ML20069G398
| ML20069G398 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 02/27/2020 |
| From: | Chuck Zoia NRC/RGN-III/DRS/OLB |
| To: | DTE Energy, Detroit Edison, Co |
| Zoia C | |
| Shared Package | |
| ML19303A603 | List: |
| References | |
| Download: ML20069G398 (17) | |
Text
ES-401 1 Form ES-401-1 Facility: Fermi Date of Exam: January 2020 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 2 1 1 1 1 1 7 1 2 3 Abnormal Plant Evolutions Tier Totals 5 4 5 5 4 4 27 5 5 10 1 2 2 3 2 3 2 3 2 2 3 2 26 3 2 5 2.
Plant 2 1 1 1 1 1 2 1 1 1 1 1 12 0 1 2 3 Systems Tier Totals 3 3 4 3 4 4 4 3 3 4 3 38 4 4 8
- 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 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 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 #
AK3.06 - Knowledge of the reasons for the 295001 (APE 1) Partial or Complete Loss of 06 following responses as they apply to 2.9 1 Forced Core Flow Circulation / 1 & 4 PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:
Core flow indication.
(CFR: 41.5 / 45.6)
AA1.02 - Ability o operate and/or monitor 295003 (APE 3) Partial or Complete Loss of 02 the following as they apply to PARTIAL OR 4.2 2 AC Power / 6 COMPLETE LOSS OF AC POWER:
Emergency generators.
(CFR: 41.7 / 45.6)
AA2.01 - Ability to determine and/or 295004 (APE 4) Partial or Total Loss of DC 01 interpret the following as they apply to 3.2 3 Power / 6 PARTIAL OR COMPLETE LOSS OF DC POWER: Cause of partial or complete loss of DC power.
(CFR: 41.10 / 43.5 / 45.13)
G2.1.20 - Ability to interpret and execute 295005 (APE 5) Main Turbine Generator Trip / 01. procedure steps. 4.6 4 3 20 (CFR: 41.10 / 43.5 / 45.12)
AK1.03 - Knowledge of the operational 295006 (APE 6) Scram / 1 03 implications of the following concepts as 3.7 5 they apply to SCRAM: Reactivity control (CFR: 41.8 to 41.10)
AK2.01 - Knowledge of the interrelations 295016 (APE 16) Control Room Abandonment 01 between CONTROL ROOM 4.4 6
/7 ABANDONMENT and the following: Remote shutdown panel: Plant-specific (CFR: 41.7 / 45.6)
AK3.02 - Knowledge of the reasons for the 295018 (APE 18) Partial or Complete Loss of 02 following responses as they apply to 3.3 7 CCW / 8 PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: Reactor power reduction.
(CFR: 41.5 / 45.6)
AA1.01 - Ability to operate and/or monitor 295019 (APE 19) Partial or Complete Loss of 01 the following as thy apply to PARTIAL OR 3.5 8 Instrument Air / 8 COMPLETE LOSS OF INSTRUMENT AIR:
Backup air supply.
(CFR: 41.7 / 45.6)
AA2.02 - Ability to determine and/or 295021 (APE 21) Loss of Shutdown Cooling / 02 interpret the following as they apply to 3.4 9 4 LOSS OF SHUTDOWN COOLING:
RHR/Shutdown cooling system flow.
(CFR: 41.10 / 43.5 / 45.13)
G2.1.7 - Ability to evaluate plant 295023 (APE 23) Refueling Accidents / 8 01. performance and make operational 4.4 10 07 judgements based on operating characteristics, reactor behavior, and instrument interpretation.
(CFR: 41.5 / 43.5 / 45.12, 45.13)
EK1.01 - Knowledge of the operational 295024 High Drywell Pressure / 5 01 implications of the following concepts as 4.1 11 they apply to HIGH DRYWELL PRESSURE:
Drywell integrity: Plant-specific.
(CFR: 41.8 to 41.10)
EK2.08 - Knowledge of the interrelations 295025 (EPE 2) High Reactor Pressure / 3 08 between HIGH REACTOR PRESSURE and 3.7 12 the following: Reactor/turbine regulating system: Plant-specific.
