRESSURIZATION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: ADS initiation signals present 223002 (SF5 PCIS) Primary 01 Ability to monitor automatic operations of the 3.4 Containment Isolation/Nuclear Steam PRIMARY CONTAINMENT ISOLATION Supply Shutoff SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF including: System Indicating lights and alarms.
ES-401 7 Form ES-401-1 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) IR #
259002 (SF2 RWLCS) Reactor Water 08 Knowledge of the physical connections and/or 3.2 Level Control cause effect relationships between REACTOR WATER LEVEL CONTROL SYSTEM and the following: Recirculation system.
261000 (SF9 SGTS) Standby Gas 2. Knowledge of surveillance procedures. 3.7 Treatment 12 262001 (SF6 AC) AC Electrical 03 Knowledge of the effect that a loss or 2.9 Distribution malfunction of the A.C. ELECTRICAL DISTRIBUTION will have on following: D.C.
electrical distribution.
262002 (SF6 UPS) Uninterruptable 01 Knowledge of UNINTERRUPTABLE POWER 3.1 Power Supply (AC/DC) SUPPLY (A.C./D.C.) design feature(s) and/or interlocks which provide for the following:
Transfer from preferred power to alternate power supplies.
263000 (SF6 DC) DC Electrical 01 Knowledge of electrical power supplies to the 3.1 Distribution following: Major DC Loads.
264000 (SF6 EGE) Emergency 06 Knowledge of the operational implications of the 3.4 Generators (Diesel/Jet) EDG following concepts as they apply to EMERGENCY GENERATORS (DIESEL/JET):
Load Sequencing.
300000 (SF8 IA) Instrument Air 13 Knowledge of the effect that a loss or 2.8 malfunction of the following will have on the INSTRUMENT AIR SYSTEM: Filters.
400000 (SF8 CCS) Component 03 Ability to predict and / or monitor changes in 2.7 Cooling Water parameters associated with operating the CCWS controls including: CCW Pressure.
203000 (SF2, RHR/LPCI) RHR/LPCI: 13 Ability to (a) predict the impacts of the following 3.2 Injection Mode on the RHR/LPCI: INJECTION MODE; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Valve openings.
205000 (SF4 SCS) Shutdown Cooling 02 Ability to monitor automatic operations of the 3.2 SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) including:
Pump trips.
206000 (SF2, SF4 HPCIS) 12 Ability to manually operate and/or monitor in the 4.0 High-Pressure Coolant Injection control room: Turbine trip controls.
209001 (SF2, SF4 LPCS) 4. Ability to identify post-accident instrumentation. 3.7 Low-Pressure Core Spray 3 211000 (SF1 SLCS) Standby Liquid 02 Knowledge of the physical connections and/or 2.7 Control cause effect relationships between STANDBY LIQUID CONTROL SYSTEM and the following:
Core plate differential pressure indication.
212000 (SF7 RPS) Reactor Protection 03 Knowledge of the effect that a loss or 3.5 malfunction of the following well have on the REACTOR PROTECTION SYSTEM: Nuclear Boiler Instrumentation.
K/A Category Point Totals: 3 2 2 2 2 3 2 2 3 2 3 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 07 Knowledge of CONTROL ROD DRIVE 2.8 HYDRAULIC SYSTEM design feature(s) and/or interlocks which provide for the following: Testing SCRAM discharge volume isolation valves.
201002 (SF1 RMCS) Reactor Manual Control 201003 (SF1 CRDM) Control Rod and Drive Mechanism 05 Ability to (a) predict the impacts of the 4.1 following on the CONTROL ROD AND DRIVE MECHANISM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Reactor Scram.
201004 (SF7 RSCS) Rod Sequence Control 201005 (SF1, SF7 RCIS) Rod Control and Information 201006 (SF7 RWMS) Rod Worth Minimizer 08 Knowledge of the operational 2.9 implications of the following concepts as they apply to ROD WORTH MINIMIZER SYSTEM (RWM):
Operating sequence.
202001 (SF1, SF4 RS) Recirculation 202002 (SF1 RSCTL) Recirculation Flow Control 204000 (SF2 RWCU) Reactor Water Cleanup 04 Ability to monitor automatic operations 3.4 of the REACTOR WATER CLEANUP SYSTEM including: Response to interlocks and trips designed to protect system components.
214000 (SF7 RPIS) Rod Position Information 215001 (SF7 TIP) Traversing In-Core Probe 04 Knowledge of the effect that a loss or 3.1 malfunction of the following will have on the TRAVERSING IN-CORE PROBE:
Primary containment isolation system.
215002 (SF7 RBMS) Rod Block Monitor 216000 (SF7 NBI) Nuclear Boiler Instrumentation 02 Ability to manually operate and/or 3.3 monitor in the control room: Channel select controls.
