ML22199A270
| ML22199A270 | |
| Person / Time | |
|---|---|
| Site: | Braidwood  |
| Issue date: | 02/22/2022 |
| From: | Randy Baker NRC/RGN-III/DRS/OLB |
| To: | Exelon Generation Co LLC, Exelon Generation Co |
| Baker R | |
| Shared Package | |
| ML20140A264 | List: |
| References | |
| Download: ML22199A270 (14) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: Braidwood Station, Units 1 and 2 Date of Exam: March 2022 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.
Emergency and Abnormal Plant Evolutions 1
3 2
3 3
4 3
18 3
3 6
2 2
2 2
1 1
1 9
2 2
4 Tier Totals 5
4 5
4 5
4 27 5
5 10
- 2.
Plant Systems 1
3 2
3 3
2 3
3 3
2 2
2 28 2
3 5
2 0
1 1
1 1
1 1
1 1
1 1
10 0
2 1
3 Tier Totals 3
3 4
4 3
4 4
4 3
3 3
38 4
4 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
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 shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 6.
Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.
- 7.
The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.
- 8.
On the following pages, enter the K/A numbers, a brief description of each topic, the topics 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-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 000007 (EPE 7; BW E02&E10; CE E02)
Reactor Trip, Stabilization, Recovery / 1 X
(000007EK2.03) Knowledge of the interrelations between (EPE 7) REACTOR TRIP, STABILIZATION, RECOVERY / 1 and the following (CFR: 41.7 / 45.7): Reactor trip status panel 3.5 1
000008 (APE 8) Pressurizer Vapor Space Accident / 3 X
(000008AA2.05) Ability to determine and interpret the following as they apply to the (APE 8)
PRESSURIZER VAPOR SPACE ACCIDENT / 3 (CFR: 43.5 / 45.13): PORV isolation (block)valve switches and indicators 3.9 2
000009 (EPE 9) Small Break LOCA / 3 X (000009 (EPE 9) Small Break LOCA / 3) (G2.4.30)
Knowledge of events related to system operation/
status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10 / 43.5 / 45.11) 4.1 76 000011 (EPE 11) Large Break LOCA / 3 X (000011 (EPE 11) Large Break LOCA / 3) (G2.4.2)
Knowledge of system set points, interlocks and automatic actions associated with EOP entry conditions. (CFR: 41.7 / 45.7 / 45.8) 4.5 3
000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 X (000015 (APE 15) Reactor Coolant Pump Malfunctions / 4) (G2.1.20) Ability to interpret and execute procedure steps. (CFR: 41.10 / 43.5 /
45.12) 4.6 4
000022 (APE 22) Loss of Reactor Coolant Makeup / 2 X
(000022AK1.01) Knowledge of the operational implications of the following concepts as they apply to (APE 22) LOSS OF REACTOR COOLANT MAKEUP / 2 (CFR 41.8 / 41.10 / 45.3):
Consequences of thermal shock to RCP seals 2.8 5
000025 (APE 25) Loss of Residual Heat Removal System / 4 X
(000025AA2.03) Ability to determine and interpret the following as they apply to the (APE 25) LOSS OF RESIDUAL HEAT REMOVAL SYSTEM / 4 (CFR: 43.5 / 45.13): Increasing reactor building sump level 3.6 6
000025 (APE 25) Loss of Residual Heat Removal System / 4 X (000025 (APE 25) Loss of Residual Heat Removal System / 4) (G2.4.20) Knowledge of the operational implications of EOP warnings, cautions, and notes.
