ML22236A018
| ML22236A018 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 05/14/2021 |
| From: | Chuck Zoia NRC/RGN-III/DRS/OLB |
| To: | Exelon Generation Co LLC |
| Zoia C | |
| Shared Package | |
| ML20136A310 | List: |
| References | |
| Download: ML22236A018 (20) | |
Text
ES-401 1 Form ES-401-1 Facility: Dresden Nuclear Power Station, Units 2 and 3 Date of Exam: April 19 - 30, 2021 Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total
- 1. 1 3 3 3 3 4 4 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 4 4 5 5 27 5 5 10 1 2 3 3 2 3 3 2 2 2 2 2 26 3 2 5 2.
Plant 2 1 1 1 2 1 1 1 1 1 1 1 12 0 1 2 3 Systems Tier Totals 3 4 4 4 4 4 3 3 3 3 3 38 4 4 8
- 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 2 3 3 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 #
AA2.04 - Ability to determine and/or 295001 (APE 1) Partial or Complete Loss of 04 interpret the following as they apply to 3.0 1 Forced Core Flow Circulation / 1 & 4 PARTIAL OR COMPLETE LOSS OF (1)
FORCED CORE FLOW CIRCULATION:
Individual jet pump flows: Not BWR 1&2 (CFR 41.10 / 43.5 /45.13)
G2.1.7 - Ability to evaluate plant 295003 (APE 3) Partial or Complete Loss of 01. performance and make operational 4.4 1 AC Power / 6 07 judgments based on operating (2) characteristics, reactor behavior, and instrument interpretation.
(CFR: 41.5 / 43.5 / 45.12, 45.13)
AK1.04 - Knowledge of the operational 295004 (APE 4) Partial or Total Loss of DC 04 implications of the following concepts as 2.8 1 Power / 6 they apply to PARTIAL OR COMPLETE LOSS OF DC POWER: Effect of battery (3) discharge rate on capacity (CFR: 41.8 to 41.10)
AK2.05 - Knowledge of the interrelations 295005 (APE 5) Main Turbine Generator Trip / 05 between the MAIN TURBINE GENERATOR 2.6 1 3 TRIP and the following: Extraction steam system (4)
(CFR 41.7 / 45.8)
AK3.02 - Knowledge of the reasons for the following responses as they apply to 1 295006 (APE 6) Scram / 1 02 SCRAM: Reactor power response 4.1*
(5)
(CFR: 41.5 / 45.6)
AA1.09 - Ability to operate and/or monitor 295016 (APE 16) Control Room Abandonment 09 the following as they apply to CONTROL 4.0 1
/7 ROOM ABANDONMENT:
(6)
Isolation/emergency condenser: Plant specific (CFR: 41.7 / 45.6)
AA2.04 - Ability to determine and/or 295018 (APE 18) Partial or Complete Loss of 04 interpret the following as they apply to 2.9 1 CCW / 8 PARTIAL OR COMPLETE LOSS OF COMPONENT COOLING WATER: System (7) flow (CFR: 41.10 / 43.5 / 45.13)
G2.4.8 - Knowledge of how abnormal 295019 (APE 19) Partial or Complete Loss of 04. operating procedures are used in 3.8 1 Instrument Air / 8 08 conjunction with EOPs.
(CFR: 41.10 / 43.5 / 45.13) (8)
AK1.01 - Knowledge of the operational 295021 (APE 21) Loss of Shutdown Cooling / 01 implications of the following concepts as 3.6 1 4 they apply to LOSS OF SHUTDOWN COOLING: Decay heat (9)
(CFR: 41.8 to 41.10)
AK2.04 - Knowledge of the interrelations 295023 (APE 23) Refueling Accidents / 8 04 between REFUELING ACCIDENTS and the 3.2 1 following: RMCS (CFR 41.7 / 45.8) (10)
EK3.07 - Knowledge of the reasons for the 295024 High Drywell Pressure / 5 07 following responses as they apply to HIGH 3.5 1 DRYWELL PRESSURE: Drywell venting (CFR: 41.5 / 45.6) (11)
EA1.01 - Ability to operate and/or monitor 295025 (EPE 2) High Reactor Pressure / 3 01 the following as they apply to HIGH 2.9 1 REACTOR PRESSURE: Main steam line drains (12)
(CFR: 41.7 / 45.6)
ES-401 3 Form ES-401-1 EA2.01 - Ability to determine and/or 295026 (EPE 3) Suppression Pool High Water 01 interpret the following as they apply to 4.1* 1 Temperature / 5 SUPPRESSION POOL HIGH WATER (13)
TEMPERATURE: Suppression pool water temperature (CFR: 41.10 / 43.5 / 45.13) 295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 G2.1.23 - Ability to perform specific system 295028 (EPE 5) High Drywell Temperature 01. and integrated plant procedures during all 4.3 1 (Mark I and Mark II only) / 5 23 modes of plant operation.
