ML21361A256
| ML21361A256 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 10/28/2021 |
| From: | Gregory Roach NRC/RGN-III/DRS/OLB |
| To: | Exelon Generation Co |
| Roach G | |
| Shared Package | |
| ML21055A846 | List: |
| References | |
| Download: ML21361A256 (16) | |
Text
ES-401 PWR Examination Outline Form ES-401-2
Facility: Byron Nuclear Generating Station Date of Exam: September 2021
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 1 1 N/A 2 2 N/A 2 9 2 2 4 Evolutions Tier Totals 4 4 4 5 5 5 27 5 5 10
1 2 2 3 2 2 3 3 3 3 3 2 28 3 2 5 2.
Plant 2 1 0 1 1 1 1 1 1 1 1 1 10 0 2 1 3 Systems Tier Totals 3 2 4 3 3 4 4 4 4 4 3 38 5 3 8
- 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 3 2 2 2 2 1 2
Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two). (One Tier 3 radiation control K/A is allowed if it is replaced by a K/A from another Tier 3 category.)
- 2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points, and the SRO-only exam must total 25 points.
- 3. Systems/evolutions within each group are identified on the outline. Systems or evolutions that do not apply at the facility should be deleted with justification. Operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.
- 4. Select topics from as many systems and evolutions as possible. Sample every system or evolution in the group before selecting a second topic for any system or evolution.
- 5. Absent a plant -specific priority, only those K/As having an importance rating (IR) of 2.5 or higher 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 -h andling 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 t he 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 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions Tier 1/Group 1 (RO)
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) 03 reactor trip and the following: Reactor trip status panel. 3.5 1 Reactor Trip, Stabilization, Recovery / 1 (CFR: 41.7 / 45.7)
AK3.05 - Knowledge of the reasons for the following 000008 (APE 8) Pressurizer Vapor Space 05 responses as they apply to the Pressurizer Vapor Space 4.0 2 Accident / 3 Accident: ECCS termination or throttling criteria.
(CFR: 41.5, 10 / 45.6, 13)
000009 (EPE 9) Small Break LOCA / 3 EA1.03 - Ability to operate and monitor the following as 000011 (EPE 11) Large Break LOCA / 3 03 they apply to a Large Break LOCA: Securing of RCPs. 4.0 3 (CFR: 41.7 / 45.5, 6)
000015 (APE 15) Reactor Coolant Pump Malfunctions / 4
000022 (APE 22) Loss of Reactor Coolant Makeup / 2 AA2.03 - Ability to determine and interpret the following as 000025 (APE 25) Loss of Residual Heat 03 they apply to the Loss of Residual Heat Removal System: 3.6 4 Removal System / 4 Increasing reactor building sump level.
(CFR: 43.5 / 45.13)
G2.4.4 - Ability to recognize abnormal indications for 000026 (APE 26) Loss of Component 04.system operating parameters that are entry-level conditions 4.5 5 Cooling Water / 8 04 for emergency and abnormal operating procedures.
(CFR: 41.10 / 43.2 / 45.6)
AK1.03 - Knowledge of the operational implications of the 000027 (APE 27) Pressurizer Pressure 03 following concepts as they apply to Pressurizer Pressure 2.6 6 Control System Malfunction / 3 Control Malfunctions: Latent heat of vaporization/condensation.
(CFR: 41.8, 10 / 45.3)
EK2.06 - Knowledge of the interrelations between the and 000029 (EPE 29) Anticipated Transient 06 the following an ATWS: Breakers, relays, and disconnects. 2.9 7 Without Scram / 1 (CFR: 41.7 / 45.7)
EK3.06 - Knowledge of the reasons for the following 000038 (EPE 38) Steam Generator Tube 06 responses as they apply to the SGTR: Actions contained in 4.2 8 Rupture / 3 EOP for RCS water inventory balance, S/G tube rupture, and plant shutdown procedures.
(CFR: 41.5, 10 / 45.6, 13)
WE12 EA1.2 - Ability to operate and/or monitor the 000040 (APE 40; BW E05; CE E05; W E12) 02 following as they apply to the (Uncontrolled 3.6 9 Steam Line Rupture Excessive Heat Depressurization of all Steam Generators): Operating Transfer / 4 behavior characteristics of the facility.