(CFR: 41.10 / 43.5 / 45.13) 4.3 77 000026 (APE 26) Loss of Component Cooling Water / 8 X
(000026AA2.04) Ability to determine and interpret the following as they apply to the (APE 26) LOSS OF COMPONENT COOLING WATER / 8 (CFR:
43.5 / 45.13): The normal values and upper limits for the temperatures of the components cooled by CCW 2.9 78 000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 X
(000027AK3.02) Knowledge of the reasons for the following responses as they apply to the (APE 27)
PRESSURIZER PRESSURE CONTROL SYSTEM MALFUNCTION / 3 (CFR 41.5,41.10 / 45.6 / 45.13):
Verification of alternate transmitter and/or plant computer prior to shifting flow chart transmitters 2.9 7
000029 (EPE 29) Anticipated Transient Without Scram / 1 X
(000029EA2.08) Ability to determine and interpret the following as they apply to (EPE 29)
ANTICIPATED TRANSIENT WITHOUT SCRAM / 1 (CFR: 43.5 / 45.13): Rod bank step counters and RPI 3.4 8
ES-401 3
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 000038 (EPE 38) Steam Generator Tube Rupture / 3 X (000038 (EPE 38) Steam Generator Tube Rupture /
- 3) (G2.4.8) Knowledge of how abnormal operating procedures are used in conjunction with EOPs.
(CFR: 41.10 / 43.5 / 45.13) 3.8 9
000040 (APE 40; BW E05; CE E05; W E12)
Steam Line RuptureExcessive Heat Transfer / 4 X
(000040AA1.16) Ability to operate and / or monitor the following as they apply to the (APE 40) STEAM LINE RUPTURE - EXCESSIVE HEAT TRANSFER /
4 (CFR 41.7 / 45.5 / 45.6): Reactor coolant loop delta temperature gauges 3.4 10 000054 (APE 54; CE E06) Loss of Main Feedwater /4 X (000054 (APE 54; CE E06) Loss of Main Feedwater
/4) (G2.4.45) Ability to prioritize and interpret the significance of each annunciator or alarm. (CFR:
41.10 / 43.5 / 45.3 / 45.13) 4.3 79 000055 (EPE 55) Station Blackout / 6 X
(000055EK3.02) Knowledge of the reasons for the following responses as they apply to (EPE 55)
STATION BLACKOUT / 6 (CFR: 41.5 / 41.10 / 45.6
/ 45.13): Actions contained in EOP for loss of offsite and onsite power 4.3 11 000056 (APE 56) Loss of Offsite Power / 6 X
(000056AA2.45) Ability to determine and interpret the following as they apply to the (APE 56) LOSS OF OFFSITE POWER / 6 (CFR: 43.5 / 45.13):
Indicators to assess status of ESF breakers (tripped/ not-tripped)and validity of alarms (false/not-false) 3.6 12 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 X
(000057AA2.20) Ability to determine and interpret the following as they apply to the (APE 57) LOSS OF VITAL AC INSTRUMENT BUS / 6 (CFR: 43.5 /
45.13): Interlocks in effect on loss of ac vital electrical instrument bus that must be bypassed to restore normal equipment operation 3.9 80 000058 (APE 58) Loss of DC Power / 6 X
(000058AA1.01) Ability to operate and / or monitor the following as they apply to the (APE 58) LOSS OF DC POWER / 6 (CFR 41.7 / 45.5 / 45.6): Cross-tie of the affected dc bus with the alternate supply 3.4 13 000062 (APE 62) Loss of Nuclear Service Water / 4 X
(000062AA1.05) Ability to operate and / or monitor the following as they apply to the (APE 62) LOSS OF NUCLEAR SERVICE WATER / 4 (CFR 41.7 /
45.5 / 45.6): The CCWS surge tank, including level control and level alarms, and radiation alarm 3.1 14 000065 (APE 65) Loss of Instrument Air / 8 X
(000065AK3.03) Knowledge of the reasons for the following responses as they apply to the (APE 65)
LOSS OF INSTRUMENT AIR / 8 (CFR 41.5,41.10 /
45.6 / 45.13): Knowing effects on plant operation of isolating certain equipment from instrument air 2.9 15 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 X
(000077AA2.07) Ability to determine and interpret the following as they apply to the (APE 77)
GENERATOR VOLTAGE AND ELECTRIC GRID DISTURBANCES / 6 (CFR: 43.5 / 45.13):
Operational status of engineered safety features.
4.0 81 (W E04) LOCA Outside Containment / 3 X
(WE04EK1.3) Knowledge of the operational implications of the following concepts as they apply to (W E04) LOCA OUTSIDE CONTAINMENT / 3 (CFR: 41.8 / 41.10 / 45.3): Annunciators and conditions indicating signals, and remedial actions associated with the (LOCA Outside Containment).
