ML22173A151

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Ile ES-401-2 and ES-401-3
ML22173A151
Person / Time
Site: Braidwood  Constellation icon.png
Issue date: 02/22/2018
From: Randy Baker
NRC/RGN-III/DRS/OLB
To:
Baker R
Shared Package
ML17164A334 List:
References
Download: ML22173A151 (11)
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Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: BRAIDWOOD STATION UNITS 1 and 2 Date of Exam: MAY 29 - June 8, 2018 RO K/A Category Points SRO-Only Points Tier Group K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 3 3 3 3 3 3 18 3 3 6 Emergency and Abnormal Plant 2 1 2 1 N/A 1 2 N/A 2 9 2 2 4 Evolutions Tier Totals 4 5 4 4 5 5 27 5 5 10 1 3 2 3 3 2 2 3 3 2 2 3 28 3 2 5 2.

Plant 2 1 1 1 1 0 1 1 1 1 1 1 10 0 2 1 3 Systems Tier Totals 4 3 4 4 2 3 4 4 3 3 4 38 5 3 8

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

EK2.03 - Knowledge of the interrelations between a 000007 (EPE 7; BW E02&E10; CE E02) X Reactor Trip and the following: Reactor trip status 3.5 39 Reactor Trip, Stabilization, Recovery / 1 panel. (CFR 41.7 / 45.7)

AK2.01 - Knowledge of the interrelations between 000008 (APE 8) Pressurizer Vapor Space X the Pressurizer Vapor Space Accident and the 2.7* 40 Accident / 3 following: Valves EK1.01 -Knowledge of the operational implications 000009 (EPE 9) Small Break LOCA / 3 X of the following concepts as they apply to the Small 4.2 41 Break LOCA- Natural circulation and cooling, including reflux boiling.

EA1.05 Ability to operate and monitor the following 000011 (EPE 11) Large Break LOCA / 3 X as they apply to a Large Break LOCA: Containment 4.4 42 isolation valves.

2.4.20 - Knowledge of operational implications of 000011 (EPE 11) Large Break LOCA / 3 X EOP warnings, cautions, and notes. 4.3 84 (CFR: 41.10 / 43.5 / 45.13)

SRO-Only Question AA1.13 - Ability to operate and/or monitor the 000015 (APE 15) Reactor Coolant Pump X following as they apply to Reactor Coolant Pump 3.4* 43 Malfunctions / 4 Malfunctions (Loss of RC Flow): Reactor power level indicators.

AA2.01 - Ability to determine or interpret the 000022 (APE 22) Loss of Reactor Coolant X following as they apply to the Loss of Reactor 3.2 44 Makeup / 2 Coolant Makeup: Whether charging line leak exists.

(CFR 43.5/ 45.13)

AK1.01 - Knowledge of the operational implications 000025 (APE 25) Loss of Residual Heat X of the following concepts as they apply to the 3.9 45 Removal System / 4 Residual Heat Removal system: Loss of RHRS during all modes of operation.

(CFR 41.8 / 41.10 / 45.3)

AK3.02 - Knowledge of the reasons for the 000026 (APE 26) Loss of Component X following responses as the apply to the Loss of 3.6 46 Cooling Water / 8 Component Cooling Water: The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS AA2.06 - Ability to determine and interpret the 000027 (APE 27) Pressurizer Pressure X following as they apply to the Pressurizer Pressure 3.9 85 Control System Malfunction / 3 Control Malfunctions: Conditions requiring plant shutdown. (CFR: 43.5 / 45.13)

SRO-Only Question 2.4.22 - Knowledge of the bases for prioritizing 000029 (EPE 29) Anticipated Transient X safety functions during abnormal/emergency 4.4 86 Without Scram / 1 operations. (CFR: 41.7 / 41.10 / 43.5 / 45.12)

SRO-Only Question EK3.09 - Knowledge of the reasons for the 000038 (EPE 38) Steam Generator Tube X following responses as the apply to the SGTR: 4.1 47 Rupture / 3 Criteria for securing/throttling ECCS.

AK1.04 - Knowledge of the operational implications 000040 (APE 40; BW E05; CE E05; W E12) X of the following concepts as they apply to Steam 3.2 48 Steam Line RuptureExcessive Heat Line Rupture: Nil ductility temperature.

