ML14237A236
| ML14237A236 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/31/2014 |
| From: | Vincent Gaddy Operations Branch IV |
| To: | Entergy Operations |
| laura hurley | |
| References | |
| 50-368/14-07 50-368/OL-14 | |
| Download: ML14237A236 (30) | |
Text
ES-401 PWR Examination Outline Form ES-401-2 Facility: ANO2 Date of Exam: July 31, 2014 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4
- Total
- 1. 1 2 3 3 4 3 3 18 3 3 6 Emergency &
Abnormal 2 1 1 2 N/A 2 2 N/A 1 9 2 2 4 Plant Evolutions Tier Totals 4 4 5 5 5 4 27 5 5 10 1 4 2 2 2 2 2 2 4 4 2 2 28 3 2 5 2.
Plant 2 1 1 1 1 1 1 1 0 1 1 1 10 0 1 2 3 Systems Tier Totals 5 3 3 3 3 3 3 4 5 3 3 38 4 4 8
- 3. Generic Knowledge and Abilities 1 2 3 4 10 1 2 3 4 7 Categories 3 2 3 2 1 2 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 outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).
- 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 associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; 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 importance ratings (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 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.
Rev 3 1 of 23
ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 ( RO / SRO)
E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #
1 2 3 1 2 000007 (BW/E02&E10; CE/E02) Reactor X Ability to determine or interpret the 4.1 1 Trip - Stabilization - Recovery / 1 following as they apply to a reactor trip:
EA2.01 Decreasing power level, from available indications CFR 41.7 000008 Pressurizer Vapor Space X Knowledge of the reasons for the following 4.2 2 Accident / 3 responses as they apply to the Pressurizer Vapor Space Accident:
AK3.04 RCP tripping requirements CFR 41.5, 41.10 000009 Small Break LOCA / 3 X Knowledge of the interrelations between 3.0 3 the small break LOCA and the following:
EK2.03 S/Gs CFR 41.7 000011 Large Break LOCA / 3 X Ability to operate and monitor the 4.2 4 following as they apply to a Large Break LOCA:
EA1.06 D/Gs CFR 41.7 000015/17 RCP Malfunctions / 4 X Ability to determine and interpret the 3.4 5 following as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow):
AA2.08 When to secure RCPs on high bearing temperature CFR 41.10 000022 Loss of Rx Coolant Makeup / 2 X 2.4.45 Ability to prioritize and interpret the 4.1 6 significance of each annunciator or alarm.
CFR: 41.10 000025 Loss of RHR System / 4 X 2.1.20 Ability to interpret and execute 4.6 7 procedure steps CFR: 41.10 000026 Loss of Component Cooling X Ability to operate and/or monitor the 3.1 8 Water / 8 following as they apply to the Loss of Component Cooling Water:
(CFR 41.7 / 45.5 / 45.6)
AA1.01 CCW temperature indications Rev 3 2 of 23
ES-401 2 Form ES-401-2 000027 Pressurizer Pressure Control X Knowledge of the operational implications 2.8 9 System Malfunction / 3 of the following concepts as they apply to Pressurizer Pressure Control Malfunctions:
AK1.02 Expansion of liquids as temperature increases CFR 41.8 Knowledge of the interrelations between 000029 ATWS / 1 X 2.9 10 the and the following an ATWS:
(CFR 41.7 / 45.7)
EK2.06 Breakers, relays, and disconnects 000038 Steam Gen. Tube Rupture / 3 X Knowledge of the reasons for the following 4.1 11 responses as they apply to the SGTR:
EK3.09 Criteria for securing/throttling ECCS CFR 41.5, 41.10 000040 (BW/E05; CE/E05; W/E12) X Knowledge of the operational implications 4.1 12 Steam Line Rupture - Excessive Heat of the following concepts as they apply to Transfer / 4 Steam Line Rupture:
AK1.05 Reactivity effects of cooldown CFR 41.8, 41.10 000054 (CE/E06) Loss of Main X Ability to operate and/or monitor the 4.4 13 Feedwater / 4 following as they apply to the Loss of Main Feedwater (MFW):
AA1.02 Manual startup of electric and steam driven AFW pumps CFR 41.7 Knowledge of the reasons for the following 000055 Station Blackout / 6 X 4.3 14 responses as they apply to the Station Blackout:
(CFR 41.5 / 41.10 / 45.6 /45.13)
EK3.02 Actions contained in EOP for loss of offsite and onsite power 000056 Loss of Off-site Power / 6 X Ability to determine and interpret the 3.0 15 following as they apply to the Loss of Offsite Power:
AA2.75 CVCS makeup CFR: 41.4, 41.7 000057 Loss of Vital AC Inst. Bus / 6 X Ability to operate and / or monitor the 3.7 16 following as they apply to the Loss of Vital AC Instrument Bus:
AA1.01 Manual Inverter Swapping CFR 41.7 / 45.5 / 45.6 Rev 3 3 of 23
ES-401 2 Form ES-401-2 000058 Loss of DC Power / 6 X 2.1.23 Ability to perform specific system 4.3 17 and integrated plant procedures during all modes of plant operations.