3.5 16
ES-401 4
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR (W E11) Loss of Emergency Coolant Recirculation / 4 X
(WE11EK1.3) Knowledge of the operational implications of the following concepts as they apply to (W E11) LOSS OF EMERGENCY COOLANT RECIRCULATION / 4 (CFR: 41.8 / 41.10 / 45.3):
Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Emergency Coolant Recirculation).
3.6 17 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 X
(WE05EK2.2) Knowledge of the interrelations between (W E05) LOSS OF SECONDARY HEAT SINK / 4 and the following (CFR: 41.7 / 45.7):
Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.
3.9 18 K/A Category Totals:
3 2
3 3
7 6
Group Point Total: (RO/SRO) 18/6
ES-401 5
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 000001 (APE 1) Continuous Rod Withdrawal / 1 X
(000001AK2.08) Knowledge of the interrelations between the (APE 1) CONTINUOUS ROD WITHDRAWAL / 1 and the following (CFR 41.7 / 45.7):
Individual rod display lights and indications 3.1 19 000003 (APE 3) Dropped Control Rod / 1 000005 (APE 5) Inoperable/Stuck Control Rod / 1 X
(000005AA2.03) Ability to determine and interpret the following as they apply to the (APE 5) INOPERABLE/STUCK CONTROL ROD / 1 (CFR: 43.5 /
45.13): Required actions if more than one rod is stuck or inoperable 3.5 20 000024 (APE 24) Emergency Boration / 1 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 000032 (APE 32) Loss of Source Range Nuclear Instrumentation / 7 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 X
(000033AK3.02) Knowledge of the reasons for the following responses as they apply to the Loss of Intermediate Range Nuclear Instrumentation (CFR 41.5,41.10 / 45.6 / 45.13):
Guidance contained in EOP for loss of intermediate range instrumentation 3.6 21 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 X
(000036AK2.02 Knowledge of the interrelations between the (APE 36) FUEL-HANDLING INCIDENTS / 8) and the following (CFR: 41.7 / 45.7): Radiation monitoring equipment (portable and installed) 3.4 22 000037 (APE 37) Steam Generator Tube Leak / 3 X
(000037AA2.16) Ability to determine and interpret the following as they apply to the (APE 37) STEAM GENERATOR TUBE LEAK / 3 (CFR: 43.5 /
45.13): Pressure at which to maintain RCS during S/G cooldown 4.3 82 000051 (APE 51) Loss of Condenser Vacuum / 4 000059 (APE 59) Accidental Liquid Radwaste Release / 9 X
(000059AA2.02) Ability to determine and interpret the following as they apply to the (APE 59) ACCIDENTAL LIQUID RADWASTE RELEASE / 9 (CFR:
43.5 / 45.13): The permit for liquid radioactive-waste release 3.9 83 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 X
(000060AA1.02) Ability to operate and / or monitor the following as they apply to the (APE 60)
ACCIDENTAL GASEOUS RADWASTE RELEASE / 9 (CFR 41.7 / 45.5 / 45.6): Ventilation system 2.9 23
ES-401 6
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR 000061 (APE 61) Area Radiation Monitoring System Alarms
/ 7 000067 (APE 67) Plant Fire On Site / 8 X
(000067AK1.02) Knowledge of the operational implications of the following concepts as they apply to (APE 67) PLANT FIRE ON SITE / 8 (CFR 41.8 / 41.10 /
45.3): Fire fighting 3.1 24 000068 (APE 68; BW A06) Control Room Evacuation / 8 000069 (APE 69; W E14) Loss of Containment Integrity / 5 X (000069 (APE 69; W E14) Loss of Containment Integrity / 5)
(G2.2.39) Knowledge of less than or equal to one hour Technical Specification action statements for systems. (CFR: 41.7 / 41.10 /
43.2 / 45.13) 3.9 25 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling /
4 000076 (APE 76) High Reactor Coolant Activity / 9 X
(000076AK3.05) Knowledge of the reasons for the following responses as they apply to the (APE 76) HIGH REACTOR COOLANT ACTIVITY / 9 (CFR 41.5,41.10 / 45.6 / 45.13):
Corrective actions as a result of high fission-product radioactivity level in the RCS 2.9 26 000078 (APE 78*) RCS Leak / 3 (W E01 & E02) Rediagnosis & SI Termination / 3 X ((W E01 & E02) Rediagnosis & SI Termination / 3) (G2.4.9)
Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.