219000 (SF5 RHR SPC) RHR/LPCI:
Torus/Suppression Pool Cooling Mode 223001 (SF5 PCS) Primary Containment and Auxiliaries 226001 (SF5 RHR CSS) RHR/LPCI: Containment Spray Mode 07 Ability to predict and/or monitor 3.1 changes in parameters associated with operating the RHR/LPCI:
CONTAINMENT SPRAY SYSTEM MODE controls including: System pressure.
230000 (SF5 RHR SPS) RHR/LPCI:
Torus/Suppression Pool Spray Mode 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup 234000 (SF8 FH) Fuel-Handling Equipment
- 1. Knowledge of system purpose and/or 3.9 27 function.
ES-401 9 Form ES-401-1 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) IR #
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 09 Knowledge of the physical connections 2.7 and/or cause effect relationships between MAIN TURBINE GENERATOR AND AUXILIARY SYSTEMS and the following: D. C.
electrical distribution.
256000 (SF2 CDS) Condensate 259001 (SF2 FWS) Feedwater 01 Knowledge of electrical power supplies 3.3 to the following: Reactor feedwater pump(s): Motor Driven Only.
268000 (SF9 RW) Radwaste 271000 (SF9 OG) Offgas 272000 (SF7, SF9 RMS) Radiation Monitoring 08 Knowledge of the effect that a loss or 2.9 malfunction of the RADIATION MONITORING System will have on following: Auxiliary building ventilation.
286000 (SF8 FPS) Fire Protection 288000 (SF9 PVS) Plant Ventilation 290001 (SF5 SC) Secondary Containment 01 Knowledge of SECONDARY 3.5 CONTAINMENT design feature(s) and/or interlocks which provide for the following: Personnel access without breaching secondary containment.
290003 (SF9 CRV) Control Room Ventilation 290002 (SF5 RVI) Reactor Vessel Internals K/A Category Point Totals: 1 1 1 2 1 1 1 1 1 1 1 Group Point Total: 12 START SRO WRITTEN EXAM OUTLINE
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 4. Knowledge of the specific bases for EOPs. 4.0 AC Power / 6 18 295004 (APE 4) Partial or Total Loss of DC Power / 6 295005 (APE 5) Main Turbine Generator Trip
/3 295006 (APE 6) Scram / 1 02 Ability to determine and/or interpret the following as 3.6 they apply to SCRAM: Control Rod position.
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 01 Ability to determine and/or interpret the following as 3.5 Instrument Air / 8 they apply to PARTIAL OR COMPLETE LOSS OF INSTRUMENT AIR: Instrument air system pressure.
295021 (APE 21) Loss of Shutdown Cooling /
4 295023 (APE 23) Refueling Accidents / 8 295024 High Drywell Pressure / 5 1. Ability to explain and apply system limits and 4.0 32 precautions.
295025 (EPE 2) High Reactor Pressure / 3 295026 (EPE 3) Suppression Pool High 2. Knowledge of the bases in Technical Specifications 4.2 Water Temperature / 5 25 for limiting conditions for operations and safety limits.
295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 295028 (EPE 5) High Drywell Temperature 02 Ability to determine and/or interpret the following as 3.9 (Mark I and Mark II only) / 5 they apply to HIGH DRYWELL TEMPERATURE:
Reactor pressure.
295030 (EPE 7) Low Suppression Pool Water Level / 5 295031 (EPE 8) Reactor Low Water Level / 2 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 295038 (EPE 15) High Offsite Radioactivity 04 Ability to determine and/or interpret the following as 4.1 Release Rate / 9 they apply to HIGH OFF-SITE RELEASE RATE:
Source of offsite release.
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 11 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #
295002 (APE 2) Loss of Main Condenser Vacuum / 3 295007 (APE 7) High Reactor Pressure / 3 295008 (APE 8) High Reactor Water Level / 2 295009 (APE 9) Low Reactor Water Level / 2 295010 (APE 10) High Drywell Pressure / 5 295011 (APE 11) High Containment Temperature (Mark III Containment only) / 5 295012 (APE 12) High Drywell Temperature /
5 295013 (APE 13) High Suppression Pool Temperature. / 5 295014 (APE 14) Inadvertent Reactivity Addition / 1 295015 (APE 15) Incomplete Scram / 1 1. Ability to locate and operate components, including 4.0 30 local controls.
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 01 Ability to determine and/or interpret the following 3.9 Level / 5 as they apply to HIGH SUPPRESSION POOL WATER LEVEL: Suppression pool water level.
295032 (EPE 9) High Secondary Containment Area Temperature / 5 295033 (EPE 10) High Secondary 01 Ability to determine and/or interpret the following 3.9 Containment Area Radiation Levels / 9 as they apply to HIGH SECONDARY CONTAINMENT AREA RADIATION LEVELS:
Area radiation levels.
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 12 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 11 Ability to (a) predict the impacts of the following 2.7 on the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING MODE) ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Recirculation pump trips.
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 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling 218000 (SF3 ADS) Automatic 03 Ability to (a) predict the impacts of the following 3.6 Depressurization on the AUTOMATIC DEPRESSURIZATION SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Loss of air supply to ADS valves.