(CFR: 41.10 / 43.5 / 45.2 / 45.6) (14)
EK1.02 - Knowledge of the operational 295030 (EPE 7) Low Suppression Pool Water 02 implications of the following concepts as 3.5 1 Level / 5 they apply to LOW SUPPRESSION POOL WATER LEVEL: Pump NPSH (15)
(CFR: 41.8 to 41.10)
EK2.09 - Knowledge of the interrelations 295031 (EPE 8) Reactor Low Water Level / 2 09 between REACTOR LOW WATER LEVEL 3.3 1 and the following: Recirculation system:
(16)
Plant specific (CFR 41.7 / 45.8)
EK3.05 - Knowledge of the reasons for the 295037 (EPE 14) Scram Condition Present 05 following responses as they apply to 3.2 1 and Reactor Power Above APRM Downscale SCRAM CONDITION PRESENT AND or Unknown / 1 REACTOR POWER ABOVE APRM (17)
DOWNSCALE OR UNKNOWN: Cold shutdown boron weight: Plant specific (CFR: 41.5 / 45.6)
EA1.06 - Ability to operate and/or monitor 295038 (EPE 15) High Offsite Radioactivity 06 the following as they apply to HIGH OFF- 3.5 1 Release Rate / 9 SITE RELEASE RATE: Plant ventilation (CFR: 41.7 / 45.6) (18)
AA2.06 - Ability to determine and interpret 600000 (APE 24) Plant Fire On Site / 8 06 the following as they apply to PLANT FIRE 2.5 1 ON SITE: Need for pressurizing the control room (recirculation mode) (19)
(CFR: 41.10 / 43.5 / 45.13)
G2.4.45 - Ability to prioritize and interpret 700000 (APE 25) Generator Voltage and 04. the significance of each annunciator or 4.1 1 Electric Grid Disturbances / 6 45 alarm.
(20)
(CFR: 41.10 / 43.5 / 45.3 / 45.12)
K/A Category Totals: 3 3 3 3 4 4 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 #
AK1.04 - Knowledge of the operational 295002 (APE 2) Loss of Main Condenser 04 implications of the following concepts as 3.0 1 Vacuum / 3 they apply to LOSS OF MAIN CONDENSER VACUUM: Increased off (21) gas flow (CFR: 41.8 to 41.10) 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 AK2.01 - Knowledge of the interrelations 295012 (APE 12) High Drywell Temperature / 01 between HIGH DRYWELL 3.4 1 5 TEMPERATURE and the following:
Drywell ventilation (22)
(CFR 41.7 / 45.8)
AK3.01 - Knowledge of the reasons for the 295013 (APE 13) High Suppression Pool 01 following responses as they apply to HIGH 3.6 1 Temperature. / 5 SUPPRESSION POOL TEMPERATURE:
Suppression pool cooling operation (23)
(CFR: 41.5 / 45.6) 295014 (APE 14) Inadvertent Reactivity Addition / 1 295015 (APE 15) Incomplete Scram / 1 AA1.05 - Ability to operate and/or monitor 295017 (APE 17) Abnormal Offsite Release 05 the following as they apply to HIGH OFF- 2.7 1 Rate / 9 SITE RELEASE RATE: SPDS: Plant specific (24)
(CFR: 41.7 / 45.6)
G2.4.46 - Ability to verify that the alarms 295020 (APE 20) Inadvertent Containment 04. are consistent with the plant conditions. 4.2 1 Isolation / 5 & 7 46 (CFR: 41.10 / 43.5 / 45.3 / 45.12)