(CFR: 41.7 / 45.8)
ES-401 3 Form ES-401-1 EK3.02 - Knowledge of the reasons for the 295026 (EPE 3) Suppression Pool High Water 02 following responses as they apply to 3.9 13 Temperature / 5 SUPPRESSION POOL HIGH WATER TEMPERATURE: Suppression pool cooling.
(CFR: 41.5 / 45.6) 295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 EA1.01 - Ability to operate and/or monitor 295028 (EPE 5) High Drywell Temperature 01 the following as they apply to HIGH 3.8 14 (Mark I and Mark II only) / 5 DRYWELL TEMPERATURE: Drywell spray:
Mark-1&II.
(CFR: 41.7 / 45.6)
EA2.03 - Ability to determine and/or 295030 (EPE 7) Low Suppression Pool Water 02 interpret the following as they apply to LOW 3.7 15 Level / 5 SUPPRESSION POOL WATER LEVEL:
Reactor pressure.
(CFR: 41.10 / 43.5 / 45.13)
G2.4.49 - Ability to perform without 295031 (EPE 8) Reactor Low Water Level / 2 04. reference to procedures those actions that 4.6 16 49 require immediate operation of system components and controls.
(CFR: 41.10 / 43.2 / 45.6)
EK1.06 - Knowledge of the operational 295037 (EPE 14) Scram Condition Present 06 implications of the following concepts as 4.0 17 and Reactor Power Above APRM Downscale they apply to SCRAM CONDITION or Unknown / 1 PRESENT AND REACTOR POWER ABOVE APRM DOWNSCALE OR UNKNOWN: Cooldown effects on reactor power.
(CFR: 41.8 to 41.10)
AK2.03 - Knowledge of the interrelations 295038 (EPE 15) High Offsite Radioactivity 03 between HIGH OFF-SITE RELEASE RATE 3.3 Release Rate / 9 and the following: Off-gas system.
(CFR: 41.7 / 45.8) 3.6 18 EK2.03 - Knowledge of the interrelations between HIGH OFF-SITE RELEASE RATE and the following: Plant ventilation system.
(CFR: 41.7 / 45.8)
AK3.04 - Knowledge of the reasons for the 600000 (APE 24) Plant Fire On Site / 8 04 following responses as they apply to PLANT 2.8 19 FIRE ON SITE: Actions contained in the abnormal procedure for plant fire on site.
(CFR: 41.10 / 45.8)
AA1.04 - Ability to operate and/or monitor 700000 (APE 25) Generator Voltage and 04 the following as they apply to GENERATOR 4.1 20 Electric Grid Disturbances / 6 VOLTAGE AND ELECTRIC GRID DISTURBANCES: Reactor controls.
(CFR: 41.5, 41.10 / 45.5, 45.7, 45.8)
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 Vacuum / 3 AK1.04 - Knowledge of the operational 295007 (APE 7) High Reactor Pressure / 3 04 implications of the following concepts as 2.7 21 they apply to HIGH REACTOR PRESSURE: Turbine load.
(CFR: 41.8 to 41.10) 295008 (APE 8) High Reactor Water Level / 2 295009 (APE 9) Low Reactor Water Level / 2 AK2.01 - Knowledge of the interrelations 295010 (APE 10) High Drywell Pressure / 5 01 between HIGH DRYWELL PRESSURE 3.2 22 and the following: Suppression pool level.
(CFR: 41.7 / 45.8) 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 AK3.02 - Knowledge of the reasons for the 295014 (APE 14) Inadvertent Reactivity 02 following responses as they apply to 3.7 23 Addition / 1 INADVERTENT REACTIVITY ADDITION:
Control rod blocks.
(CFR: 41.5 / 45.6)
AA1.03 - Ability to operate and/or monitor 295015 (APE 15) Incomplete Scram / 1 03 the following as they apply to 3.6 24 INCOMPLETE SCRAM: RMCS: Plant-specific.
