ML19343C830
| ML19343C830 | |
| Person / Time | |
|---|---|
| Site: | Byron  |
| Issue date: | 01/29/2019 |
| From: | Chuck Zoia NRC/RGN-III/DRS/OLB |
| To: | Exelon Generation Co |
| Zoia C | |
| Shared Package | |
| ML17164A346 | List: |
| References | |
| Download: ML19343C830 (17) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: BYRON Date of Exam: Jan 7, 2019 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 3
3 N/A 3
3 N/A 3
18 3
3 6
2 1
1 2
2 2
1 9
2 2
4 Tier Totals 4
4 5
5 5
4 27 5
5 10
- 2.
Plant Systems 1
3 2
3 3
2 2
3 3
3 2
2 28 3
2 5
2 1
0 1
1 1
1 1
1 1
1 1
10 1
1 1
3 Tier Totals 4
2 4
4 3
3 4
4 4
3 3
38 5
3 8
- 3. Generic Knowledge and Abilities Categories 1
2 3
4 10 1
2 3
4 7
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-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)
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 19 AA2.19 - Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident: PZR spray valve failure, using plant parameters.
(CFR: 43.5 / 45.13) 3.4 1
000009 (EPE 9) Small Break LOCA / 3 01.
20 G2.1.20 - Ability to interpret and execute procedure steps.
(CFR: 41.10 / 43.5 / 45.12) 4.6 2
000011 (EPE 11) Large Break LOCA / 3 01 EK1.01 - Knowledge of the operational implications of the following concepts as they apply to the Large Break LOCA: Natural circulation and cooling, including reflux boiling.
(CFR: 41.8, 41.10 / 45.3) 4.1 3
000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 08 AK2.08 - Knowledge of the interrelations between the Reactor Coolant Pump Malfunctions (Loss of RC Flow) and the following: CCWS.
(CFR: 41.7 / 45.7) 2.6 4
000022 (APE 22) Loss of Reactor Coolant Makeup / 2 000025 (APE 25) Loss of Residual Heat Removal System / 4 02 AK3.02 - Knowledge of the reasons for the following responses as they apply to the Loss of Residual Heat Removal System: Isolation of RHR low-pressure piping prior to pressure increase above specified level.
(CFR: 41.5, 41.10 / 45.6, 45.13) 3.3 5
000026 (APE 26) Loss of Component Cooling Water / 8 05 AA1.05 - Ability to operate and / or monitor the following as they apply to the Loss of Component Cooling Water: The CCWS surge tank, including level control and level alarms, and radiation alarm.
(CFR: 41.7 / 45.5, 45.6) 3.1 6
000027 (APE 27) Pressurizer Pressure Control System Malfunction / 3 08 AA2.08 - Ability to determine and interpret the following as they apply to the Pressurizer Pressure Control Malfunction: Letdown flow indication.
(CFR: 43.5 / 45.13) 3.2 7
000029 (EPE 29) Anticipated Transient Without Scram / 1 000038 (EPE 38) Steam Generator Tube Rupture / 3 02 EK1.02 - Knowledge of the operational implications of the following concepts as they apply to the SGTR: Leak rate vs. pressure drop.
(CFR: 41.8, 41.10 / 45.3) 3.2 8
000040 (APE 40; BW E05; CE E05; W E12)
Steam Line RuptureExcessive Heat Transfer / 4 01 EK2.1 - Knowledge of the interrelations between the (Uncontrolled Depressurization of all Steam Generators) 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) 3.4 9
000054 (APE 54; CE E06) Loss of Main Feedwater /4 01.
31 G2.1.31 - Ability to locate control room switches, controls, and indications, and to determine that they correctly reflect the desired plant lineup.
(CFR: 41.10 / 45.12) 4.6 10 000055 (EPE 55) Station Blackout / 6 000056 (APE 56) Loss of Offsite Power / 6 01 AK3.01 - Knowledge of the reasons for the following responses as they apply to the Loss of Offsite Power: Order and time to initiation of power for the load sequencer.