(G2.4.47) Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
(CFR: 41.10 / 43.5 / 45.12) 4.2 84 (W E13) Steam Generator Overpressure / 4 (W E15) Containment Flooding / 5 (W E16) High Containment Radiation /9 (BW A01) Plant Runback / 1 (BW A02 & A03) Loss of NNI-X/Y/7 (BW A04) Turbine Trip / 4 (BW A05) Emergency Diesel Actuation / 6 (BW A07) Flooding / 8 (BW E03) Inadequate Subcooling Margin / 4 (BW E08; W E03) LOCA CooldownDepressurization / 4 X ((W E03) LOCA Cooldown Depressurization / 4) (G2.2.3)
(multi-unit license) Knowledge of the design, procedural, and operational differences between units. (CFR: 41.5 / 41.6 / 41.7 /
41.10 / 45.12) 3.9 85 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4
ES-401 7
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)
E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G*
K/A Topic(s)
IR (BW E13 & E14) EOP Rules and Enclosures (CE A11**; W E08) RCS OvercoolingPressurized Thermal Shock / 4 X
(WE08EK1.2) Knowledge of the operational implications of the following concepts as they apply to (W E08) PRESSURIZED THERMAL SHOCK / 4 (CFR:
41.8 / 41.10 / 45.3): Normal, abnormal and emergency operating procedures associated with (Pressurized Thermal Shock).
3.4 27 (CE A16) Excess RCS Leakage / 2 (CE E09) Functional Recovery (CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 K/A Category Point Totals:
2 2
2 1
3 3
Group Point Total: (RO/SRO) 9/4
ES-401 8
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 003 (SF4P RCP) Reactor Coolant Pump X
(003K5.04) Knowledge of the operational implications of the following concepts as they apply to the (SF4P RCP) REACTOR COOLANT PUMP SYSTEM (CFR: 41.5 /
45.7): Effects of RCP shutdown on secondary parameters, such as steam pressure, steam flow, and feed flow 3.2 28 004 (SF1; SF2 CVCS) Chemical and Volume Control X
(004K5.04) Knowledge of the operational implications of the following concepts as they apply to the (SF1; SF2 CVCS) CHEMICAL AND VOLUME CONTROL SYSTEM (CFR:
41.5 / 45.7): Reason for hydrogen cover gas in VCT (oxygen scavenge) 2.8 29 005 (SF4P RHR) Residual Heat Removal X
(005K2.01) (SF4P RHR) RESIDUAL HEAT REMOVAL SYSTEM Knowledge of electrical power supplies to the following (CFR: 41.7):
RHR pumps 3.0 30 005 (SF4P RHR) Residual Heat Removal System X
(005K6.03) Knowledge of the of the effect of a loss or malfunction on the following will have on the (SF4P RHR) RESIDUAL HEAT REMOVAL SYSTEM (CFR: 41.7 / 45.7): RHR heat exchanger 2.5 31 006 (SF2; SF3 ECCS) Emergency Core Cooling X
(006A1.07) Ability to predict and/or monitor changes in parameters associated with operating the (SF2; SF3 ECCS) EMERGENCY CORE COOLING SYSTEM controls including (CFR: 41.5 / 45.5): Pressure, high and low 3.3 32 006 (SF2; SF3 ECCS) Emergency Core Cooling X
(006A3.05) Ability to monitor automatic operations of the (SF2; SF3 ECCS)