(25) 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 EA2.03 - Ability to determine and/or 295033 (EPE 10) High Secondary 03 interpret the following as they apply to 3.7 1 Containment Area Radiation Levels / 9 HIGH SECONDARY CONTAINMENT (26)
AREA RADIATION LEVELS: Cause of high area radiation (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 1 High Differential Pressure / 5 they apply to SECONDARY CONTAINMENT (27)
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) 03 K2.03 - Knowledge of electrical power 2.7* 1 RHR/LPCI: Injection Mode supplies to the following: Initiation logic (CFR: 41.7) (28) 205000 (SF4 SCS) Shutdown Cooling 03 K3.03 - Knowledge of the effect that loss or 3.8 1 malfunction of the SHUTDOWN COOLING SYSTEM (RHR SHUTDOWN COOLING (29)
MODE) will have on following: Reactor temperatures (moderator, vessel, flange)
(CFR: 41.7 / 45.4) 206000 (SF2, SF4 HPCIS) 19 K4.19 - Knowledge of HIGH-PRESSURE 3.7 1 High-Pressure Coolant Injection COOLANT INJECTION SYSTEM design feature(s) and/or interlocks which provide for (30) the following: Automatic transfer of HPCI pump suction: BWR-2,3,4 (CFR: 41.7) 207000 (SF4 IC) Isolation 09 K5.09 - Knowledge of the operational 3.7 1 (Emergency) Condenser implications of the following concepts as they apply to ISOLATION (EMERGENCY) (31)
CONDENSER: Cooldown rate BWR-2,3 (CFR: 41.5 / 45.3)
K6.08 - Knowledge of the effect that a loss or 08 malfunction of the following will have on the 3.5 1 ISOLATION (EMERGENCY) CONDENSER: (32)
DC power: BWR-2,3 (CFR: 41.7 / 45.7) 209001 (SF2, SF4 LPCS) 03 A1.03 - Ability to predict and/or monitor 3.8 1 Low-Pressure Core Spray changes in parameters associated with operating LOW PRESSURE CORE SPRAY (33)
SYSTEM controls including: Reactor water level (CFR: 41.5 / 45.5) 209002 (SF2, SF4 HPCS)
High-Pressure Core Spray 211000 (SF1 SLCS) Standby Liquid 02 A2.02 - Ability to (a) predict the impacts of 3.6 1 Control the following on the STANDBY LIQUID CONTROL SYSTEM; and (b) based on those (34) predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations: Failure of explosive valves to fire (CFR: 41.5 / 45.6) 212000 (SF7 RPS) Reactor Protection 07 A3.07 - Ability to monitor automatic 3.6 1 operations of the REACTOR PROTECTION SYSTEM including: SCRAM air header (35) pressure (CFR: 41.7 / 45.7) 215003 (SF7 IRM) 03 A4.03 - Ability to manually operate and/or 3.6 1 Intermediate-Range Monitor monitor in the control room: IRM range switches (36)
(CFR: 41.7 / 45.5 to 45.8) 215004 (SF7 SRMS) Source-Range 02 G2.2.44 - Ability to interpret control room 4.2 1 Monitor 44 indications to verify the status and operation (37) of a system and understand how operator actions and directives affect plant and system conditions.