Transfer / 4 2.4.9 - Knowledge of low power/shutdown 000054 (APE 54; CE E06) Loss of Main X implications in accident (e.g., loss of coolant 3.8 49 Feedwater /4 accident or loss of residual heat removal) mitigation strategies.

EA2.02 - Ability to determine or interpret the 000055 (EPE 55) Station Blackout / 6 X following as they apply to a Station Blackout: RCS 4.4 50 core cooling through natural circulation cooling to S/G cooling.

AA2.76 - Ability to determine or interpret the 000056 (APE 56) Loss of Offsite Power / 6 X following as they apply to the Loss of Offsite Power: 2.6 51 Reactor makeup water pump (running).

ES-401 3 Form ES-401-2 AA2.14 - Ability to determine and interpret the 000057 (APE 57) Loss of Vital AC X following as they apply to the Loss of Vital AC 3.6 87 Instrument Bus / 6 Instrument Bus: That substitute power sources have come on line on a loss of initial AC.

SRO-Only Question (CFR: 43.5 / 45.13)

AA1.03 - Ability to operate and/or monitor the 000058 (APE 58) Loss of DC Power / 6 X following as they apply to Loss of DC Power: Vital 3.1 52 and battery bus components.

AK3.02 - Knowledge of the reasons for the 000062 (APE 62) Loss of Nuclear Service X following responses as the apply to the Loss of 3.6 53 Water / 4 Nuclear Service Water: The automatic actions (alignments) within the nuclear service water resulting from the actuation of the ESFAS.

2.4.35 - Knowledge of local auxiliary operator tasks 000065 (APE 65) Loss of Instrument Air / 8 X during an emergency plan and the resultant 3.8 54 operational effects.

AK2.07 - Knowledge of the interrelations between 000077 (APE 77) Generator Voltage and X Generator Voltage and Electric Grid Disturbances 3.6 55 Electric Grid Disturbances / 6 and the following: Turbine / Generator control.

2.1.32 - Ability to explain and apply system limits (W E04) LOCA Outside Containment / 3 X and precautions. 3.8 56 2.1.31 - Ability to locate control room switches, (W E11) Loss of Emergency Coolant X controls, and indications, and to determine that they 4.3 88 Recirculation / 4 correctly reflect the desired plant lineup.

(CFR: 41.10 / 45.12)

SRO-Only Question EA2.05 - Ability to determine and interpret the (BW E04; W E05) Inadequate Heat X following as they apply to the (Loss of Secondary 4.4 89 TransferLoss of Secondary Heat Sink / 4 Heat Sink): Facility conditions and selection of appropriate procedures during abnormal and SRO-Only Question emergency operations. (CFR: 43.5 / 45.13)

K/A Category Totals: 3 3 3 3 3/3 3/3 Group Point Total: 18/6

ES-401 4 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 000003 (APE 3) Dropped Control Rod / 1 X 2.1.27 - Knowledge of system 3.9 57 purpose and/or function.

000005 (APE 5) Inoperable/Stuck Control Rod / 1 X AA2.01 - Ability to determine and 3.3 58 interpret the following as they apply to the Inoperable/Stuck Control Rod: Stuck or inoperable rod from in-core and ex-core NIS, in-core or loop temperature measurements.

000024 (APE 24) Emergency Boration / 1 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 000032 (APE 32) Loss of Source Range Nuclear X AK2.01 - Knowledge of the 2.7* 59 Instrumentation / 7 interrelations between the Loss of Source Range Nuclear Instrumentation and the following:

Power supplies, including proper switch positions.

000033 (APE 33) Loss of Intermediate Range Nuclear X 2.4.45 - Ability to prioritize and 4.3 90 Instrumentation / 7 interpret the significance of each SRO-Only Question annunciator or alarm.

(CFR: 41.10 / 43.5 / 45.3 / 45.12) 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 X K3.02 Knowledge of the reasons 2.9 60 for the following responses as they apply to Fuel Handling Incidents: Interlocks associated with fuel handling equipment.

(CFR 41.5,41.10 / 45.6 / 45.13) 000037 (APE 37) Steam Generator Tube Leak / 3 X AK1.01 - Knowledge of the 2.9* 61 operational implications of the following concepts as they apply to Steam Generator Tube Leak:

Use of steam tables.