(CFR: 41.5, 41.10 / 45.6, 45.13) 3.5 11
ES-401 3
Form ES-401-2 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 06 AA1.06 - Ability to operate and / or monitor the following as they apply to the Loss of Vital AC Instrument Bus: Manual control of components for which automatic control is lost.
(CFR: 41.7 / 45.5, 45.6) 3.5 12 000058 (APE 58) Loss of DC Power / 6 01 AK1.01 - Knowledge of the operational implications of the following concepts as they apply to Loss of DC Power: Battery charger equipment and instrumentation.
(CFR: 41.8, 41.10 / 45.3) 2.8 13 000062 (APE 62) Loss of Nuclear Service Water / 4 02 AA2.02 - Ability to determine and interpret the following as they apply to the Loss of Nuclear Service Water: The cause of possible SWS loss.
(CFR: 43.5 / 45.13) 2.9 14 000065 (APE 65) Loss of Instrument Air / 8 04.
31 G2.4.31 - Knowledge of annunciator alarms, indications, or response procedures.
(CFR: 41.10 / 45.3) 4.2 15 000077 (APE 77) Generator Voltage and Electric Grid Disturbances / 6 05 AK2.05 - Knowledge of the interrelations between Generator Voltage and Electric Grid Disturbances and the following: Pumps.
(CFR: 41.4, 41.5, 41.7, 41.10 / 45.8) 3.1 16 (W E04) LOCA Outside Containment / 3 01 EK3.1 - Knowledge of the reasons for the following responses as they apply to the (LOCA Outside Containment): Facility operating characteristics during transient conditions, including coolant chemistry and the effects of temperature, pressure, and reactivity changes and operating limitations and reasons for these operating characteristics.
(CFR: 41.5, 41.10 / 45.6, 45.13) 3.2 17 (W E11) Loss of Emergency Coolant Recirculation / 4 03 EA1.3 - Ability to operate and / or monitor the following as they apply to the (Loss of Emergency Coolant Recirculation): Desired operating results during abnormal and emergency situations.
(CFR: 41.7 / 45.5, 45.6) 3.7 18 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 K/A Category Totals:
3 3
3 3
3 3
Group Point Total:
18
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)
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 10 AK1.10 - Knowledge of the operational implications of the following concepts as they apply to Dropped Control Rod:
Definitions of core quadrant power tilt.
(CFR: 41.8, 41.10 / 45.3) 2.6 19 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 01 AK3.01 - Knowledge of the reasons for the following responses as they apply to the Loss of Source Range Nuclear Instrumentation: Startup termination on source-range loss.
(CFR: 41.5, 41.10 / 45.6, 45.13) 3.2 20 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 11 AA1.11 - Ability to operate and /
or monitor the following as they apply to the Steam Generator Tube Leak: PZR level indicator (CFR: 41.7 / 45.5, 45.6) 3.4 21 000051 (APE 51) Loss of Condenser Vacuum / 4 000059 (APE 59) Accidental Liquid Radwaste Release / 9 05 AA2.05 - Ability to determine and interpret the following as they apply to the Accidental Liquid Radwaste Release: The occurrence of automatic safety actions as a result of a high PRM system signal.
(CFR: 43.5 / 45.13) 3.6 22 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 04.
45 G2.4.45 - Ability to prioritize and interpret the significance of each annunciator or alarm.
(CFR: 41.10 / 43.5 / 45.3, 45.12) 4.1 23 000068 (APE 68; BW A06) Control Room Evacuation / 8 05 AA2.05 - Ability to determine and interpret the following as they apply to the Control Room Evacuation: Availability of heat sink.
(CFR: 43.5 / 45.13) 4.2 24 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 Activity / 9 000078 (APE 78*) RCS Leak / 3
ES-401 5
Form ES-401-2 (W E01 & E02) Rediagnosis & SI Termination / 3 02 EK2.2 - Knowledge of the interrelations between the (Reactor Trip or Safety Injection /
Rediagnoses) and the following:
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.