223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff 239002 (SF3 SRV) Safety Relief 2. Ability to apply Technical Specifications for a 4.7 Valves 40 system.
259002 (SF2 RWLCS) Reactor Water Level Control 261000 (SF9 SGTS) Standby Gas Treatment 262001 (SF6 AC) AC Electrical Distribution 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC)
ES-401 13 Form ES-401-1 263000 (SF6 DC) DC Electrical 1. Ability to evaluate plant performance and make 4.7 Distribution 07 operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.
264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG 300000 (SF8 IA) Instrument Air 4. Ability to verify that the alarms are consistent 4.2 46 with the plant conditions.
400000 (SF8 CCS) Component Cooling Water K/A Category Point Totals: 2 3 Group Point Total: 5
ES-401 14 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 01 Ability to (a) predict the impacts of 3.4 Control the following on the RECIRCULATION FLOW CONTROL SYSTEM ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Recirculation pump trip 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 2. Ability to determine operability 4.6 37 and/or availability of safety related l equipment.
216000 (SF7 NBI) Nuclear Boiler Instrumentation 219000 (SF5 RHR SPC) RHR/LPCI:
Torus/Suppression Pool Cooling Mode 223001 (SF5 PCS) Primary Containment and Auxiliaries 226001 (SF5 RHR CSS) RHR/LPCI:
Containment Spray Mode 230000 (SF5 RHR SPS) RHR/LPCI:
Torus/Suppression Pool Spray Mode 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup 234000 (SF8 FH) Fuel-Handling Equipment 239001 (SF3, SF4 MRSS) Main and Reheat 10 Ability to (a) predict the impacts of 3.9 Steam the following on the MAIN AND REHEAT STEAM SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Closure of one or more MSIVs at power.
239003 (SF9 MSVLCS) Main Steam Isolation Valve Leakage Control 241000 (SF3 RTPRS) Reactor/Turbine Pressure Regulating
ES-401 15 Form ES-401-1 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 256000 (SF2 CDS) Condensate 259001 (SF2 FWS) Feedwater 268000 (SF9 RW) Radwaste 271000 (SF9 OG) Offgas 272000 (SF7, SF9 RMS) Radiation Monitoring 286000 (SF8 FPS) Fire Protection 288000 (SF9 PVS) Plant Ventilation 290001 (SF5 SC) Secondary Containment 290003 (SF9 CRV) Control Room Ventilation 290002 (SF4 RVI) Reactor Vessel Internals K/A Category Point Totals: 2 1 Group Point Total: 3
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: FERMI Date of Exam: Week of 2/26/2018 Category K/A # Topic RO SRO-only IR # IR #
2.1. Ability to evaluate plant performance and make operational judgments 4.4 based on operating characteristics, reactor behavior, and instrument interpretation. (2.1.7) 2.1. Ability to locate control room switches, controls, and indications, and to 4.6 determine that they correctly reflect the desired plant lineup. (2.1.31)
- 1. Conduct of 2.1. Ability to identify and interpret diverse indications to validate the response 4.3 Operations of another indication. (2.1.45) 2.1. Ability to interpret reference materials, such as graphs, curves, tables, etc. 4.2 (2.1.25) 2.1. Knowledge of procedures, guidelines, or limitations associated with 4.6 reactivity management. (2.1.37)
Subtotal 3 2 2.2. Knowledge of surveillance procedures. (2.2.12) 3.7 2.2. Ability to determine the expected plant configuration using design and 3.9 configuration control documentation, such as drawings, line-ups, tag-outs, etc. (2.2.15)
- 2. Equipment 2.2. Knowledge of less than or equal to one hour Technical Specification action 3.9 Control statements for systems. (2.2.39) 2.2. Knowledge of maintenance work order requirements. (2.2.19) 3.4 2.2. Knowledge of the bases in Technical Specifications for limiting conditions 4.2 for operations and safety limits. (2.2.25)
Subtotal 3 2 2.3. Knowledge of radiological safety principles pertaining to licensed operator 3.2 duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
(2.3.12)
- 3. Radiation Control 2.3. Knowledge of radiation or contamination hazards that may arise during 3.4 normal, abnormal, or emergency conditions or activities. (2.3.14) 2.3. Ability to approve release permits. (2.3.6) 3.8 Subtotal 2 1 2.4. Knowledge of abnormal condition procedures. (2.4.11) 4.0 2.4. Knowledge of operator response to loss of all annunciators. (2.4.32) 3.6
- 4. Emergency 2.4. Ability to take actions called for in the facility emergency plan, including 4.4 Procedures/ supporting or acting as emergency coordinator if required. (2.4.38)
Plan 2.4. Ability to diagnose and recognize trends in an accurate and timely manner 4.2 utilizing the appropriate control room reference material. (2.4.47)
Subtotal 2 2 Tier 3 Point Total 10 7