EMERGENCY CORE COOLING SYSTEM including (CFR: 41.7 / 45.5): Safety Injection pumps 3.4 33 007 (SF5 PRTS) Pressurizer Relief/Quench Tank X
(007K1.01) Knowledge of the physical connections and/or cause-effect relationships between (SF5 PRTS) PRESSURIZER RELIEF/QUENCH TANK SYSTEM and the following (CFR: 41.2 to 41.9 / 45.7 to 45.8):
Containment system 2.9 34 008 (SF8 CCW) Component Cooling Water X
(008K4.09) Knowledge of (SF8 CCW)
COMPONENT COOLING WATER SYSTEM design feature(s) and or interlock(s) which provide for the following (CFR: 41.7): The standby feature for the CCW pumps 2.7 35 008 (SF8 CCW) Component Cooling Water X
(008A2.05) Ability to (a) predict the impacts of the following on the (SF8 CCW) COMPONENT COOLING WATER SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR: 41.5 / 43.5 / 45.3 /
45.13): Effect of loss of instrument and control air on the position of the CCW valves that are air operated 3.3 86 010 (SF3 PZR PCS) Pressurizer Pressure Control X
(010A1.08) Ability to predict and/or monitor changes in parameters associated with operating the (SF3 PZR PCS) PRESSURIZER PRESSURE CONTROL SYSTEM controls including (CFR: 41.5 / 45.5): Spray nozzle DT 3.2 36
ES-401 9
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 010 (SF3 PZR PCS) Pressurizer Pressure Control X
(010K4.03) Knowledge of (SF3 PZR PCS)
PRESSURIZER PRESSURE CONTROL SYSTEM design feature(s) and or interlock(s) which provide for the following (CFR: 41.7):
Over pressure control 3.8 37 012 (SF7 RPS) Reactor Protection X
(012A3.02) Ability to monitor automatic operations of the (SF7 RPS) REACTOR PROTECTION SYSTEM including (CFR: 41.7
/ 45.5): Bistables 3.6 38 013 (SF2 ESFAS) Engineered Safety Features Actuation X
(013A4.03) (SF2 ESFAS) ENGINEERED SAFETY FEATURES ACTUATION SYSTEM Ability to manually operate and/or monitor in the control room (CFR: 41.7 / 45.5 to 45.8):
ESFAS initiation 4.5 39 022 (SF5 CCS) Containment Cooling X
(022A2.03) Ability to (a) predict the impacts of the following on the (SF5 CCS)
CONTAINMENT COOLING SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR: 41.5 /43.5/
45.3/45.13): Fan motor thermal overload/high-speed operation 2.6 40 025 (SF5 ICE) Ice Condenser 026 (SF5 CSS) Containment Spray X
(026A2.05) Ability to (a) predict the impacts of the following on the (SF5 CSS)
CONTAINMENT SPRAY SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR: 41.5 / 43.5
/ 45.3 / 45.13): Failure of chemical addition tanks to inject 3.7 41 026 (SF5 CSS) Containment Spray X
(026K2.02) (SF5 CSS) CONTAINMENT SPRAY SYSTEM Knowledge of electrical power supplies to the following (CFR: 41.7):
MOVs 2.7 42 039 (SF4S MSS) Main and Reheat Steam X (039 (SF4S MSS) MAIN AND REHEAT STEAM SYSTEM) (G2.1.30) Ability to locate and operate components, including local controls. (CFR: 41.7 / 45.7) 4.4 43 039 (SF4S MSS) Main and Reheat Steam X (039 (SF4S MSS) MAIN AND REHEAT STEAM SYSTEM) (G2.1.32) Ability to explain and apply system limits and precautions.