(CFR: 41.5 / 43.5 / 45.12)
ES-401 7 Form ES-401-1 215005 (SF7 PRMS) Average Power 16 K1.16 - Knowledge of the physical 3.3 1 Range Monitor/Local Power Range connections and/or cause-effect relationships between AVERAGE POWER RANGE (38)
Monitor MONITOR/LOCAL POWER RANGE MONITOR SYSTEM and the following: Flow converter/comparator network: Plant specific (CFR: 41.2 to 41.9 / 45.7 to 45.8) 02 K2.02 - Knowledge of electrical power 2.6 1 supplies to the following: APRM channels (39)
(CFR: 41.7) 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling 218000 (SF3 ADS) Automatic 01 K3.01 - Knowledge of the effect that loss or 4.4* 1 Depressurization malfunction of the AUTOMATIC DEPRESSURIZATION SYSTEM will have on (40) following: Restoration of reactor water level after a break that does not depressurize the reactor when required (CFR: 41.7 / 45.4) 223002 (SF5 PCIS) Primary 08 K4.08 - Knowledge of PRIMARY 3.3 1 Containment Isolation/Nuclear Steam CONTAINMENT ISOLATION SYSTEM/NUCLEAR STEAM SUPPLY (41)
Supply Shutoff SHUT-OFF design feature(s) and/or interlocks which provide for the following:
Manual defeating of selected isolations during specified emergency conditions (CFR: 41.7)
K6.08 - Knowledge of the effect that a loss or 08 3.5 1 malfunction of the following will have on the PRIMARY CONTAINMENT ISOLATION (42)
SYSTEM/NUCLEAR STEAM SUPPLY SHUT-OFF: Reactor protection system (CFR: 41.7 / 45.7) 239002 (SF3 SRV) Safety Relief 02 K5.02 - Knowledge of the operational 3.7 1 Valves implications of the following concepts as they apply to RELIEF/SAFETY VALVES: Safety (43) function of SRV operation (CFR: 41.5 / 45.3) 259002 (SF2 RWLCS) Reactor Water 02 A1.02 - Ability to predict and/or monitor 3.6 1 Level Control changes in parameters associated with operating the REACTOR WATER LEVEL (44)
CONTROL SYSTEM controls including:
Reactor feedwater flow (CFR: 41.5 / 45.5) 261000 (SF9 SGTS) Standby Gas 14 A2.14 - Ability to (a) predict the impacts of 3.0 1 Treatment the following on the STANDBY GAS TREATMENT SYSTEM; and (b) based on (45) those predictions, use procedures to correct, control or mitigate the consequences of those abnormal conditions or operations: High system pressure: Plant specific (CFR: 41.5 / 45.6)
A3.02 - Ability to monitor automatic 02 3.2 1 operations of the STANDBY GAS TREATMENT SYSTEM including: Fan start (46)
(CFR: 41.7 / 45.7) 262001 (SF6 AC) AC Electrical 02 A4.02 - Ability to manually operate and/or 3.4 1 Distribution monitor in the control room: Synchroscope, including understanding of running and (47) incoming voltages (CFR: 41.7 / 45.5 to 45.8)
ES-401 8 Form ES-401-1 262002 (SF6 UPS) Uninterruptable 19 K1.19 - Knowledge of the physical 3.1 1 Power Supply (AC/DC) connections and/or cause-effect relationships between UNINTERRUPTABLE POWER (48)
SUPPLY (AC/DC) and the following: Power range neutron monitoring system: Plant Specific (CFR: 41.2 to 41.9 / 45.7 to 45.8) 263000 (SF6 DC) DC Electrical 01 K2.01 - Knowledge of electrical power 3.1 1 Distribution supplies to the following: Major DC loads (CFR: 41.7) (49) 01 G2.1.19 - Ability to use plant computers to 3.9 1 19 evaluate system or component status. (50)
(CFR: 41.10 / 45.12) 264000 (SF6 EGE) Emergency 03 K3.03 - Knowledge of the effect that loss or 4.1* 1 Generators (Diesel/Jet) EDG malfunction of the EMERGENCY GENERATORS (DIESEL/JET) will have on (51) following: Major loads powered from electrical buses fed by the emergency generators (CFR: 41.7 / 45.4) 300000 (SF8 IA) Instrument Air 13 K5.13 - Knowledge of the operational 2.9 1 implications of the following concepts as they apply to the INSTRUMENT AIR SYSTEM: (52)
Filters (CFR: 41.5 / 45.3) 400000 (SF8 CCS) Component 01 K6.01 - Knowledge of the effect that a loss or 2.7 1 Cooling Water malfunction of the following will have on the COMPONENT COOLING WATER SYSTEM: (53)
Valves (CFR: 41.7 / 45.7) 510000 (SF4 SWS*) Service Water (Normal and Emergency)
K/A Category Point Totals: 2 3 3 2 3 3 2 2 2 2 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 K4.10 - Knowledge of CONTROL ROD 10 DRIVE HYDRAULIC SYSTEM design 3.1 1 feature(s) and/or interlocks which provide for (54) the following: Control of rod movement (HCU directional control valves)
(CFR: 41.7) 201002 (SF1 RMCS) Reactor Manual A1.04 - Ability to predict and/or monitor 04 changes in parameters associated with 3.6 1 Control operating the REACTOR MANUAL (55)
CONTROL SYSTEM controls including:
Overall reactor power.