(CFR 41.8 / 41.10 / 45.3) 000051 (APE 51) Loss of Condenser Vacuum / 4 000059 (APE 59) Accidental Liquid Radwaste Release / 9 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 000061 (APE 61) Area Radiation Monitoring System Alarms X 2.2.44 - Ability to interpret control 4.2 62

/7 room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions.

(CFR: 41.5 / 43.5 / 45.12) 000067 (APE 67) Plant Fire On Site / 8 X AA2.15 - Ability to determine and 3.9 91 SRO-Only Question interpret the following as they apply to the Plant Fire on Site:

Fire Watch Requirements.

(CFR: 43.5 / 45.13) 000068 (APE 68; BW A06) Control Room Evacuation / 8 000069 (APE 69; W E14) Loss of Containment Integrity / 5 X 2.4.30 - Knowledge of events 4.1 92 SRO-Only Question 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)

ES-401 5 Form ES-401-2 000074 (EPE 74; W E06 & E07) Inadequate Core Cooling / X EA2.1 - Ability to determine and 4.0 93 4 interpret the following as they SRO-Only Question apply to the (Saturated Core Cooling): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

(CFR: 43.5 / 45.13) 000076 (APE 76) High Reactor Coolant Activity / 9 000078 (APE 78*) RCS Leak / 3 (W E01 & E02) Rediagnosis & SI Termination / 3 (W E13) Steam Generator Overpressure / 4 (W E15) Containment Flooding / 5 X EA2.2 - Ability to determine or 2.9 63 interpret the following as they apply to the (Containment Flooding): Adherence to appropriate procedures and operation within the limitations in the facility's license and amendments. (CFR: 43.5 / 45.13)

(W E16) High Containment Radiation /9 X EK2.1 - Knowledge of the 3.0 64 interrelations between the (High Containment Radiation) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(CFR: 41.7 / 45.7)

(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 EA1.1 - Ability to operate and / or 4.0 65 monitor the following as they apply to the (LOCA Cooldown and Depressurization):

Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

(CFR: 41.7 / 45.5 / 45.6)

(BW E09; CE A13**; W E09 & E10) Natural Circulation/4 (BW E13 & E14) EOP Rules and Enclosures (CE A11**; W E08) RCS OvercoolingPressurized Thermal Shock / 4 (CE A16) Excess RCS Leakage / 2 (CE E09) Functional Recovery (CE E13*) Loss of Forced Circulation/LOOP/Blackout / 4 K/A Category Point Totals: 1 2 1 1 2/2 2/2 Group Point Total: 9/4

ES-401 6 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 #

K1.01 - Knowledge of the physical 003 (SF4P RCP) Reactor Coolant X connections and/or cause-effect relationships 2.6 1 Pump between the RCPS and the following systems:

RCP lube oil.

A4.03 - Ability to manually operate and/or 003 (SF4P RCP) Reactor Coolant X monitor in the control room: RCP lube oil and 2.8 2 Pump lift pump motor controls.

K4.12 - Knowledge of CVCS design feature(s) 004 (SF1; SF2 CVCS) Chemical and X and/or interlock(s) which provide for the 3.1 3 Volume Control following: Minimum level of VCT.

A2.10 - Ability to (a) predict the impacts of the 004 (SF1; SF2 CVCS) Chemical and X following malfunctions or operations on the 4.2 76 Volume Control CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate SRO-Only Question the consequences of those malfunctions or operations: Inadvertent boration/dilution.

(CFR: 41.5/ 43/5 / 45/3 / 45/5)

K5.05 - Knowledge of the operational 005 (SF4P RHR) Residual Heat X implications of the following concepts as they 2.7* 4 Removal apply the RHRS: Plant response during "solid plant": pressure change due to the relative incompressibility of water.

2.1.23 - Ability to perform specific system and 005 (SF4P RHR) Residual Heat X integrated plant procedures during all modes 4.4 77 Removal of plant operation.

(CFR: 41.10 / 43.5 / 45.2 / 45.6)

SRO-Only Question K4.26 - Knowledge of ECCS design feature(s) 006 (SF2; SF3 ECCS) Emergency X and/or interlock(s) which provide for the 3.3 5 Core Cooling following: Parallel redundant systems.