(CFR: 41.10 / 43.2 / 45.12) 3.8 87 059 (SF4S MFW) Main Feedwater X
(059A1.03) Ability to predict and/or monitor changes in parameters associated with operating the (SF4S MFW) MAIN FEEDWATER SYSTEM controls including (CFR: 41.5 / 45.5):Power level restrictions for operation of MFW pumps and valves 2.7 44 061 (SF4S AFW)
Auxiliary/Emergency Feedwater X
(061K6.01) Knowledge of the of the effect of a loss or malfunction on the following will have on the (SF4S AFW) AUXILIARY /
EMERGENCY FEEDWATER SYSTEM (CFR:
41.7 / 45.7): Controllers and positioners 2.5 45
ES-401 10 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 061 (SF4S AFW)
Auxiliary/Emergency Feedwater X
(061A2.04) Ability to (a) predict the impacts of the following on the (SF4S AFW) AUXILIARY /
EMERGENCY FEEDWATER SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR: 41.5 / 43.5
/ 45.3 / 45.13): pump failure or improper operation 3.8 88 062 (SF6 ED AC) AC Electrical Distribution X
(062K3.03) Knowledge of the effect that a loss or malfunction of the (SF6 ED AC) AC ELECTRICAL DISTRIBUTION SYSTEM will have on the following (CFR: 41.7 / 45.6): DC system 3.7 46 062 (SF6 ED AC) AC Electrical Distribution X (062 (SF6 ED AC) AC ELECTRICAL DISTRIBUTION SYSTEM) (G2.4.46) Ability to verify that the alarms are consistent with the plant conditions. (CFR: 41.10 / 43.5 / 45.3 /
45.12) 4.2 89 063 (SF6 ED DC) DC Electrical Distribution X
(063K3.02) Knowledge of the effect that a loss or malfunction of the (SF6 ED DC) DC ELECTRICAL DISTRIBUTION SYSTEM will have on the following (CFR: 41.7 / 45.6): ED/G 3.7 47 064 (SF6 EDG) Emergency Diesel Generator X
(064K4.01) Knowledge of (SF6 EDG)
EMERGENCY DIESEL GENERATOR SYSTEM design feature(s) and or interlock(s) which provide for the following (CFR: 41.7):
Trips while loading the ED/G (frequency, voltage, speed) 3.8 48 064 (SF6 EDG) Emergency Diesel Generator X
(064K6.08) Knowledge of the of the effect of a loss or malfunction on the following will have on the (SF6 EDG) EMERGENCY DIESEL GENERATOR SYSTEM (CFR: 41.7 / 45.7):
Fuel oil storage tanks 3.2 49 073 (SF7 PRM) Process Radiation Monitoring X
(073K1.01) Knowledge of the physical connections and/or cause-effect relationships between (SF7 PRM) PROCESS RADIATION MONITORING SYSTEM and the following (CFR: 41.2 to 41.9 / 45.7 to 45.8): Those systems served by PRMs 3.6 50 076 (SF4S SW) Service Water X
(076K1.05) Knowledge of the physical connections and/or cause-effect relationships between (SF4S SW) SERVICE WATER SYSTEM and the following (CFR: 41.2 to 41.9
/ 45.7 to 45.8):D/G 3.8 51 076 (SF4S SW) Service Water X (076 (SF4S SW) SERVICE WATER SYSTEM)
(G2.4.18) Knowledge of the specific bases for EOPs. (CFR: 41.10 / 43.1 / 45.13) 4.0 90 078 (SF8 IAS) Instrument Air X (078 (SF8 IAS) INSTRUMENT AIR SYSTEM)
(G2.4.31) Knowledge of annunciator alarms, indications, or response procedures. (CFR:
41.10 / 45.3) 4.2 52 078 (SF8 IAS) Instrument Air X
(078K3.01) Knowledge of the effect that a loss or malfunction of the (SF8 IAS) INSTRUMENT AIR SYSTEM will have on the following (CFR:
41.7 / 45.6): Containment air system 3.1 53
ES-401 11 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO/SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 103 (SF5 CNT) Containment X
(103A2.03) Ability to (a) predict the impacts of the following on the (SF5 CNT)
CONTAINMENT SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR: 41.5 /43.5/
45.3/45.13): Phase A and B isolation 3.5 54 103 (SF5 CNT) Containment X
(103A4.01) (SF5 CNT) CONTAINMENT Ability to manually operate and/or monitor in the control room: (CFR: 41.7 / 45.5 to 45.8) Flow control, pressure control, and temperature control valves, including pneumatic valve controller 3.2 55 053 (SF1; SF4P ICS*) Integrated Control K/A Category Point Totals:
3 2
3 3
2 3
3 5
2 2
5 Group Point Total: (RO/SRO) 28/5
ES-401 12 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO/SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 001 (SF1 CRDS) Control Rod Drive 002 (SF2; SF4P RCS) Reactor Coolant X
(002K3.03) Knowledge of the effect that a loss or malfunction of the (SF2; SF4P RCS)
REACTOR COOLANT SYSTEM will have on the following (CFR: 41.7 / 45.6): Containment 4.2 56 014 (SF1 RPI) Rod Position Indication X
(014A2.05) Ability to (a) predict the impacts of the following on the (SF1 RPI) ROD POSITION INDICATION SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR: 41.5 /43.5/
45.3/45.13): Reactor trip 4.1 91 015 (SF7 NI) Nuclear Instrumentation X
(015K2.01) (SF7 NI) NUCLEAR INSTRUMENTATION SYSTEM Knowledge of electrical power supplies to the following (CFR:
41.7): NIS channels, components, and interconnections 3.3 57 016 (SF7 NNI) Nonnuclear Instrumentation 017 (SF7 ITM) In-Core Temperature Monitor X (017 (SF7 ITM) IN CORE TEMPERATURE MONITOR SYSTEM) (G2.4.1) Knowledge of EOP entry conditions and immediate action steps. (CFR: 41.10 / 43.5 / 45.13) 4.6 58 027 (SF5 CIRS) Containment Iodine Removal 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control 029 (SF8 CPS) Containment Purge X
(029A2.01) Ability to (a) predict the impacts of the following on the (SF8 CPS)
CONTAINMENT PURGE SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR: 41.5 / 43.5
/ 45.3 / 45.13): Maintenance or other activity taking place inside containment 3.6 92 033 (SF8 SFPCS) Spent Fuel Pool Cooling 034 (SF8 FHS) Fuel-Handling Equipment X
(034A2.02) Ability to (a) predict the impacts of the following on the (SF8 FHS) FUEL HANDLING EQUIPMENT SYSTEM and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those abnormal operation (CFR: 41.5 / 43.5
/ 45.3 / 45.13): Dropped cask 3.4 59 035 (SF 4P SG) Steam Generator X
(035K6.01) Knowledge of the of the effect of a loss or malfunction on the following will have on the (SF4P SG) STEAM GENERATOR SYSTEM (CFR: 41.7 / 45.7): MSIVs 3.2 60 041 (SF4S SDS) Steam Dump/Turbine Bypass Control X
(041A1.01) Ability to predict and/or monitor changes in parameters associated with operating the (SF4S SDS) STEAM DUMP/TURBINE BYPASS CONTROL SYSTEM controls including (CFR: 41.5 / 45.5):
T-ave., verification above low/low setpoint 2.9 61 045 (SF 4S MTG) Main Turbine Generator X
(045A3.07) Ability to monitor automatic operations of the (SF4S MTG) MAIN TURBINE GENERATOR SYSTEM, including (CFR: 41.7
/ 45.5): Turbine stop/governor valve closure on turbine trip 3.5 62
ES-401 13 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 2 (RO/SRO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 055 (SF4S CARS) Condenser Air Removal 056 (SF4S CDS) Condensate 068 (SF9 LRS) Liquid Radwaste X
(068A4.04) (SF9 LRS) LIQUID RADWASTE SYSTEM Ability to manually operate and/or monitor in the control room (CFR: 41.7 / 45.5 to 45.8): Automatic isolation 3.8 63 071 (SF9 WGS) Waste Gas Disposal X
(071K4.02) Knowledge of (SF9 WGS) WASTE GAS DISPOSAL SYSTEM design feature(s) and or interlock(s) which provide for the following (CFR: 41.7): Sealing water around the shaft of the gas compressor 2.5 64 072 (SF7 ARM) Area Radiation Monitoring X
(072K5.01) Knowledge of the operational implications of the following concepts as they apply to the (SF7 ARM) AREA RADIATION MONITORING SYSTEM (CFR: 41.5 / 45.7):
Radiation theory, including sources, types, units, and effects 2.7 65 075 (SF8 CW) Circulating Water 079 (SF8 SAS**) Station Air X (079 (SF8 SAS) STATION AIR) (G2.4.47)
Ability to diagnose and recognize trends in an accurate and timely manner utilizing the appropriate control room reference material.