(CFR: 41.7 / 45.5, 6)
AA2.02 - Ability to determine and interpret the following as 000054 (APE 54; CE E06 ) Loss of Main 02 they apply to the Loss of Main Feedwater (MFW): 4.1 10 Feedwater /4 Differentiation between loss of all MFW and trip of one MFW pump.
(CFR: 43.5 / 45.13)
G2.4.35 - Knowledge of local auxiliary operator tasks 000055 (EPE 55) Station Blackout / 6 04.during an emergency and the resultant operational effects 3.8 11 35 (CFR: 41.10 / 43.5 / 45.13)
AK1.04 - Knowledge of the operational implications of the 000056 (APE 56) Loss of Offsite Power / 6 04 following concepts as they apply to Loss of Offsite Power: 3.1 12 Definition of saturation conditions, implication for the systems.
(CFR: 41.8, 10 /45.3)
AK3.01 - Knowledge of the reasons for the following 000057 (APE 57) Loss of Vital AC 01 responses as they apply to the Loss of Vital AC Instrument 4.1 13 Instrument Bus / 6 Bus: Actions contained in EOP for loss of vital AC electrical instrument bus.
(CFR: 41.5, 10 / 45.6, 13)
000058 (APE 58) Loss of DC Power / 6 AA1.06 - Ability to operate and/or monitor the following as 000062 (APE 62) Loss of Nuclear Service 06 they apply to the Loss of Nuclear Service Water (SWS): 2.9 14 Water / 4 Control of flow rates to components cooled by the SWS (CFR: 41.7 / 45.5, 6)
AA2.08 - Ability to determine and interpret the following as 000065 (APE 65) Loss of Instrument Air / 8 08 they apply to the Loss of Instrument Air: Failure modes of 2.9 15 air-operated equipment (CFR: 43.5 / 45.13)
AK2.03 - Knowledge of the interrelations between 000077 (APE 77) Generator Voltage and 03 Generator Voltage and Electric Grid Disturbances and the 3.0 16 Electric Grid Disturbances / 6 following: Sensors, detectors, indicators.
(CFR: 41.4, 5, 7, 10 / 45.8)
(W E04) LOCA Outside Containment / 3 G2.4.31 - Knowledge of annunciator alarms, indications, or (W E11) Loss of Emergency Coolant 04.response procedures. 4.2 17 Recirculation / 4 31 (CFR: 41.10 / 45.3)
WE05 EK1.3 - Knowledge of the operational implications (BW E04; W E05) Inadequate Heat 03 of the following concepts as they apply to the (Loss of 3.9 18 Transfer Loss of Secondary Heat Sink / 4 Secondary Heat Sink): Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Secondary Heat Sink)
(CFR: 41.8, 10 / 45.3)
K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18
ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions Tier 1/Group 2 (RO)
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 000005 (APE 5) Inoperable/Stuck Control 01 AA1.01 - Ability to operate and/or monitor the following as 3.6 19 Rod / 1 they apply to the Inoperable / Stuck Control Rod: CRDS (CFR: 41.7 / 45.5, 6) 000024 (APE 24) Emergency Boration / 1 01 AA2.01 - Ability to determine and interpret the following 3.8 20 as they apply to the Emergency Boration: Whether boron flow and/or MOVs are malfunctioning, from plant conditions.
(CFR: 43.5 / 45.13) 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 000032 (APE 32) Loss of Source Range 02.G2.2.42 - Ability to recognize system parameters that are 3.9 21 Nuclear Instrumentation / 7 42 entry-level conditions for Technical Specifications.
(CFR: 41.7, 10 / 43.2, 3 / 45.3) 000033 (APE 33) Loss of Intermediate Range Nuclear Instrumentation / 7 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 000037 (APE 37) Steam Generator Tube 02 AK1.02 - Knowledge of the operational implications of the 3.5 22 Leak / 3 following concepts as they apply to Steam Generator Tube Leak: Leak rate vs pressure drop.