K1.01 - Knowledge of the physical 007 (SF5 PRTS) Pressurizer X connections and/or cause-effect relationships 2.9 6 Relief/Quench Tank between the PRTS and the following systems:

Containment system.

K3.01 - Knowledge of the effect that a loss or 008 (SF8 CCW) Component Cooling X malfunction of the CCWS will have on the 3.4 7 Water following: Loads cooled by CCWS.

2.4.21 - Knowledge of the parameters and 008 (SF8 CCW) Component Cooling X logic used to assess the status of safety 4.0 8 Water functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc.

A3.01 - Ability to monitor automatic operation 010 (SF3 PZR PCS) Pressurizer X of the PZR PCS, including: PRT temperature 3.0 9 Pressure Control and pressure during PORV testing.

K5.01 - Knowledge of the operational 010 (SF3 PZR PCS) Pressurizer X implications of the following concepts as they 3.5 10 Pressure Control apply to the PZR PCS: Determination of condition of fluid in PZR, using steam tables.

A4.01 - Ability to manually operate and/or 012 (SF7 RPS) Reactor Protection X monitor in the control room: Manual trip button. 4.5 11 K1.02 - Knowledge of the physical 012 (SF7 RPS) Reactor Protection X connections and/or cause-effect relationships 3.4 12 between the RPS and the following systems:

125VDC system.

K6.01 - Knowledge of the effect of a loss or 013 (SF2 ESFAS) Engineered X malfunction on the following will have on the 2.7* 13 Safety Features Actuation ESFAS: Sensors and detectors

ES-401 7 Form ES-401-2 A2.03 - Ability to (a) predict the impacts of the 022 (SF5 CCS) Containment Cooling X following malfunctions or operations on the 2.6 14 CCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Fan motor thermal overload/high-speed operation.

A2.06 - Ability to (a) predict the impacts of the 022 (SF5 CCS) Containment Cooling X following malfunctions or operations on the 3.2* 78 CCS; and (b) based on those predictions, use SRO-Only Question procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of CCS pump.

(CFR: 41.5 / 43.5 / 45.3 / 45.13) 025 (SF5 ICE) Ice Condenser A1.01 - Ability to predict and/or monitor 026 (SF5 CSS) Containment Spray X changes in parameters (to prevent exceeding 3.9 15 design limits) associated with operating the CSS controls including: Containment pressure.

A1.10 - Ability to predict and/or monitor 039 (SF4S MSS) Main and Reheat X changes in parameters (to prevent exceeding 2.9* 16 Steam design limits) associated with operating the MRSS controls including: Air ejector PRM.

A3.02 - Ability to monitor automatic operation 039 (SF4S MSS) Main and Reheat X of the MRSS, including: Isolation of the MRSS. 3.1 17 Steam A2.05 - Ability to (a) predict the impacts of the 059 (SF4S MFW) Main Feedwater X following malfunctions or operations on the 3.1* 18 MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Rupture in MFW suction or discharge line.

K2.03 - Knowledge of bus power supplies to 061 (SF4S AFW) X the following: AFW diesel driven pump. 4.0* 19 Auxiliary/Emergency Feedwater A1.03 - Ability to predict and/or monitor 062 (SF6 ED AC) AC Electrical X changes in parameters (to prevent exceeding 2.5 20 Distribution design limits) associated with operating the AC distribution system controls including: Effect on instrumentation and controls of switching power supplies.

A2.06 - Ability to (a) predict the impacts of the 062 (SF6 ED AC) AC Electrical X following malfunctions or operations on the ac 3.9 79 Distribution distribution system; and (b) based on those predictions, use procedures to correct, control, SRO-Only Question or mitigate the consequences of those malfunctions or operations: Keeping the safeguards buses electrically separate.

(CFR: 41.5 / 43.5 / 45.3 / 45.13)

A2.01 - Ability to (a) predict the impacts of the 063 (SF6 ED DC) DC Electrical X following malfunctions or operations on the DC 2.5 21 Distribution electrical systems; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Grounds.