(CFR: 41.5 / 45.5) 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 A2.12 - Ability to (a) predict the impacts of 12 the following on the RECIRCULATION 3.6 1 SYSTEM; and (b) based on those (56) predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Loss of reactor feedwater (CFR: 41.5 / 45.6) 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 A3.03 - Ability to monitor automatic 03 operations of the ROD BLOCK MONITOR 3.1 1 Monitor SYSTEM including: Alarm and indicating (57) lights: BWR-3,4,5 (CFR: 41.7 / 45.7) 216000 (SF7 NBI) Nuclear Boiler Instrumentation 219000 (SF5 RHR SPC) RHR/LPCI:
Torus/Suppression Pool Cooling Mode 223001 (SF5 PCS) Primary A4.10 - Ability to manually operate and/or 10 monitor in the control room: Drywell nitrogen 3.2 1 Containment and Auxiliaries makeup: Mark I, II (58)
(CFR: 41.7 / 45.5 to 45.8) 226001 (SF5 RHR CSS) RHR/LPCI:
Containment Spray Mode 230000 (SF5 RHR SPS) RHR/LPCI: G2.4.31 - Knowledge of annunciator alarms, 04 indications, or response procedures. 4.2 1 Torus/Suppression Pool Spray Mode 31 (CFR: 41.10 / 45.3) (59)
ES-401 10 Form ES-401-1 233000 (SF9 FPCCU) Fuel Pool K1.01 - Knowledge of the physical 01 connections and/or cause-effect relationships 2.6 1 Cooling/Cleanup between FUEL POOL COOLING AND (60)
CLEANUP and the following: Shutdown cooling system: Plant specific (CFR: 41.2 to 41.9 / 45.7 to 45.8) 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 Regulating 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 256000 (SF2 CDS) Condensate K2.01 - Knowledge of electrical power 01 2.7* 1 supplies to the following: System pumps (CFR: 41.7) (61) 259001 (SF2 FWS) Feedwater 268000 (SF9 RW) Radwaste 271000 (SF9 OG) Offgas 272000 (SF7, SF9 RMS) Radiation K3.05 - Knowledge of the effect that a loss or 05 malfunction of the RADIATION 3.5 1 Monitoring MONITORING SYSTEM will have on the (62) following: Offgas system (CFR: 41.5 / 45.3) 286000 (SF8 FPS) Fire Protection 288000 (SF9 PVS) Plant Ventilation 290001 (SF5 SC) Secondary K4.01 - Knowledge of SECONDARY 01 CONTAINMENT design feature(s) and/or 3.5 1 Containment interlocks which provide for the following: (63)
Personnel access without breaching secondary containment: Plant specific (CFR: 41.7) 290003 (SF9 CRV) Control Room K5.01 - Knowledge of the operational 01 implications of the following concepts as they 3.2 1 Ventilation apply to CONTROL ROOM HVAC: Airborne (64) contamination (e.g. radiological, toxic gas, smoke) control (CFR: 41.5 / 45.3) 290002 (SF4 RVI) Reactor Vessel K6.17 - Knowledge of the effect that a loss or 17 malfunction of the following will have on the 2.5 1 Internals REACTOR VESSEL INTERNALS: TIP (65)
(CFR: 41.7 / 45.7) 51001 (SF8 CWS*) Circulating Water K/A Category Point Totals: 1 1 1 2 1 1 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 #
295001 (APE 1) Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 295003 (APE 3) Partial or Complete Loss of AC Power / 6 295004 (APE 4) Partial or Total Loss of DC Power / 6 295005 (APE 5) Main Turbine Generator Trip /
3 AA2.02 - Ability to determine and/or 295006 (APE 6) Scram / 1 02 interpret the following as they apply to 4.4* 1 SCRAM: Control rod position (76)
(CFR: 41.10 / 43.5 / 45.13)
G2.4.34 - Knowledge of RO tasks 295016 (APE 16) Control Room Abandonment 04. performed outside the main control room 4.1 1
/7 34 during an emergency and the resultant (77) operational effects.