(CFR: 41.7 / 45.7) 3.5 25 (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 02 EK3.2 - Knowledge of the reasons for the following responses as they apply to the (LOCA Cooldown and Depressurization): Normal, abnormal and emergency operating procedures associated with (LOCA Cooldown and Depressurization).
(CFR: 41.5, 41.10 / 45.6, 45.13) 3.4 26 (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 03 EA1.3 - Ability to operate and / or monitor the following as they apply to the (Pressurized Thermal Shock): Desired operating results during abnormal and emergency situations.
(CFR: 41.7 / 45.5, 45.6) 3.6 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:
1 1
2 2
2 1
Group Point Total:
9
ES-401 6
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (RO)
System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*
K/A Topic(s)
IR 003 (SF4P RCP) Reactor Coolant Pump 01 05 K3.01 - Knowledge of the effect that a loss or malfunction of the RCPS will have on the following: RCS (CFR: 41.7 / 45.6)
A2.05 - Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effects of VCT pressure on RCP seal leakoff flows.
(CFR: 41.5 / 43.5 / 45.3, 45.13) 3.7 2.5 28 29 004 (SF1; SF2 CVCS) Chemical and Volume Control 14 K4.14 - Knowledge of CVCS design feature(s) and/or interlock(s) which provide for the following: Control interlocks on letdown system (letdown tank bypass valve).
(CFR: 41.7) 2.8 30 005 (SF4P RHR) Residual Heat Removal 05 02 K5.05 - Knowledge of the operational implications of the following concepts as they apply to the RHRS: Plant response during solid plant: pressure change due to the relative incompressibility of water.
(CFR: 41.5 / 45.7)
A1.02 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RHRS controls including: RHR flow rate.
(CFR: 41.5 / 45.5) 2.7 3.3 31 32 006 (SF2; SF3 ECCS) Emergency Core Cooling 18 K6.18 - Knowledge of the effect of a loss or malfunction on the following will have on the ECCS: Subcooling margin indicators.
(CFR: 41.7 / 45.7) 3.5 33 007 (SF5 PRTS) Pressurizer Relief/Quench Tank 02 A1.02 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRTS controls including: Maintaining quench tank pressure.
(CFR: 41.5 / 45.5) 2.7 34 008 (SF8 CCW) Component Cooling Water 03 A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the CCWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High/low CCW temperature.
(CFR: 41.5 / 43.5 / 45.3, 45.13) 3.0 35 010 (SF3 PZR PCS) Pressurizer Pressure Control 03 01 A3.01 - Ability to monitor automatic operation of the PZR PCS, including: PRT temperature and pressure during PORV testing.
(CFR: 41.7 / 45.5)
K1.03 - Knowledge of the physical connections and/or cause-effect relationships between the PZR PCS and the following systems: PZR LCS.
(CFR: 41.2-41.9 / 45.7-45.8) 3.0 3.2 36 37 012 (SF7 RPS) Reactor Protection 05 A4.05 - Ability to manually operate and/or monitor in the control room: Channel defeat controls.
(CFR: 41.7 / 45.5-45.8) 3.6 38
ES-401 7
Form ES-401-2 013 (SF2 ESFAS) Engineered Safety Features Actuation 02 02 K5.02 - Knowledge of the operational implications of the following concepts as they apply to the ESFAS: Safety system logic and reliability.
(CFR: 41.5 / 45.7)
A3.02 - Ability to monitor automatic operation of the ESFAS including: Operation of actuated equipment.
(CFR: 41.7 / 45.5) 2.9 4.1 39 40 022 (SF5 CCS) Containment Cooling 01 K1.01 - Knowledge of the physical connections and/or cause-effect relationships between the CCS and the following systems:
SWS/cooling system.
(CFR: 41.2-41.9 / 45.7-45.8) 3.5 41 025 (SF5 ICE) Ice Condenser 026 (SF5 CSS) Containment Spray 01 K2.01 - Knowledge of bus power supplies to the following: Containment spray pumps (CFR: 41.7) 3.4 42 039 (SF4S MSS) Main and Reheat Steam 04 K3.04 - Knowledge of the effect that a loss or malfunction of the MRSS will have on the following: MFW pumps.