(CFR: 41.7 / 45.6) 295017 (APE 17) Abnormal Offsite Release Rate / 9 AA2.05 - Ability to determine and/or 295020 (APE 20) Inadvertent Containment 05 interpret the following as they apply to 3.6 25 Isolation / 5 & 7 INADVERTENT CONTAINMENT ISOLATION: Reactor water level.
(CFR: 41.10 / 43.5 / 45.13) 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 G2.4.20 - Knowledge of the operational 295033 (EPE 10) High Secondary 01. implications of EOP warnings, cautions, 3.8 26 Containment Area Radiation Levels / 9 20 and notes.
(CFR: 41.10 / 43.5 / 45.13) 295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9 EK1.01 - Knowledge of the operational 295035 (EPE 12) Secondary Containment 01 implications of the following concepts as 3.9 27 High Differential Pressure / 5 they apply to SECONDARY CONTAINMENT HIGH DIFFERENTIAL PRESSURE: Secondary containment integrity.
(CFR: 41.8 to 41.10)
ES-401 5 Form ES-401-1 295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5 500000 (EPE 16) High Containment Hydrogen Concentration / 5 K/A Category Point Totals: 2 1 1 1 1 1 Group Point Total: 7
ES-401 6 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 1 (RO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #
203000 (SF2, SF4 RHR/LPCI) x K1.07 - Knowledge of the physical 3.1 28 RHR/LPCI: Injection Mode connections and/or cause-effect relationships between RHR/LPCI:
INJECTINO MODE (PLANT SPECIFIC) and the following: DC electrical power.
(CFR: 41.2 to 41.9 / 45.7, 45.8)
- 02. G2.2.42 - Ability to recognize system 3.9 29 42 parameters that are entry-level conditions for Technical Specifications.
(CFR:41.7, 41.10 / 43.2, 43.3 / 45.3) 205000 (SF4 SCS) Shutdown Cooling 09 A4.09 - Ability to manually operate and/or 3.1 30 monitor in the control room: System flow.
(CFR: 41.7 / 45.5 to 45.8) 206000 (SF2, SF4 HPCIS) 04 A3.04 - Ability to monitor automatic 4.2 31 High-Pressure Coolant Injection operations of the HIGH PRESSURE COOLANT INJECTION SYSTEM including:
System lineup: BWR-2,3,4 (CFR: 41.7 / 45.7) 207000 (SF4 IC) Isolation (Emergency) Condenser 209001 (SF2, SF4 LPCS) 08 A2.08 - Ability to (a) predict the impacts of 3.1 32 Low-Pressure Core Spray the following on the LOW PRESSURE CORE SPRAY SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Valve openings.
(CFR: 41.5 / 45.6) 209002 (SF2, SF4 HPCS)
High-Pressure Core Spray 211000 (SF1 SLCS) Standby Liquid 09 A1.09 - Ability to predict and/or monitor 4.0 33 Control changes in parameters associated with operating the STANDBY LIQUID CONTROL SYSTEM controls including: SBLC system lineup.
(CFR: 41.5 / 45.5) 212000 (SF7 RPS) Reactor Protection 03 K6.03 - Knowledge of the effect that a loss 3.5 34 or malfunction of the following will have on the REACTOR PROTECTION SYSTEM:
Nuclear boiler instrumentation.
(CFR: 41.7 / 45.7) 215003 (SF7 IRM) 01 K5.01 - Knowledge of the operational 2.6 35 Intermediate-Range Monitor implications of the following concepts as they apply to INTERMEDIATE RANGE MONITOR (IRM) SYSTEM: Detector operation.
(CFR: 41.5 / 45.3) 215004 (SF7 SRMS) Source-Range 01 K3.01 - Knowledge of the effect that a loss 3.4 36 Monitor or malfunction of the SOURCE RANGE MONITOR (SRM) SYSTEM will have on following: RPS.
(CFR: 41.7 / 45.4) 02 K4.02 - Knowledge of SOURCE RANGE 3.4 37 MONITOR (SRM) SYSTEM design feature(s) and/or interlocks which provide for the following: Reactor SCRAM signals.