CFR 41.10 000062 Loss of Nuclear Svc Water / 4 000065 Loss of Instrument Air / 8 W/E04 LOCA Outside Containment / 3 W/E11 Loss of Emergency Coolant Recirc. / 4 BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 000077 Generator Voltage and Electric X Knowledge of the interrelations between 3.9 18 Grid Disturbances / 6 Generator Voltage and Electric Grid Disturbances and the following:
(CFR: 41.4, 41.5, 41.7, 41.10 / 45.8)
AK2.07 Turbine / generator control K/A Category Totals: 2 3 3 4 3 3 Group Point Total: 18 Rev 3 4 of 23
ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 ( RO / SRO)
E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #
1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 X Ability to determine and interpret 4.5 19 the following as they apply to the Continuous Rod Withdrawal :
(CFR: 43.5 / 45.13)
AA2.03 Proper actions to be taken if automatic safety functions have not taken place 000003 Dropped Control Rod / 1 000005 Inoperable/Stuck Control Rod / 1 X Knowledge of the operational 3.2 20 implications of the following concepts as they apply to Inoperable/
Stuck Control Rod:
(CFR 41.8 / 41.10 / 45.3)
AK1.03 Xenon transient 000024 Emergency Boration / 1 X Knowledge of the reasons for the 4.2 21 following responses as they apply to Emergency Boration:
(CFR 41.5, 41.10 / 45.6 / 45.13)
AK3.02 Actions contained in EOP for emergency boration 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 000036 (BW/A08) Fuel Handling Accident / 8 000037 Steam Generator Tube Leak / 3 X Ability to operate and / or monitor 3.3 23 the following as they apply to the Steam Generator Tube Leak:
(CFR 41.7 / 45.5 / 45.6)
AA1.05 Radiation Monitor for auxiliary building exhaust processes 000051 Loss of Condenser Vacuum / 4 X Knowledge of the reasons for the 2.8 22 following responses as they apply to the Loss of Condenser Vacuum:
(CFR 41.5,41.10 / 45.6 / 45.13)
AK3.01 Loss of steam dump capability upon loss of condenser vacuum 000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8 000068 (BW/A06) Control Room Evac. / 8 000069 (W/E14) Loss of CTMT Integrity / 5 Rev 3 5 of 23
ES-401 3 Form ES-401-2 000074 (W/E06&E07) Inad. Core Cooling / 4 000076 High Reactor Coolant Activity / 9 X Knowledge of the interrelations 2.6 24 between the High Reactor Coolant Activity and the following:
(CFR 41.7 / 45.7)
AK2.01 Process radiation monitors W/EO1 & E02 Rediagnosis & SI Termination / 3 W/E13 Steam Generator Over-pressure / 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 - Depress. / 4 BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 BW/E13&E14 EOP Rules and Enclosures CE/A11; W/E08 RCS Overcooling - PTS / 4 X Ability to determine and interpret 3.0 25 the following as they apply to the (RCS overcooling)
(CFR: 43.5 / 45.13)
AA2.2 Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.
CE/A16 Excess RCS Leakage / 2 X 2.4.6 Knowledge of EOP mitigation 3.7 26 strategies. l (CFR: 41.10 / 43.5 / 45.13)
CE/E09 Functional Recovery X Ability to operate and / or monitor 3.6 27 the following as they apply to the (Functional Recovery)
(CFR: 41.7 / 45.5 / 45.6)
EA1.3 Desired operating results during abnormal and emergency situations.