(CFR: 41.10 / 43.5 / 45.13) 295018 (APE 18) Partial or Complete Loss of CCW / 8 295019 (APE 19) Partial or Complete Loss of Instrument Air / 8 AA2.01 - Ability to determine and/or 295021 (APE 21) Loss of Shutdown Cooling / 01 interpret the following as they apply to 3.6 1 4 LOSS OF SHUTDOWN COOLING: Reactor water heatup/cooldown rate (78)
(CFR: 41.10 / 43.5 / 45.13) 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 G2.1.20 - Ability to interpret and execute 295028 (EPE 5) High Drywell Temperature 01. procedure steps. 4.6 1 (Mark I and Mark II only) / 5 20 (CFR: 41.10 / 43.5 / 45.12)
(79) 295030 (EPE 7) Low Suppression Pool Water Level / 5 EA2.04 - Ability to determine and/or 295031 (EPE 8) Reactor Low Water Level / 2 04 interpret the following as they apply to 4.8* 1 REACTOR LOW WATER LEVEL: Adequate (80) core cooling (CFR: 41.10 / 43.5 / 45.13)
G2.4.6 - Knowledge of EOP mitigation 295037 (EPE 14) Scram Condition Present 04. strategies. 4.7 1 and Reactor Power Above APRM Downscale 06 (CFR: 41.10 / 43.5 / 45.13)
(81) or Unknown / 1 295038 (EPE 15) High Offsite Radioactivity Release Rate / 9
ES-401 12 Form ES-401-1 AA2.13 - Ability to determine and interpret 600000 (APE 24) Plant Fire On Site / 8 13 the following as they apply to PLANT FIRE 3.8 1 ON SITE: Need for emergency plant (82) shutdown (CFR: 41.10 / 43.5 / 45.13) 700000 (APE 25) Generator Voltage and Electric Grid Disturbances / 6 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 G2.1.32 - Ability to explain and apply 295010 (APE 10) High Drywell Pressure / 5 01. system limits and precautions. 4.0 1 32 (CFR: 41.10 / 43.2 / 45.12) (83) 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 AA2.02 - Ability to determine and interpret 295022 (APE 22) Loss of Control Rod Drive 02 the following as they apply to LOSS OF 3.4 1 Pumps / 1 CRD PUMPS: CRD system status (CFR: 41.10 / 43.5 / 45.13) (84) 295029 (EPE 6) High Suppression Pool Water Level / 5 295032 (EPE 9) High Secondary Containment Area Temperature / 5 295033 (EPE 10) High Secondary Containment Area Radiation Levels / 9 295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9 295035 (EPE 12) Secondary Containment High Differential Pressure / 5 295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5 G2.4.21 - Knowledge of the parameters 500000 (EPE 16) High Containment Hydrogen 04. and logic used to assess the status of 4.6 1 Concentration / 5 21 safety functions, such as reactivity control, core cooling and heat removal, reactor (85) coolant system integrity, containment conditions, radioactivity release control, etc.
(CFR: 41.7 / 43.5 / 45.12)
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) 07 A2.07 - Ability to (a) predict the impacts of 3.1 1 RHR/LPCI: Injection Mode the following on the RHR/LPCI: INJECTION (86)
MODE; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations: Pump seal failure (CFR: 41.5 / 43.5 / 45.6) 205000 (SF4 SCS) Shutdown Cooling 206000 (SF2, SF4 HPCIS) 02 G2.2.25 - Knowledge of the bases in 4.2 1 High-Pressure Coolant Injection 25 Technical Specifications for limiting conditions (87) for operations and safety limits.