(CFR: 41.7)
ES-401 7 Form ES-401-1 215005 (SF7 PRMS) Average Power 06 K3.06 - Knowledge of the effect that a loss 3.5 38 Range Monitor/Local Power Range or malfunction of the AVERAGE POWER RANGE MONITOR/LOCAL POWER Monitor RANGE MONITOR SYSTEM will have on following: IRM: Plant-specific.
(CFR: 41.7 / 45.4) 217000 (SF2, SF4 RCIC) Reactor 03 K2.03 - Knowledge of electrical power 2.7 39 Core Isolation Cooling supplies to the following: RCIC flow controller (CFR: 41.7) 218000 (SF3 ADS) Automatic 06 K1.06 - Knowledge of the physical 3.9 40 Depressurization connections and/or cause-effect relationships between AUTOMATIC DEPRESSURIZATION SYSTEM and the following: Safety/relief valves (CFR: 41.2 to 41.9 / 45.7, 45.8) 223002 (SF5 PCIS) Primary 01. G2.1.23 - Ability to perform specific system 4.3 41 Containment Isolation/Nuclear Steam 23 and integrated plant procedures during all modes of plant operation.
Supply Shutoff (CFR: 41.10 / 43.5 / 45.2, 45.6) 239002 (SF3 SRV) Safety Relief 06 A4.06 - Ability to manually operate and/or 3.9 42 Valves monitor in the control room: Reactor water level.
(CFR: 41.7 / 45.5 to 45.8) 259002 (SF2 RWLCS) Reactor Water 07 K5.07 - Knowledge of the operational 2.7 43 Level Control implications of the following concepts as they apply to REACTOR WATER LEVEL CONTROL SYSTEM: Turbine speed control mechanisms: TDRFP.
(CFR: 41.5 / 45.3) 03 A3.03 - Ability to monitor automatic 3.2 44 operations of the REACTOR WATER LEVEL CONTROL SYSTEM including:
Changes in main steam flow.
(CFR: 41.7 / 45.7) 261000 (SF9 SGTS) Standby Gas 04 A1.04 - Ability to predict and/or monitor 3.0 45 Treatment changes in parameters associated with operating the STANDBY GAS TREATMENT SYSTEM controls including: Secondary containment differential pressure.
(CFR: 41.5 / 45.5) 05 A2.05 - Ability to (a) predict the impacts of 3.0 46 the following on the STANDBY GAS TREATMENT SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Fan trips.
(CFR: 41.5 / 45.6) 262001 (SF6 AC) AC Electrical 03 A1.03 - Ability to predict and/or monitor 2.9 47 Distribution changes in parameters associated with operating the AC ELECTRICAL DISTRIBUTION controls including: Bus voltage.
(CFR: 41.5 / 45.5) 262002 (SF6 UPS) Uninterruptable 03 K6.03 - Knowledge of the effect that a loss 2.7 48 Power Supply (AC/DC) or malfunction of the following will have on the UNINTERRUPTIBLE POWER SUPPLY (AC/DC): Static inverter.
(CFR: 41.7 / 45.7) 263000 (SF6 DC) DC Electrical 01 K5.01 - Knowledge of the operational 2.6 49 Distribution implications of the following concepts as they apply to DC ELECTRICAL DISTRIBUTION: Hydrogen generation during battery charging (CFR: 41.5 / 45.3)
ES-401 8 Form ES-401-1 264000 (SF6 EGE) Emergency 06 K4.06 - Knowledge of EMERGENCY 2.6 50 Generators (Diesel/Jet) EDG GENERATORS (DIESEL/JET) design feature(s) and/or interlocks which provide for the following: Governor control.
(CFR: 41.7) 02 A4.02 - Ability to manually operate and/or 3.4 51 monitor in the control room: Synchroscope (CFR: 41.7 / 45.5 to 45.8) 300000 (SF8 IA) Instrument Air 02 K3.02 - Knowledge of the effect that a loss 3.3 52 or malfunction of the (INSTRUMENT AIR SYSTEM) will have on the following:
Systems having pneumatic valves and controls.