(CFR: 41.8, 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 01 AK2.01 - Knowledge of the interrelations between the 2.5 23 Monitoring System Alarms / 7 Area Radiation Monitoring (ARM) System Alarms and the following: Detectors at each ARM system location.
(CFR: 41.7 / 45.7) 000067 (APE 67) Plant Fire On Site / 8 000068 (APE 68; BW A06) Control Room Evacuation / 8 000069 (APE 69; W E14) Loss of 01 AK3.01 - Knowledge of the reasons for the following 3.8 24 Containment Integrity / 5 responses as they apply to the Loss of Containment Integrity: Guidance contained in EOP for loss of containment integrity.
(CFR: 41.5, 10 / 45.6, 13) 000074 (EPE 74; W E06 & E07)
Inadequate Core Cooling / 4 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 01 WE13 EA1.1 - Ability to operate and/or monitor the 3.1 25 following as they apply to the (Steam Generator Overpressure): Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.
(CFR: 41.7 / 45.5, 6)
(W E15) Containment Flooding / 5 (W E16) High Containment Radiation /9 01 WE16 EA2.1 - Ability to determine and interpret the 2.9 26 following as they apply to the (High Containment Radiation): Facility conditions and selection of appropriate procedures during abnormal and emergency operations.
(CFR: 43.5 / 45.13)
(BW A01) Plant Runback / 1 (BW A02 & A03) Loss of NNI-X/Y/7 ES-401 5 Form ES-401-2
(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 Cooldown Depressurization / 4 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 (BW E13 & E14) EOP Rules and Enclosures (CE A11**; W E08) RCS Overcooling 01.G2.1.25 - Ability to interpret reference materials, such as 3.9 27 Pressurized Thermal Shock / 4 25 graphs, curves, tables, etc.
(CFR: 41.10 / 43.5 / 45.12)
(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 1 1 2 2 2 Group Point Total: 9
ES-401 PWR Examination Outline Form ES-401Plant SystemsTier 2/Group 1 (RO) - 2
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #
K3.01 - Knowledge of the effect that a loss or 003 (SF4P RCP) Reactor Coolant 01 malfunction of the RCPS will have on the following: 3.7 28 Pump RCS (CFR: 41.7 / 45.6)
K4.14 - Knowledge of CVCS design feature(s) 004 (SF1; SF2 CVCS) Chemical and 14 and/or interlock(s) which provide for the following: 2.8 29 Volume Control Control interlocks on letdown system (letdown tank bypass valve).
(CFR: 41.7)
K6.20 - Knowledge of the effect of a loss or 20 malfunction on the following CVCS components: 2.5 30 Function of demineralizer, including boron loading and temperature limits.
(CFR: 41.7 / 45.7)
K5.09 - Knowledge of the operational implications of 005 (SF4P RHR) Residual Heat 09 the following concepts as they apply to RHRS: 3.2 31 Removal Dilution and boration considerations.
(CFR: 41.5 / 45.7)
K6.01 - Knowledge of the effect of a loss or 006 (SF2; SF3 ECCS) Emergency 01 malfunction on the following will have on the ECCS: 3.432 Core Cooling BIT/borated water sources.
(CFR: 41.7 / 45.7)
A1.12 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) 12 associated with operating the ECCS controls 2.9 33 including: RHR heatup limits.
(CFR: 41.5 / 45.5)
A1.02 - Ability to predict and/or monitor changes in 007 (SF5 PRTS) Pressurizer 02 parameters (to prevent exceeding design limits) 2.7 34 Relief/Quench Tank associated with operating the PRTS controls including: Maintaining quench tank pressure.
(CFR: 41.5 / 45.5)
A2.05 - Ability to (a) predict the impacts of the 008 (SF8 CCW) Component Cooling 05 following malfunctions or operations on the CCWS, 3.3 35 Water and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effect of loss of instrument and control air on the position of the CCW valves that are air operated.
(CFR: 41.5 / 43.5 / 45.3, 13)
A3.02 - Ability to monitor automatic operation of the 010 (SF3 PZR PCS) Pressurizer 02 PZR PCS, including PZR pressure.