(CFR: 41.7 / 45.6) 2.5 43 059 (SF4S MFW) Main Feedwater 19 K4.19 - Knowledge of MFW design feature(s) and/or interlock(s) which provide for the following: Automatic feedwater isolation of MFW.
(CFR: 41.7) 3.2 44 061 (SF4S AFW)
Auxiliary/Emergency Feedwater 01 K6.01 - Knowledge of the effect of a loss or malfunction of the following will have on the AFW components: Controllers and positioners.
(CFR: 41.7 / 45.7) 2.5 45 062 (SF6 ED AC) AC Electrical Distribution
- 02.
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) 3.2 46 063 (SF6 ED DC) DC Electrical Distribution 02 01 A1.01 - Ability to predict and/or monitor changes in parameters associated with operating the DC electrical system controls including: Battery capacity as it is affected by discharge rate.
(CFR: 41.5 / 45.5)
K4.02 - Knowledge of DC electrical system design feature(s) and/or interlock(s) which provide for the following: Breaker interlocks, permissives, bypasses and cross-ties.
(CFR: 41.7) 2.5 2.9 47 48 064 (SF6 EDG) Emergency Diesel Generator 02 16 A2.16 - Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of offsite power during full-load testing of ED/G (CFR: 41.5 / 43.5 / 45.3, 45.13)
K2.02 - Knowledge of bus power supplies to the following: Fuel oil pumps (CFR: 41.7) 3.3 2.8 49 50 073 (SF7 PRM) Process Radiation Monitoring 02 A4.02 - Ability to manually operate and/or monitor in the control room: Radiation monitoring system control panel.
(CFR: 41.7 / 45.5, 45.8) 3.7 51
ES-401 8
Form ES-401-2 076 (SF4S SW) Service Water
- 04.
46 G2.4.46 - Ability to verify that the alarms are consistent with the plant conditions.
(CFR: 41.10 / 43.5 / 45.12) 4.2 52 078 (SF8 IAS) Instrument Air 01 A3.01 - Ability to monitor automatic operation of the IAS, including: Air pressure.
(CFR: 41.7 / 45.5) 3.1 53 103 (SF5 CNT) Containment 02 03 K1.02 - Knowledge of the physical connections and/or cause-effect relationships between the containment system and the following systems: Containment isolation/containment integrity.
(CFR: 41.2-41.9 / 45.7-45.8)
K3.03 - Knowledge of the effect that a loss or malfunction of the containment system will have on the following: Loss of containment integrity under refueling operations.
(CFR: 41.7 / 45.6) 3.9 3.7 54 55 053 (SF1; SF4P ICS*) Integrated Control K/A Category Point Totals:
3 2
3 3
2 2
3 3
3 2
2 Group Point Total:
28
ES-401 9
Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 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 002 (SF2; SF4P RCS) Reactor Coolant 06 K6.06 - Knowledge of the effect or a loss or malfunction on the following RCS components:
Sensors and Detectors.
(CFR: 41.7 / 45.7) 2.5 56 011 (SF2 PZR LCS) Pressurizer Level Control 02 A1.02 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PZR LCS controls including: Charging and letdown flows.
(CFR: 41.5 / 45.5) 3.3 57 014 (SF1 RPI) Rod Position Indication 015 (SF7 NI) Nuclear Instrumentation 016 (SF7 NNI) Nonnuclear Instrumentation 04 A2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the NNIS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Voltage to instruments, both too high and too low.
(CFR: 41.5 / 43.5 / 45.3, 45.5) 2.5 58 017 (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 01 A3.01 - Ability to monitor automatic operation of the Containment Purge System including:
CPS isolation.
(CFR: 41.7 / 45.5) 3.8 59 033 (SF8 SFPCS) Spent Fuel Pool Cooling 034 (SF8 FHS) Fuel-Handling Equipment 035 (SF 4P SG) Steam Generator 03 K5.03 - Knowledge of the operational implications of the following concepts as they apply to the S/GS: Shrink and swell concept.