(CFR: 41.7 / 45.6) 400000 (SF8 CCS) Component 02 K2.02 - Knowledge of the electrical power 2.9 53 Cooling Water supplies to the following: CCW valves.
(CFR: 41.7) 510000 (SF4 SWS*) Service Water (Normal and Emergency)
K/A Category Point Totals: 2 2 3 2 3 2 3 2 2 3 2 Group Point Total: 26
ES-401 9 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 2 (RO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #
201001 (SF1 CRDH) CRD Hydraulic K6.05 - Knowledge of the effect that a 05 loss or malfunction of the following will 3.3 54 have on the CONTROL ROD DRIVE HYDRAULIC system: AC power.
(CFR: 41.7 / 45.7) 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 A1.02 - Ability to predict and/or monitor 02 changes in parameters associated with 3.4 55 operating the ROD WORTH MINIMIZER SYSTEM (RWM) (PLANT SPECIFIC) controls including: Status of control rod movement blocks; P-spec (Not-BWR6)
(CFR: 41.5 / 45.5) 202001 (SF1, SF4 RS) Recirculation A2.13 - Ability to (a) predict the impacts 13 of the following on the RECIRCULATION 2.6 56 SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Carryunder.
(CFR: 41.5 / 45.6) 202002 (SF1 RSCTL) Recirculation Flow Control 204000 (SF2 RWCU) Reactor Water Cleanup A3.03 - Ability to monitor automatic 03 operations of the REACTOR WATER 3.6 57 CLEANUP SYSTEM including: Response to system isolations.
(CFR: 41.7 / 45.7) 214000 (SF7 RPIS) Rod Position Information 215001 (SF7 TIP) Traversing In-Core Probe 215002 (SF7 RBMS) Rod Block Monitor A4.03 - Ability to manually operate and/or 03 monitor in the control room: Trip 2.8 58 bypasses: BWR-3,4,5 (CFR: 41.7 / 45.5 to 45.8) 216000 (SF7 NBI) Nuclear Boiler Instrumentation 219000 (SF5 RHR SPC) RHR/LPCI: G2.2.12 - Knowledge of surveillance
- 02. procedures. 3.7 59 Torus/Suppression Pool Cooling Mode 12 (CFR: 41.10 / 45.13) 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 Steam K2.01 - Knowledge of electrical power 01 supplies to the following: Main steam 3.2 60 isolation valve solenoids.
(CFR: 41.7) 239003 (SF9 MSVLCS) Main Steam Isolation Valve Leakage Control 241000 (SF3 RTPRS) Reactor/Turbine Pressure Regulating 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 256000 (SF2 CDS) Condensate 259001 (SF2 FWS) Feedwater
ES-401 10 Form ES-401-1 268000 (SF9 RW) Radwaste K1.09 - Knowledge of the physical 09 connections and/or cause-effect 2.6 61 relationships between RADWASTE and the following: ECCS systems.
(CFR: 41.2 to 41.9 / 45.7, 45.8) 271000 (SF9 OG) Offgas K3.02 - Knowledge of the effect that a 02 loss or malfunction of the OFFGAS 3.3 62 SYSTEM will have on the following: Off-site radioactive release rate.
(CFR: 41.5 / 45.3) 272000 (SF7, SF9 RMS) Radiation Monitoring 286000 (SF8 FPS) Fire Protection K4.02 - Knowledge of FIRE 02 PROTECTION SYSTEM design feature(s) 3.3 63 and/or interlocks which provide for the following: Automatic system initiation.
(CFR: 41.5 / 45.7) 288000 (SF9 PVS) Plant Ventilation 290001 (SF5 SC) Secondary Containment 290003 (SF9 CRV) Control Room Ventilation K5.03 - Knowledge of the operational 03 implications of the following concepts as 2.6 64 they apply to CONTROL ROOM HVAC:
Temperature control.
(CFR: 41.5 / 45.3) 290002 (SF4 RVI) Reactor Vessel Internals K6.07 - Knowledge of the effect that a 07 loss or malfunction of the following will 2.6 65 have on the REACTOR VESSEL INTERNALS: RWCU.