Pressure Control (CFR: 41.7 / 45.5) 3.6 36 A4.04 - Ability to manually operate and/or monitor in 012 (SF7 RPS) Reactor Protection 04 the control room: Bistable, trips, reset and test 3.3 37 switches.
(CFR: 41.7 / 45.5 to 45.8)
G2.1.31 - Ability to locate control room switches, 013 (SF2 ESFAS) Engineered 01.controls, and indications, and to determine that they 4.6 38 Safety Features Actuation 31 correctly reflect the desired plant lineup.
(CFR: 41.10 / 45.12)
K1.01 - Knowledge of the physical connections 022 (SF5 CCS) Containment Cooling 01 and/or cause-effect relationships between the CCS 3.5 39 and the following systems: SWS/cooling systems (CFR: 41.2 to 41.9 / 45.7 to 45.8) 02 K3.02 - Knowledge of the effect that a loss or 3.0 40 malfunction of the CCS will have on the following:
Containment instrumentation readings.
(CFR: 41.7 / 45.6)
025 (SF5 ICE) Ice Condenser K2.02 - Knowledge of bus power supplies to the 026 (SF5 CSS) Containment Spray 02 following: MOVs. 2.7 41 (CFR: 41.7)
K3.04 - Knowledge of the effect that a loss or 039 (SF4S MSS) Main and Reheat 04 malfunction of the MRSS will have on the following: 2.5 42 Steam MFW pumps.
(CFR: 41.7 / 45.6)
K4.16 - Knowledge of MFW design feature(s) and/or 059 (SF4S MFW) Main Feedwater 16 interlock(s) which provide for the following: 3.1 43 Automatic trips for MFW pumps.
(CFR: 41.7) 03 A3.03 - Ability to monitor automatic operation of the 2.5 44 MFW, including: Feedwater pump suction flow pressure.
(CFR: 41.7 / 45.5)
K5.05 - Knowledge of the operational implications of 061 (SF4S AFW) 05 the following concepts as they apply to the AFW: 2.7 45 Auxiliary/Emergency Feedwater Feed line voiding and water hammer (CFR: 41.5 / 45.7)
A1.01 - Ability to predict and/or monitor changes in 062 (SF6 ED AC) AC Electrical 01 parameters (to prevent exceeding design limits) 3.4 46 Distribution associated with operating AC distribution system control including: Significance of D/G load limits (CFR: 41.5 / 45.5)
A2.15 - Ability to (a) predict the impacts of the 15 following malfunctions or operations on the AC 2.8 47 distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Consequence of paralleling out-of-phase/mismatch in volts (CFR: 41.5 / 43.5 / 45.3, 13)
K2.01 - Knowledge of bus power supplies to the 063 (SF6 ED DC) DC Electrical 01 following: Major DC loads 2.9 48 Distribution (CFR: 41.7)
A2.01 - Ability to (a) predict the impacts of the 01 following malfunctions or operations on the DC 2.5 49 electrical systems, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Grounds.
(CFR: 41.5 / 43.5 / 45.3, 13)
K6.07 - Knowledge of the effect of a loss or 064 (SF6 EDG) Emergency Diesel 07 malfunction of the following will have on the ED/G 2.7 50 Generator system: Air receivers.
(CFR: 41.7 / 45.7)
A4.02 - Ability to manually operate and/or monitor in 073 (SF7 PRM) Process Radiation 02 the control room: Radiation monitoring system 3.7 51 Monitoring control panel (CFR: 41.7 / 45.5 to 45.8)
A3.02 - Ability to monitor automatic operation of the 076 (SF4S SW) Service Water 02 SWS, including: Emergency heat loads. 3.7 52 (CFR: 41.7 / 45.5)
G2.1.30 - Ability to locate and operate components, 078 (SF8 IAS) Instrument Air 01.including local controls. 53 30 (CFR: 41.7 / 45.7) 4.4 K1.08 - Knowledge of the physical connections 103 (SF5 CNT) Containment 08 and/or cause-effect relationships between the 3.6 54 containment system and the following systems: SIS, including actions of safety injection reset.