(CFR: 41.5 / 41.7 / 43.2) 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 08 A2.08 - Ability to (a) predict the impacts of 4.2* 1 Control the following on the STANDBY LIQUID (88)
CONTROL SYSTEM; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Failure to Scram (CFR: 41.5 / 43.5 / 45.6) 212000 (SF7 RPS) Reactor Protection 215003 (SF7 IRM)
Intermediate-Range Monitor 215004 (SF7 SRMS) Source-Range Monitor 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling 218000 (SF3 ADS) Automatic 02 G2.2.36 - Ability to analyze the effect of 4.2 1 Depressurization 36 maintenance activities, such as degraded (89) power sources, on the status of limiting conditions for operations.
(CFR: 41.10 / 43.2 / 45.13) 223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff 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
ES-401 15 Form ES-401-1 262002 (SF6 UPS) Uninterruptable 01 A2.01 - Ability to (a) predict the impacts of 2.8 1 Power Supply (AC/DC) the following on the UNINTERRUPTABLE (90)
POWER SUPPLY (AC/DC); and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Under voltage (CFR: 41.5 / 43.5 / 45.6) 263000 (SF6 DC) DC Electrical Distribution 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 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 G2.4.9 - Knowledge of low power/shutdown 04 implications in accident (e.g., loss of coolant 4.2 1 Flow Control 09 accident or loss of residual heat removal)
(91) mitigation strategies.
(CFR: 41.10 / 43.5 / 45.13) 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 A2.03 - Ability to (a) predict the impacts of 03 the following on the NUCLEAR BOILER 3.1 1 Instrumentation INSTRUMENTATION; and (b) based on (92) those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal conditions or operations:
Instrument line leakage (CFR: 41.5 / 43.5 / 45.6) 219000 (SF5 RHR SPC) RHR/LPCI: G2.4.20 - Knowledge of the operational 04 implications of EOP warnings, cautions, and 4.3 1 Torus/Suppression Pool Cooling Mode 20 notes.
(93)
(CFR: 41.10 / 43.5/ 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 239003 (SF9 MSVLCS) Main Steam Isolation Valve Leakage Control 241000 (SF3 RTPRS)
Reactor/Turbine Pressure Regulating
ES-401 17 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 51001 (SF8 CWS*) Circulating Water K/A Category Point Totals: 1 2 Group Point Total: 3
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Dresden Nuclear Power Station, Units 2 and 3 Date of Exam: April 19 - 30, 2021 Category K/A # Topic RO SRO-only IR # IR #
Knowledge of conduct of operations requirements.
2.1.1 3.8 1 (CFR: 41.10 / 45.13)
(66)
Knowledge of administrative requirements for temporary 2.1.15 2.7 1 management directives, such as standing orders, night orders, operations memos, etc. (67)
- 1. Conduct of (CFR: 41.10 / 45.12)
Operations Knowledge of facility requirements for controlling 2.1.13 3.2 1 vital/controlled access.
(CFR: 41.10 / 43.5 / 45.9 / 45.10) (94)
Knowledge of procedures, guidelines, or limitations 2.1.37 4.6 1 associated with reactivity management.
(CFR: 41.1 / 43.6 / 45.6) (95)
Subtotal 2 2 Knowledge of the process for making changes to 2.2.6 3.0 1 procedures.
(CFR: 41.10 / 43.3 / 45.13) (68)
Knowledge of tagging and clearance procedures.
2.2.13 4.1 1 (CFR: 41.10 / 45.13)
(69)
Knowledge of the process used to track inoperable 2.2.43 3.0 1
- 2. Equipment alarms.
Control (CFR: 41.10 / 43.5 / 45.13) (70)
Knowledge of the process for making design or 2.2.5 3.2 1 operating changes to the facility.
(CFR: 41.10 / 43.3 / 45.13) (96)
Knowledge of pre- and post-maintenance operability 2.2.21 4.1 1 requirements.
(CFR: 41.10 / 43.2) (97)
Subtotal 3 2 Ability to use radiation monitoring systems, such as 2.3.5 2.9 1 fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (71)
(CFR: 41.11 / 41.12 / 43.4 / 45.9)
Ability to comply with radiation work permit requirements 2.3.7 3.5 1 during normal or abnormal conditions.