(CFR: 41.7 / 45.7) 51001 (SF8 CWS*) Circulating Water K/A Category Point Totals: 1 1 1 1 1 2 1 1 1 1 1 Group Point Total: 12
ES-401 11 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #
AA2.04 - Ability to determine and/or 295001 (APE 1) Partial or Complete Loss of 04 interpret the following they apply to 3.1 76 Forced Core Flow Circulation / 1 & 4 PARTIAL OR COMPLETE LOSS OF FORCED CORE FLOW CIRCULATION:
Individual jet pump flows: Not-BWR-1&2.
(CFR: 41.10 / 43.5 / 45.13) 295003 (APE 3) Partial or Complete Loss of AC Power / 6 295004 (APE 4) Partial or Total Loss of DC Power / 6 G2.2.44 - Ability to interpret control room 295005 (APE 5) Main Turbine Generator Trip / 02. indications to verify the status and operation 4.4 77 3 44 of a system and understand how operator actions and directives affect plant and system conditions.
(CFR: 41.5 / 43.5 / 45.12) 295006 (APE 6) Scram / 1 AA2.01 - Ability to determine and/or 295016 (APE 16) Control Room Abandonment 01 interpret the following as they apply to 4.1 78
/7 CONTROL ROOM ABANDONMENT:
Reactor power.
(CFR: 41.10 / 43.5 / 45.13)
G2.4.31 - Knowledge of annunciator 295018 (APE 18) Partial or Complete Loss of 04. alarms, indications, or response 4.1 79 CCW / 8 31 procedures.
(CFR: 41.10 / 45.3) 295019 (APE 19) Partial or Complete Loss of Instrument Air / 8 295021 (APE 21) Loss of Shutdown Cooling /
4 295023 (APE 23) Refueling Accidents / 8 295024 High Drywell Pressure / 5 295025 (EPE 2) High Reactor Pressure / 3 295026 (EPE 3) Suppression Pool High Water Temperature / 5 295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only) / 5 EA2.02 - Ability to determine and/or 295030 (EPE 7) Low Suppression Pool Water 02 interpret the following as they apply to LOW 3.9 80 Level / 5 SUPPRESSION POOL WATER LEVEL:
Suppression pool temperature.
(CFR: 41.10 / 43.5 / 45.13) 295031 (EPE 8) Reactor Low Water Level / 2 G2.4.8 - Knowledge of how abnormal 295037 (EPE 14) Scram Condition Present 04. operating procedures are used in 4.5 81 and Reactor Power Above APRM Downscale 08 conjunction with EOPs.
or Unknown / 1 (CFR: 41.10 / 43.5 / 45.13) 295038 (EPE 15) High Offsite Radioactivity Release Rate / 9 600000 (APE 24) Plant Fire On Site / 8
ES-401 12 Form ES-401-1 AA2.07 - Ability to determine and/or 700000 (APE 25) Generator Voltage and 07 interpret the following as they apply to 4.0 82 Electric Grid Disturbances / 6 GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES: Operational status of engineered safety features.
(CFR: 41.5 / 43.5 / 45.5, 45.7, 45.8)
K/A Category Totals: 4 3 Group Point Total: 7
ES-401 13 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #
295002 (APE 2) Loss of Main Condenser Vacuum / 3 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 G2.4.18 - Knowledge of the specific bases 295012 (APE 12) High Drywell Temperature / 04. for EOPs. 4.0 83 5 18 (CFR: 41.10 / 43.1 / 45.13) 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 AA2.01 - Ability to determine and/or 295022 (APE 22) Loss of Control Rod Drive 01 interpret the following as they apply to 3.6 84 Pumps / 1 LOSS OF CRD PUMPS: Accumulator pressure.