(CFR: 41.2 to 41.9 / 45.7 to 45.8)
A4.03 - Ability to manually operate and/or monitor in 03 the control room: ESF slave relays. 2.7 55 (CFR: 41.7 / 45.5 to 45.8) 053 (SF1; SF4P ICS*) Integrated Control
K/A Category Point Totals: 2 2 3 2 2 3 3 3 3 3 2 Group Point Total: 28
ES-401 PWR Examination Outline Form ES-401-2 Plant Systems Tier 2/Group 2 (RO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #
001 (SF1 CRDS) Control Rod Drive 47 K5.47 - Knowledge of the following operational 2.9 56 implications as they apply to the CRDS: Factors affecting SUR: b-eff, l, p (CFR: 41.5 / 45.7) 002 (SF2; SF4P RCS) Reactor Coolant 011 (SF2 PZR LCS) Pressurizer 03 K6.03 - Knowledge of the effect of a loss or 2.9 57 Level Control malfunction on the following will have on the PZR LCS: Relationship between PZR level and PZR heater control circuit.
(CFR: 41.7 / 45.7) 014 (SF1 RPI) Rod Position Indication 015 (SF7 NI) Nuclear 04 A1.04 - Ability to predict and/or monitor changes in 3.5 58 Instrumentation parameters (to prevent exceeding design limits) associated with operating the NIS controls including:
Quadrant Power Tilt Ratio.
(CFR: 41.5 / 45.5) 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 033 (SF8 SFPCS) Spent Fuel Pool 03 A2.03 - Ability to (a) predict the impacts of the 3.1 59 Cooling following malfunctions or operations on the Spent Fuel Pool Cooling System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Abnormal spent fuel pool water level or loss of water level (CFR: 41.5 / 43.5 / 45.3, 13) 034 (SF8 FHS) Fuel-Handling 02 A3.02 - Ability to monitor automatic operation of the 2.5 60 Equipment Fuel Handling System, including: Load limits (CFR: 41.7 / 45.5) 035 (SF 4P SG) Steam Generator 041 (SF4S SDS) Steam Dump/Turbine Bypass Control 045 (SF 4S MTG) Main Turbine 06 A4.06 - Ability to manually operate and/or monitor in 2.8 61 Generator the control room: Turbine stop valves.
(CFR: 41.7 / 45.5 to 45.8) 055 (SF4S CARS) Condenser Air Removal 056 (SF4S CDS) Condensate 01. G2.1.27 - Knowledge of system purpose and/or 3.9 62 27 function.
(CFR: 41.7) 068 (SF9 LRS) Liquid Radwaste 071 (SF9 WGS) Waste Gas 04 K4.04 - Knowledge of design feature(s) and/or 2.9 63 Disposal interlock(s) which provide for the following: Isolation of waste gas release tanks (CFR: 41.7) 072 (SF7 ARM) Area Radiation Monitoring 075 (SF8 CW) Circulating Water 07 K3.07 - Knowledge of the effect that a loss or 3.4 64 malfunction of the circulating water system will have on the following: ESFAS.
(CFR: 41.7 / 45.6) 079 (SF8 SAS**) Station Air 01 K1.01 - Knowledge of the physical connections 3.0 65 and/or cause-effect relationships between the SAS and the following systems: IAS.
(CFR: 41.2 to 41.9 / 45.7 to 45.8)
086 Fire Protection 050 (SF 9 CRV*) Control Room Ventilation
K/A Category Point Totals: 1 0 1 1 1 1 1 1 1 1 1 Group Point Total: 10
ES-401 PWR Examination Outline Form ES-401-2 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 #
000007 (EPE 7; BW E02&E10; CE E02)
Reactor Trip, Stabilization, Recovery / 1
000008 (APE 8) Pressurizer Vapor Space Accident / 3 EA2.14 - Ability to determine and interpret the following as 000009 (EPE 9) Small Break LOCA / 3 14 they apply to a small break LOCA: Actions to be taken if 4.4 76 PTS limits are violated (CFR: 43.5 / 45.13)
000011 (EPE 11) Large Break LOCA / 3 AA2.08 - Ability to determine and interpret the following as 000015 (APE 15) Reactor Coolant Pump 08 they apply to the Reactor Coolant Pump Malfunctions (Loss 3.5 77 Malfunctions / 4 of RC Flow): When to secure RCPs on high bearing temperature.