(G2.4.9) Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss of residual heat removal) mitigation strategies.
(CFR: 41.10 / 43.5 / 45.13) 4.2 93 079 (SF8 SAS**) Station Air 086 Fire Protection 050 (SF 9 CRV*) Control Room Ventilation K/A Category Point Totals:
0 1
1 1
1 1
1 3
1 1
2 Group Point Total: (RO/SRO) 10/3
ES-401 14 Form ES-401-3 ES-401 PWR Examination Outline (Braidwood)
Form ES-401-3 Generic Knowledge and Abilities Outline (Tier 3) (RO/SRO)
Facility:
Braidwood Date of Exam: 02/28/2022 Category K/A #
Topic RO SRO-Only IR Q#
IR Q#
- 1. Conduct of Operations G2.1.3
[G2.1.25] (G2.1.3) Knowledge of shift or short-term turnover practices.
(CFR: 41.10 / 45.13) 3.7 66 G2.1.15
[G2.1.32] (G2.1.15) Knowledge of administrative requirements for temporary management directives, such as standing orders, night orders, Operations memo, etc. (CFR: 41.10 / 45.12) 2.7 67 G2.1.17 (G2.1.17) Ability to make accurate, clear, and concise verbal reports.
(CFR: 41.10 / 45.12 / 45.13) 3.9 68 G2.1.40 (G2.1.40) Knowledge of refueling administrative requirements. (CFR:
41.10 / 43.5 / 45.13) 3.9 94 G2.1.43
[G2.1.28] (G2.1.43) Ability to use procedures to determine the effects on reactivity of plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc. (CFR: 41.10 / 43.6 /
45.6) 4.3 95 Subtotal 3
2
- 2. Equipment Control G2.2.4
[G2.2.3] (G2.2.4) (multi-unit license) Ability to explain the variations in control board/control room layouts, systems, instrumentation, and procedural actions between units at a facility. (CFR: 41.6 / 41.7 / 41.10
/ 45.1 / 45.13) 3.6 69 G2.2.43 (G2.2.43) Knowledge of the process used to track inoperable alarms.
(CFR: 41.10 / 43.5 / 45.13) 3.0 70 G2.2.20
[G2.2.44] (G2.2.20) Knowledge of the process for managing troubleshooting activities. (CFR: 41.10 / 43.5 / 45.13) 3.8 96 G2.2.25 (G2.2.25) Knowledge of the bases in Technical Specifications for limiting conditions for operations and safety limits. (CFR: 41.5 / 41.7 /
43.2) 4.2 97 Subtotal 2
2
- 3. Radiation Control G2.3.11 (G2.3.11) Ability to control radiation releases. (CFR: 41.11 / 43.4 /
45.10) 3.8 71 G2.3.14 (G2.3.14) Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities.
(CFR: 41.12 / 43.4 / 45.10) 3.4 72 G2.3.13 (G2.3.13) Knowledge of radiological safety procedures pertaining to licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR: 41.12
/ 43.4 / 45.9 / 45.10) 3.8 98 Subtotal 2
1
- 4. Emergency Procedures/Plan G2.4.12 (G2.4.12) Knowledge of general operating crew responsibilities during emergency operations. (CFR: 41.10 / 45.12) 4.0 73 G2.4.13 (G2.4.13) Knowledge of crew roles and responsibilities during EOP usage. (CFR: 41.10 / 43.5 / 45.12) 4.0 74 G2.4.39 (G2.4.39) Knowledge of RO responsibilities in emergency plan implementation. (CFR: 41.10 / 45.11) 3.9 75 G2.4.16 (G2.4.16) Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines. (CFR: 41.10 / 43.5 / 45.13) 4.4 99 G2.4.28 (G2.4.28) Knowledge of procedures relating to a security event (non-safeguards information). (CFR: 41.10 / 43.5 / 45.13) 4.1 100 Subtotal 3
2