2.4.49 - Ability to perform without reference to 063 (SF6 ED DC) DC Electrical X procedures those actions that require 4.4 80 Distribution immediate operation of system components and controls. (CFR: 41.10 / 43.2 / 45.6)

SRO-Only Question K6.07 - Knowledge of the effect of a loss or 064 (SF6 EDG) Emergency Diesel X malfunction of the following will have on the 2.7 22 Generator EDG system: Air receivers.

K4.01 - Knowledge of PRM system design 073 (SF7 PRM) Process Radiation X feature(s) and/or interlock(s) which provide for 4.0 23 Monitoring the following: Release termination when radiation exceeds setpoint.

ES-401 8 Form ES-401-2 2.4.47 - Ability to diagnose and recognize 073 (SF7 PRM) Process Radiation X trends in an accurate and timely manner 4.2 24 Monitoring utilizing the appropriate control room reference material. (CFR: 41.10 / 43.5 / 45.12)

K2.08 - Knowledge of bus power supplies to 076 (SF4S SW) Service Water X the following: ESF-actuated MOVs. 3.1* 25 2.2.39 - Knowledge of less than or equal to 076 (SF4S SW) Service Water X one hour Technical Specification action 3.9 26 statements for systems.

K3.03 - Knowledge of the effect that a loss or 078 (SF8 IAS) Instrument Air X malfunction of the IAS will have on the 3.0 27 following: Cross-tied units. (CFR: 41.7 / 45.6)

K3.03 - Knowledge of the effect that a loss or 103 (SF5 CNT) Containment X malfunction of the containment system will 3.7 28 have on the following: Loss of containment integrity under refueling operations.

053 (SF1; SF4P ICS*) Integrated Control K/A Category Point Totals: 3 2 3 3 2 2 3 3/3 2 2 3/2 Group Point Total: 28/5

ES-401 9 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 X K2.02 - Knowledge of bus power supplies to 3.6 29 the following: One-line diagram of power supply to trip breakers.

002 (SF2; SF4P RCS) Reactor X A2.01 Ability to (a) predict the impacts of the 4.3 32 Coolant following malfunctions or operations on the RCS; and (b) based on those predictions, use Procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of coolant inventory.

(CFR: 41.5 / 43.5 / 45.3 / 45.5) 011 (SF2 PZR LCS) Pressurizer X A3.01 - Ability to monitor automatic operation 2.8* 30 Level Control of the PZR LCS, including: Boration/dilution.

014 (SF1 RPI) Rod Position Indication 015 (SF7 NI) Nuclear X K3.03 - Knowledge of the effect that a loss or 2.7 31 Instrumentation malfunction of the NIS will have on the following: Fuel handling system.

016 (SF7 NNI) Nonnuclear Instrumentation 017 (SF7 ITM) In-Core Temperature Monitor 027 (SF5 CIRS) Containment Iodine Removal 028 (SF5 HRPS) Hydrogen Recombiner and Purge Control 029 (SF8 CPS) Containment Purge X A2.01 - Ability to (a) predict the impacts of the 3.6 81 following malfunctions or operations on the SRO-Only Question Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Maintenance or other activity taking place inside containment.

(CFR: 41.5 / 43.5 / 45.3 / 45.13) 033 (SF8 SFPCS) Spent Fuel Pool X 2.4.41 - Knowledge of the emergency action 4.6 82 Cooling level thresholds and classifications.

(CFR: 41.10 / 43.5 / 45.11)

SRO-Only Question 034 (SF8 FHS) Fuel-Handling Equipment 035 (SF 4P SG) Steam Generator X K6.02 - Knowledge of the effect of a loss or 3.1 34 malfunction on the following will have on the S/GS: Secondary PORV.

041 (SF4S SDS) Steam X A4.05 - Ability to manually operate and/or 3.1 35 Dump/Turbine Bypass Control monitor in the control room: Main steam header pressure.

045 (SF 4S MTG) Main Turbine X 2.4.1 - Knowledge of EOP entry conditions 4.6 33 Generator and immediate action steps.