(CFR: 41.5 / 45.7) 2.8 60 041 (SF4S SDS) Steam Dump/Turbine Bypass Control 08 A4.08 - Ability to manually operate and/or monitor in the control room: Steam dump valves.
(CFR: 41.7 / 45.5, 45.8) 3.0 61 045 (SF 4S MTG) Main Turbine Generator 055 (SF4S CARS) Condenser Air Removal 04.
35 G2.4.35 - Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.
(CFR: 41.10 / 43.5 / 45.13) 3.8 62 056 (SF4S CDS) Condensate 03 K1.03 - Knowledge of the physical connections and/or cause-effect relationships between the Condensate System and the following systems: MFW (CFR: 41.2-41.9 / 45.7-45.8) 2.6 63 068 (SF9 LRS) Liquid Radwaste 071 (SF9 WGS) Waste Gas Disposal
ES-401 10 Form ES-401-2 072 (SF7 ARM) Area Radiation Monitoring 01 K3.01 - Knowledge of the effect that a loss or malfunction of the ARM system will have on the following: Containment ventilation isolation (CFR: 41.7 / 45.6) 3.3 64 075 (SF8 CW) Circulating Water 079 (SF8 SAS**) Station Air 086 Fire Protection 05 K4.05 - Knowledge of design feature(s) and/or interlock(s) which provide for the following:
Halon (CFR: 41.7) 3.0 65 050 (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 11 Form ES-401-2 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 04.
50 G2.4.50 - Ability to verify system alarm setpoints and operate controls identified in the alarm response manual.
(CFR: 41.10 / 43.5 / 45.3) 4.0 76 000008 (APE 8) Pressurizer Vapor Space Accident / 3 000009 (EPE 9) Small Break LOCA / 3 000011 (EPE 11) Large Break LOCA / 3 10 EA2.10 - Ability to determine or interpret the following as they apply to a Large Break LOCA:
Verification of adequate core cooling.
(CFR: 43.5 / 45.13) 4.7 77 000015 (APE 15) Reactor Coolant Pump Malfunctions / 4 000022 (APE 22) Loss of Reactor Coolant Makeup / 2 01.
30 G2.1.30 - Ability to locate and operate components, including local controls.
(CFR: 41.7 / 45.7) 4.0 78 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 07 EA2.07 - Ability to determine or interpret the following as they apply to a ATWS: Reactor trip breaker indicating lights.
(CFR: 43.5 / 45.13) 4.3 79 000038 (EPE 38) Steam Generator Tube Rupture / 3 000040 (APE 40; BW E05; CE E05; W E12)
Steam Line RuptureExcessive Heat Transfer / 4 000054 (APE 54; CE E06) Loss of Main Feedwater /4 000055 (EPE 55) Station Blackout / 6 04 EA2.04 - Ability to determine or interpret the following as they apply to a Station Blackout:
Instruments and controls operable with only dc battery power available.
(CFR: 43.5 / 45.13) 4.1 80 000056 (APE 56) Loss of Offsite Power / 6 000057 (APE 57) Loss of Vital AC Instrument Bus / 6 000058 (APE 58) Loss of DC Power / 6 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 (W E04) LOCA Outside Containment / 3 (W E11) Loss of Emergency Coolant Recirculation / 4
ES-401 12 Form ES-401-2 (BW E04; W E05) Inadequate Heat TransferLoss of Secondary Heat Sink / 4 04.
02 G2.4.2 - Knowledge of system setpoints, interlocks and automatic actions associated with EOP entry conditions.
(CFR: 41.7 / 45.7, 45.8) 4.6 81 K/A Category Totals:
0 0
0 0
3 3
Group Point Total:
6
ES-401 13 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 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 000001 (APE 1) Continuous Rod Withdrawal / 1 000003 (APE 3) Dropped Control Rod / 1 000005 (APE 5) Inoperable/Stuck Control Rod / 1 000024 (APE 24) Emergency Boration / 1 000028 (APE 28) Pressurizer (PZR) Level Control Malfunction / 2 04.