(CFR: 43.5 / 45.13)
G2.4.45 - Ability to prioritize and interpret the significance 000022 (APE 22) Loss of Reactor Coolant 04.of each annunciator or alarm. 4.3 78 Makeup / 2 45 (CFR: 41.10 / 43.5 / 45.3, 12)
000025 (APE 25) Loss of Residual Heat Removal System / 4
000026 (APE 26) Loss of Component Cooling Water / 8
000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3
000029 (EPE 29) Anticipated Transient Without Scram / 1 G2.1.20 - Ability to interpret and execute procedure steps.
000038 (EPE 38) Steam Generator Tube 01.(CFR: 41.10 / 43.5 / 45.12) 4.6 79 Rupture / 3 20
000040 (APE 40; BW E05; CE E05; W E12)
Steam Line Rupture Excessive Heat Transfer / 4
000054 (APE 54; CE E06) Loss of Main Feedwater /4
000055 (EPE 55) Station Blackout / 6
000056 (APE 56) Loss of Offsite Power / 6
000057 (APE 57) Loss of Vital AC Instrument Bus / 6 AA2.03 - Ability to determine and interpret the following as 000058 (APE 58) Loss of DC Power / 6 03 they apply to the Loss of DC Power: DC loads lost; impact 3.9 80 on ability to operate and monitor plant systems.
(CFR: 43.5 / 45.13)
000062 (APE 62) Loss of Nuclear Service Water / 4
000065 (APE 65) Loss of Instrument Air / 8
000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 G2.1.7 - Ability to evaluate plant performance and make (W E04) LOCA Outside Containment / 3 01.operational judgements based on operating characteristics, 4.7 81 07 reactor behavior, and instrument interpretation.
(CFR: 41.5 / 43.5 / 45.12, 13)
(W E11) Loss of Emergency Coolant Recirculation / 4
(BW E04; W E05) Inadequate Heat Transfer Loss of Secondary Heat Sink / 4 ES-401 11 Form ES-401-2
K/A Category Totals: 3 3 Group Point Total: 6
ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions Tier 1/Group 2 (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 02.G2.2.38 - Knowledge of conditions and limitations in the 4.5 82 38 facility license.
(CFR: 41.7, 10 / 43.1 / 45.13) 000005 (APE 5) Inoperable/Stuck Control Rod / 1 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 000036 (APE 36; BW/A08) Fuel-Handling Incidents / 8 000037 (APE 37) Steam Generator Tube Leak / 3 000051 (APE 51) Loss of Condenser 02 AA2.02 - Ability to determine and interpret the following 4.1 83 Vacuum / 4 as they apply to the Loss of Condenser Vacuum:
Conditions requiring reactor and/or turbine trip.
(CFR: 43.5 / 45.13) 000059 (APE 59) Accidental Liquid Radwaste Release / 9 000060 (APE 60) Accidental Gaseous Radwaste Release / 9 000061 (APE 61) Area Radiation Monitoring System Alarms / 7 000067 (APE 67) Plant Fire On Site / 8 000068 (APE 68; BW A06) Control Room Evacuation / 8 000069 (APE 69; W E14) Loss of Containment Integrity / 5 000074 (EPE 74; W E06 & E07)
Inadequate Core Cooling / 4 000076 (APE 76) High Reactor Coolant 02 AA2.02 - Ability to determine and interpret the following 3.4 85 Activity / 9 as they apply to the High Reactor Coolant Activity:
Corrective actions required for high fission product activity in RCS.
(CFR: 43.5 / 45.13) 000078 (APE 78*) RCS Leak / 3 (W E01 & E02) Rediagnosis & SI 02.Knowledge of EOP entry conditions and immediate action 4.8 84 Termination / 3 4.1 steps.