(CFR: 41.10 / 43.5 / 45.13) 055 (SF4S CARS) Condenser Air Removal 056 (SF4S CDS) Condensate X A2.05 - Ability to (a) predict the impacts of the 2.5* 83 following malfunctions or operations on the SRO-Only Question Condensate System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Condenser tube leakage. (CFR: 41.5 / 43.5 / 45.3 / 45.13) 068 (SF9 LRS) Liquid Radwaste

ES-401 10 Form ES-401-2 071 (SF9 WGS) Waste Gas X A1.06 - Ability to predict and/or monitor 2.5 36 Disposal changes in parameters (to prevent exceeding design limits) associated with Waste Gas Disposal System operating the controls including: Ventilation system.

072 (SF7 ARM) Area Radiation X K4.01 - Knowledge of ARM system design 3.3* 37 Monitoring feature(s) and/or interlock(s) which provide for the following: Containment ventilation isolation.

075 (SF8 CW) Circulating Water X K1.08 - Knowledge of the physical 3.2* 38 connections and/or cause-effect relationships between the circulating water system and the following systems: Emergency/essential SWS.

079 (SF8 SAS**) Station Air 086 Fire Protection 050 (SF 9 CRV*) Control Room Ventilation K/A Category Point Totals: 1 1 1 1 0 1 1 1/2 1 1 1/1 Group Point Total: 10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: BRAIDWOOD STATION UNITS 1 and 2 Date of Exam: MAY 29 - June 8, 2018 Category K/A # Topic RO SRO-only IR # IR #

Ability to use procedures related to shift staffing, such as 2.1.5 3.9 94 minimum crew complement, overtime limitations, etc.

(CFR: 41.10 / 43.5 / 45.12)

Ability to make accurate, clear, and concise logs, records, status 2.1.18 3.6 66 boards, and reports. (CFR: 41.10 / 45.12 / 45.13)

Ability to interpret reference materials, such as graphs, curves,

1. Conduct of 2.1.25 3.9 67 tables, etc. (CFR: 41.10 / 43.5 / 45.12)

Operations Ability to use procedures to determine the effects on reactivity of 2.1.43 4.1 68 plant changes, such as reactor coolant system temperature, secondary plant, fuel depletion, etc. (CFR: 41.10 / 43.6 / 45.6)

Ability to identify and interpret diverse indications to validate the 2.1.45 4.3 95 response of another indication. (CFR: 41.7 / 43.5 / 45.4)

Subtotal 3 2 Knowledge of the process for controlling equipment 2.2.14 3.9 69 configuration or status. (CFR: 41.10 / 43.3 / 45.13)

Knowledge of limiting conditions for operations and safety limits.

2.2.22 4.7 96

2. Equipment (CFR: 41.5 / 43.2 / 45.2)

Control Ability to recognize system parameters that are entry-level 2.2.42 3.9 70 conditions for Technical Specifications.

(CFR: 41.7 / 41.10 / 43.2 / 43.3 / 45.3)

Subtotal 2 1 Knowledge of radiation exposure limits under normal or 2.3.4 3.2 71 emergency conditions. (CFR: 41.12 / 43.4 / 45.10) 2.3.11 Ability to control radiation releases. (CFR: 41.11 / 43.4 / 45.10) 3.8 72 Knowledge of radiological safety procedures pertaining to 2.3.13 3.8 97 licensed operator duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning

3. Radiation filters, etc. (CFR: 41.12 / 43.4 / 45.9 / 45.10)

Control Knowledge of radiation or contamination hazards that may arise 2.3.14 3.4 73 during normal, abnormal, or emergency conditions or activities.

(CFR: 41.12 / 43.4 / 45.10)

Knowledge of radiation monitoring systems, such as fixed 2.3.15 3.1 98 radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc. (CFR: 41.12 / 43.4 / 45.9)

Subtotal 3 2 Ability to identify post-accident instrumentation.

2.4.3 3.7 74 (CFR: 41.6 / 45.4)

Knowledge of low power /shutdown implications in accident (e.g.

2.4.9 4.2 99 LOCA or loss of RHR) mitigation strategies.

4. Emergency (CFR: 41.10 / 43.5 / 45.13)

Procedures/Plan Knowledge of operational implications of EOP warnings, 2.4.20 4.3 100 cautions, and notes. (CFR: 41.10 / 43.5 / 45.13)

Ability to verify that the alarms are consistent with the plant 2.4.46 4.2 75 conditions. (CFR: 41.10 / 43.5 / 45.3 / 45.12)

Subtotal 2 2 Tier 3 Point Total 10 7

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