(CFR: 41.10 / 43.5 / 45.13)
G2.4.3 - Ability to identify post-accident 295029 (EPE 6) High Suppression Pool Water 04- instrumentation. 3.9 85 Level / 5 03 (CFR: 41.6 / 45.4) 295032 (EPE 9) High Secondary Containment Area Temperature / 5 295033 (EPE 10) High Secondary Containment Area Radiation Levels / 9 295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9 295035 (EPE 12) Secondary Containment High Differential Pressure / 5 295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5 500000 (EPE 16) High Containment Hydrogen Concentration / 5 K/A Category Point Totals: 1 2 Group Point Total: 3
ES-401 14 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 1 (SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #
203000 (SF2, SF4 RHR/LPCI)
RHR/LPCI: Injection Mode 205000 (SF4 SCS) Shutdown Cooling 206000 (SF2, SF4 HPCIS) 17 A2.17 - Ability to (a) predict the impacts of 4.3 86 High-Pressure Coolant Injection the following on the HIGH PRESSURE COOLANT INJECTION SYSTEM: and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: HPCI inadvertent initiation:
BWR-2,3,4.
(CFR: 41.5 / 45.6) 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) 02. G2.2.36 - Ability to analyze the effect of 4.5 87 Intermediate-Range Monitor 36 maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.
(CFR: 41.10 / 43.2 / 45.13) 215004 (SF7 SRMS) Source-Range Monitor 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor 217000 (SF2, SF4 RCIC) Reactor 11 A2.11 - Ability to (a) predict the impacts of 3.2 88 Core Isolation Cooling the following on the REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM:
and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Inadequate system flow.
(CFR: 41.5 / 45.6) 218000 (SF3 ADS) Automatic Depressurization 223002 (SF5 PCIS) Primary 02. G2.2.37 - Ability to determine operability 4.6 89 Containment Isolation/Nuclear Steam 37 and/or availability of safety related equipment.
Supply Shutoff (CFR: 41.7 / 43.5 / 45.12) 239002 (SF3 SRV) Safety Relief Valves 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 15 Form ES-401-1 263000 (SF6 DC) DC Electrical 01 A2.01 - Ability to (a) predict the impacts of 3.2 90 Distribution the following on the DC ELECTRICAL DISTRUBTION: and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Grounds.
(CFR: 41.5 / 45.6) 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG 300000 (SF8 IA) Instrument Air 400000 (SF8 CCS) Component Cooling Water 510000 (SF4 SWS*) Service Water (Normal and Emergency)
K/A Category Point Totals: 3 2 Group Point Total: 5
ES-401 16 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 2 (SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #
201001 (SF1 CRDH) CRD Hydraulic 201002 (SF1 RMCS) Reactor Manual Control 201003 (SF1 CRDM) Control Rod and Drive G2.2.40 - Ability to apply Technical
- 02. Specifications for a system. 4.7 91 Mechanism 40 (CFR: 41.10 / 43.2, 43.5 / 45.3) 201004 (SF7 RSCS) Rod Sequence Control 201005 (SF1, SF7 RCIS) Rod Control and Information 201006 (SF7 RWMS) Rod Worth Minimizer 202001 (SF1, SF4 RS) Recirculation 202002 (SF1 RSCTL) Recirculation Flow Control 204000 (SF2 RWCU) Reactor Water Cleanup 214000 (SF7 RPIS) Rod Position Information 215001 (SF7 TIP) Traversing In-Core Probe 215002 (SF7 RBMS) Rod Block Monitor 216000 (SF7 NBI) Nuclear Boiler Instrumentation A2.03 - Ability to (a) predict the impacts 03 of the following on the NUCLEAR BOILER 3.1 92 INSTRUMENTATION; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Instrument line leakage.
(CFR: 41.5 / 45.6) 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 Steam 239003 (SF9 MSVLCS) Main Steam Isolation Valve Leakage Control 241000 (SF3 RTPRS) Reactor/Turbine Pressure G2.4.46 - Ability to verify that alarms are
- 04. consistent with the plant conditions. 4.2 93 Regulating 46 (CFR: 41.10 / 43.5 / 45.3, 45.12) 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
ES-401 17 Form ES-401-1 51001 (SF8 CWS*) Circulating Water K/A Category Point Totals: 1 2 Group Point Total: 3