(CFR: 41.12 / 45.10) (72)
- 3. Radiation Knowledge of radiation or contamination hazards that 2.3.14 3.4 1 Control may arise during normal, abnormal, or emergency conditions or activities. (73)
(CFR: 41.12 / 43.4 / 45.10)
Knowledge of radiation monitoring systems, such as 2.3.15 3.1 1 fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (98)
(CFR: 41.12 / 43.4 / 45.9)
Subtotal 3 1
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Knowledge of general operating crew responsibilities 2.4.12 4.0 1 during emergency operations.
(CFR: 41.10 / 45.12) (74)
Knowledge of facility protection requirements, including 2.4.26 3.1 1 fire brigade and portable fire fighting equipment usage.
(CFR: 41.10 / 43.5 / 45.12) (75)
- 4. Emergency Knowledge of EOP implementation hierarchy and 2.4.16 4.4 1 Procedures / coordination with other support procedures or guidelines Plan such as, operating procedures, abnormal operating (99) procedures, and severe accident management guidelines.
(CFR: 41.10 / 43.5 / 45.13)
Knowledge of events related to system operation/status 2.4.30 4.1 1 that must be reported to internal organizations or external agencies, such as the State, the NRC, or the (100) transmission system operator.
(CFR: 41.10 / 43.5 / 45.11)
Subtotal 2 2 Tier 3 Point Total 10 7
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility Name:Dresden Date of Exam:4/19/21 RO SRO-Only Category K/A # Topic Q# IR # IR #
35 2.1. 01 Knowledge of conduct of operations requirements. 3.8 1 4.2 Knowledge of administrative requirements for temporary management directives, such as 10 2.1. 15 standing orders, night orders, operations memos, etc. 2.7 1 3.4
- 1. 2.1.
Conduct of 2.1.
86 Operations 2.1. 13 Knowledge of facility requirements for controlling vital/controlled access. 2.5 3.2 1 Knowledge of procedures, guidelines, or limitations associated with reactivity 91 2.1. 37 management. 4.3 4.6 1 Subtotal 2 2 31 2.2. 06 Knowledge of the process for making changes to procedures. 3.0 1 3.6 24 2.2. 13 Knowledge of tagging and clearance procedures. 4.1 1 4.3 63 2. 2.2. 43 Knowledge of the process used to track inoperable alarms. 3.0 1 3.3 Equipment 2.2.
76 Control 2.2. 05 Knowledge of the process for making design or operating changes to the facility. 2.2 3.2 1 92 2.2. 21 Knowledge of pre- and post-maintenance operability requirements. 2.9 4.1 1 Subtotal 3 2 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, 64 2.3. 05 portable survey instruments, personnel monitoring equipment, etc. 2.9 1 2.9 Ability to comply with radiation work permit requirements during normal or abnormal 32 2.3. 07 conditions. 3.5 1 3.6 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, 9 3. 2.3. 14 or emergency conditions or activities. 3.4 1 3.8 Radiation 2.3.
Control 2.3.
Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, 85 2.3. 15 portable survey instruments, personnel monitoring equipment, etc. 2.9 3.1 1 Subtotal 3 1 61 2.4. 12 Knowledge of general operating crew responsibilities during emergency operations. 4.0 1 4.3 Knowledge of facility protection requirements, including fire brigade and portable fire 62 2.4. 26 fighting equipment usage. 3.1 1 3.6
- 4. 2.4.
Emergency 2.4.
Knowledge of EOP implementation hierarchy and coordination with other support 94 Procedures 2.4. 16 procedures or guidelines such as, operating procedures, abnormal operating procedures, 3.5 4.4 1
/ Plan and severe accident management guidelines.
Knowledge of events related to system operation/status that must be reported to internal 83 2.4. 30 organizations or external agencies, such as the State, the NRC, or the transmission 2.7 4.1 1 system operator.
Subtotal 2 2 Tier 3 Point Total 10 7 ES-401, Page 43 of 50