(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 Cooldown Depressurization / 4 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 ES-401 13 Form ES-401-2
(BW E13 & E14) EOP Rules and Enclosures (CE A11**; W E08) RCS Overcooling Pressurized 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: 2 2 Group Point Total: 4
ES-401 PWR Examination Outline Form ES-401Plant SystemsTier 2/Group 1 (SRO) - 2
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #
003 (SF4P RCP) Reactor Coolant Pump
004 (SF1; SF2 CVCS) Chemical and Volume Control A2.02 - Ability to (a) predict the impacts of the 005 (SF4P RHR) Residual Heat 02 following malfunctions or operations on the RHRS, 3.7 86 Removal and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Pressure transient protection during cold shutdown.
(CFR: 41.5 / 43.5 / 45.3, 13)
006 (SF2; SF3 ECCS) Emergency Core Cooling
007 (SF5 PRTS) Pressurizer Relief/Quench Tank
008 (SF8 CCW) Component Cooling Water
010 (SF3 PZR PCS) Pressurizer Pressure Control G2.4.30 - Knowledge of events related to system 012 (SF7 RPS) Reactor Protection 04.operation/status that must be reported to internal 4.1 87 30 organizations or external agencies, such as the State, the NRC, or the transmission system operator.
(CFR: 41.10 / 43.5 / 45.11)
013 (SF2 ESFAS) Engineered Safety Features Actuation
022 (SF5 CCS) Containment Cooling
025 (SF5 ICE) Ice Condenser A2.08 - Ability to (a) predict the impacts of the 026 (SF5 CSS) Containment Spray 08 following malfunctions or operations on the CSS, 3.7 88 and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Safe securing of containment spray when it can be done.
(CFR: 41.5 / 43.5 / 45.3, 13)
039 (SF4S MSS) Main and Reheat Steam
059 (SF4S MFW) Main Feedwater A2.07 - Ability to (a) predict the impacts of the 061 (SF4S AFW) 07 following malfunctions or operations on the AFW, 3.5 89 Auxiliary/Emergency Feedwater and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Air or MOV failure (CFR: 41.5 / 43.5 / 45.3, 13)
062 (SF6 ED AC) AC Electrical Distribution
063 (SF6 ED DC) DC Electrical Distribution
064 (SF6 EDG) Emergency Diesel Generator
073 (SF7 PRM) Process Radiation Monitoring ES-401 15 Form ES-401-2
G2.2.12 - Knowledge of surveillance procedures.
076 (SF4S SW) Service Water 02.(CFR: 41.10 / 45.13) 4.1 90 12
078 (SF8 IAS) Instrument Air
103 (SF5 CNT) Containment
053 (SF1; SF4P ICS*) Integrated Control
K/A Category Point Totals: 3 2 Group Point Total: 5
ES-401 PWR Examination Outline Form ES-401-2 Plant Systems Tier 2/Group 2 (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 03 A2.03 - Ability to (a) predict the impacts of the 4.3 91 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 forced circulation (CFR: 41.5 / 43.5 / 45.3, 5) 011 (SF2 PZR LCS) Pressurizer Level Control 014 (SF1 RPI) Rod Position Indication 015 (SF7 NI) Nuclear Instrumentation 016 (SF7 NNI) Nonnuclear 02.G2.2.40 - Ability to apply Technical Specifications 4.7 92 Instrumentation 40 for a system.
(CFR: 41.10 / 43.2, 5 / 45.3) 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 033 (SF8 SFPCS) Spent Fuel Pool Cooling 034 (SF8 FHS) Fuel-Handling Equipment 035 (SF 4P SG) Steam Generator 041 (SF4S SDS) Steam 02 A2.02 - Ability to (a) predict the impacts of the 3.9 93 Dump/Turbine Bypass Control following malfunctions or operations on the SDS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Steam valve stuck open (CFR: 41.5 / 43.5 /45.3, 13) 045 (SF 4S MTG) Main Turbine Generator 055 (SF4S CARS) Condenser Air Removal 056 (SF4S CDS) Condensate 068 (SF9 LRS) Liquid Radwaste 071 (SF9 WGS) Waste Gas Disposal 072 (SF7 ARM) Area Radiation Monitoring 075 (SF8 CW) Circulating Water 079 (SF8 SAS**) Station Air 086 Fire Protection 050 (SF 9 CRV*) Control Room Ventilation
K/A Category Point Totals: 2 1 Group Point Total: 3