03 G2.4.3 - Ability to identify post-accident instrumentation.
(CFR: 41.6 / 45.4) 3.9 82 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 Vacuum / 4 02 AA2.02 - Ability to determine or interpret the following as they apply to the Loss of Condenser Vacuum: Conditions requiring reactor and/or turbine trip.
(CFR: 43.5 / 45.13) 4.1 83 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
- 04.
18 G2.4.18 - Knowledge of the specific bases for EOPs.
(CFR: 41.10 / 43.1 / 45.13) 4.0 84 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 02 EA2.2 - Ability to determine and interpret the following as they apply to the (Containment Flooding): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.
(CFR: 43.5 / 45.13) 3.3 85 (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 (BW E09; CE A13**; W E09 & E10) Natural Circulation/4 (BW E13 & E14) EOP Rules and Enclosures
ES-401 14 Form ES-401-2 (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:
0 0
0 0
2 2
Group Point Total:
4
ES-401 15 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 2/Group 1 (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 004 (SF1; SF2 CVCS) Chemical and Volume Control
- 02.
37 G2.2.37 - Ability to determine operability and/or availability of safety related equipment (CFR: 41.7 / 43.5 / 45.12) 4.6 86 005 (SF4P RHR) Residual Heat Removal 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 012 (SF7 RPS) Reactor Protection 07 A2.07 - Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of dc control power.
(CFR: 41.5 / 43.5 / 45.3, 45.5) 3.7 87 013 (SF2 ESFAS) Engineered Safety Features Actuation 022 (SF5 CCS) Containment Cooling 025 (SF5 ICE) Ice Condenser 026 (SF5 CSS) Containment Spray
- 02.
12 G2.2.12 - Knowledge of surveillance procedures.
(CFR: 41.10 / 45.13) 4.1 88 039 (SF4S MSS) Main and Reheat Steam 059 (SF4S MFW) Main Feedwater 061 (SF4S AFW)
Auxiliary/Emergency Feedwater 062 (SF6 ED AC) AC Electrical Distribution 10 A2.10 - Ability to (a) predict the impacts of the following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Effects of switching power supplies on instruments and controls.
(CFR: 41.5 / 43.5 / 45.3, 45.13) 3.3 89 063 (SF6 ED DC) DC Electrical Distribution 064 (SF6 EDG) Emergency Diesel Generator 073 (SF7 PRM) Process Radiation Monitoring 076 (SF4S SW) Service Water
ES-401 16 Form ES-401-2 078 (SF8 IAS) Instrument Air 01 A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the IAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Air dryer and filter malfunctions (CFR: 41.5 / 43.5 / 45.3, 45.13) 2.9 90 103 (SF5 CNT) Containment 053 (SF1; SF4P ICS*) Integrated Control K/A Category Point Totals:
0 0
0 0
0 0
0 3
0 0
2 Group Point Total:
5
ES-401 17 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant SystemsTier 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 Coolant 011 (SF2 PZR LCS) Pressurizer Level Control 014 (SF1 RPI) Rod Position Indication 01.
19 G2.1.19 - Ability to use plant computers to evaluate system or component status.
(CFR: 41.10 / 45.12) 3.8 91 015 (SF7 NI) Nuclear Instrumentation 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 Cooling 034 (SF8 FHS) Fuel-Handling Equipment 01 A1.01 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the Fuel Handling System controls including: Load limits.
(CFR: 41.5 / 45.5) 3.2 92 035 (SF 4P SG) Steam Generator 041 (SF4S SDS) Steam Dump/Turbine Bypass Control 045 (SF 4S MTG) Main Turbine Generator 17 A2.17 - Ability to (a) predict the impacts of the following malfunctions or operation on the MT/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Malfunction of electrohydraulic control.
(CFR: 41.5 / 43.5 / 45.3, 45.5) 2.9 93 055 (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:
0 0
0 0
0 0
1 1
0 0
1 Group Point Total:
3