K/A Category Point Totals: 1 1 2 2 2 1 Group Point Total: 9 Rev 3 6 of 23
ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)
System # / Name K K K K K K A A A A G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 Knowledge of the operational 003 Reactor Coolant Pump X 3.1 28 implications of the following concepts as they apply to the RCPS:
(CFR: 41.5 / 45.7)
K5.03 Effects of RCP shutdown on T-ave., including the reason for the unreliability of T-ave. in the shutdown loop Knowledge of the effect of a loss 004 Chemical and Volume X 3.1 29 Control or malfunction on the following CVCS components: (CFR: 41.7 /
45.7)
K6.01 Spray/heater combination in PZR to assure uniform boron concentration Knowledge of the physical 005 Residual Heat Removal X 3.5 30 connections and/or cause effect relationships between the RHRS and the following systems:
(CFR: 41.2 to 41.9 / 45.7 to 45.8)
K1.11 RWST Ability to (a) predict the impacts 006 Emergency Core Cooling X 3.9 31 of the following malfunctions or operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
(CFR: 41.5 / 45.5)
A2.13 Inadvertent SIS actuation Knowledge of the operational 007 Pressurizer Relief/Quench X 3.1 32 Tank implications of the following concepts as the apply to PRTS:
(CFR: 41.5 / 45.7)
K5.02 Method of forming a steam bubble in the PZR Rev 3 7 of 23
ES-401 4 Form ES-401-2 Knowledge of bus power supplies 008 Component Cooling Water X 3.0 33 to the following:
(CFR: 41.7)
K2.02 CCW pump, including emergency backup Ability to (a) predict the impacts 010 Pressurizer Pressure Control X 3.3 34 of the following malfunctions or operations on the PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
(CFR: 41.5 / 43.5 / 45.3 / 45.13)
A2.01 Heater failures 2.1.32 Ability to explain and 012 Reactor Protection X 3.8 35 apply system limits and precautions.
(CFR: 41.10 / 43.2 / 45.12)
Knowledge of the effect that a 013 Engineered Safety Features X 4.4 36 Actuation loss or malfunction of the ESFAS will have on the following:
(CFR: 41.7 / 45.6)
K3.01 Fuel Ability to manually operate 022 Containment Cooling X 3.8 37 and/or monitor in the control room:
(CFR: 41.7 / 45.5 to 45.8)
A4.05 Containment readings of temperature, pressure, and humidity system 025 Ice Condenser Ability to predict and/or monitor 026 Containment Spray X 2.7 38 changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including:
(CFR: 41.5 / 45.5)
A1.06 Containment spray pump cooling Knowledge of the physical 039 Main and Reheat Steam X 2.7 39 connections and/or cause-effect relationships between the MRSS and the following systems:
(CFR: 41.2 to 41.9 / 45.7 to 45.8)
K1.08 MFW Rev 3 8 of 23
ES-401 4 Form ES-401-2 Ability to (a) predict the impacts 059 Main Feedwater X 3.1 40 of the following malfunctions or operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
(CFR: 41.5 / 43.5 / 45.3 / 45.13)
A2.12 Failure of feedwater regulating valves Knowledge of AFW design 061 Auxiliary/Emergency X 4.5 41 Feedwater feature(s) and/or interlock(s) which provide for the following:
(CFR: 41.7)
K4.02 AFW automatic start upon loss of MFW pump, S/G level, blackout, or safety injection Knowledge of bus power supplies 062 AC Electrical Distribution X 3.3 42 to the following:
(CFR: 41.7)
K2.01 Major system loads Ability to monitor automatic 063 DC Electrical Distribution X 2.7 43 operation of the DC electrical system, including:
(CFR: 41.7 / 45.5)
A3.01 Meters, annunciators, dials, recorders, and indicating lights Knowledge of the effect of a loss 064 Emergency Diesel Generator X 3.2 44 or malfunction of the following will have on the ED/G system:
(CFR: 41.7 / 45.7)
K6.08 Fuel oil storage tanks Ability to manually operate 073 Process Radiation X 3.9 45 Monitoring and/or monitor in the control room:
(CFR: 41.7 / 45.5 to 45.8)
A4.01 Effluent release Knowledge of the effect that a 076 Service Water X 3.7 46 loss or malfunction of the SWS will have on the following:
(CFR: 41.7 / 45.6)
K3.07 ESF loads Rev 3 9 of 23
ES-401 4 Form ES-401-2 Knowledge of the physical 078 Instrument Air X 3.4 47 connections and/or cause-effect relationships between the IAS and the following systems:
(CFR: 41.2 to 41.9 / 45.7 to 45.8)
K1.05 MSIV air Ability to monitor automatic 103 Containment X 3.9 48 operation of the containment system, including:
(CFR: 41.7 / 45.5)
A3.01 Containment isolation Ability to predict and/or monitor 003 Reactor Coolant Pump X 2.6 49 changes in parameters (to prevent exceeding design limits) associated with operating the RCPS controls including:
(CFR: 41.5 / 45.5)
A1.03 RCP motor stator winding temperatures Ability to monitor automatic 004 Chemical and Volume X 3.8 50 Control operation of the CVCS, including:
(CFR: 41.7 / 45.5)
A3.15 PZR pressure and temperature Ability to (a) predict the impacts 012 Reactor Protection X 3.6 51 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:
(CFR: 41.5 / 43.5 / 45.3 / 45.5)
A2.02 Loss of instrument power Knowledge of the physical 061 Auxiliary/Emergency X 3.9 52 Feedwater connections and/or causeeffect relationships between the AFW and the following systems:
(CFR: 41.2 to 41.9 / 45.7 to 45.8)
K1.04 RCS Rev 3 10 of 23
ES-401 4 Form ES-401-2 2.4.34 Knowledge of RO tasks 064 Emergency Diesel Generator X 4.2 53 performed outside the main control room during an l emergency and the resultant operational effects. l (CFR: 41.10 / 43.5 / 45.13)
Ability to monitor automatic 078 Instrument Air X 3.1 54 operation of the IAS, including:
(CFR: 41.7 / 45.5)
A3.01 Air pressure Knowledge of ECCS design 006 Emergency Core Cooling X 3.2 55 feature(s) and/or interlock(s) which provide for the following:
(CFR: 41.7)
K4.16 Interlocks between RHR valves and RCS K/A Category Point Totals 4 2 2 2 2 2 2 4 4 2 2 Group Point Total 28 Rev 3 11 of 23
ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)
System # / Name K K K K K K A A A A G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 Knowledge of bus power supplies to 001 Control Rod Drive X 3.5 56 the following:
(CFR: 41.7)
K2.01 One-line diagram of power supply to M/G sets Knowledge of RCS design feature(s) 002 Reactor Coolant X 3.8 57 and/or interlock(s) which provide for the following:
(CFR: 41.7)
K4.05 Detection of RCS leakage Knowledge of the operational 011 Pressurizer Level Control X 2.7 58 implications of the following concepts as they apply to the PZR LCS:
(CFR: 41.5 / 45.7)
K5.12 Criteria and purpose of PZR level program 014 Rod Position Indication 015 Nuclear Instrumentation X Ability to monitor automatic 3.3 59 operation of the NIS, including:
(CFR: 41.7 / 45.5)
A3.04 Maximum disagreement allowed between channels Knowledge of the effect that a loss 016 Non-nuclear Instrumentation X 3.5 60 or malfunction of the NNIS will have on the following:
(CFR: 41.7 / 45.6)
K3.06 AFW system 017 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 2.4.31 Knowledge of annunciator 033 Spent Fuel Pool Cooling X 4.2 61 alarms, indications, or response procedures.
(CFR: 41.10 / 45.3) 034 Fuel Handling Equipment Rev 3 12 of 23
ES-401 5 Form ES-401-2 Knowledge of the physical 035 Steam Generator X 3.7 62 connections and/or cause-effect relationships between the S/GS and the following systems:
(CFR: 41.2 to 41.9 / 45.7 to 45.8)
K1.12 RPS Ability to predict and/or monitor 041 Steam Dump/Turbine X 3.1 63 Bypass Control changes in parameters (to prevent exceeding design limits) associated with operating the SDS controls including:
(CFR: 41.5 / 45.5)
A1.02 Steam pressure Ability to manually operate and/or 045 Main Turbine Generator X 2.8 64 monitor in the control room:
(CFR: 41.7 / 45.5 to 45.8)
A4.06 Turbine stop valves 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air Knowledge of the effect of a loss or 086 Fire Protection X 2.6 65 malfunction on the Fire Protection System following will have on the :
(CFR: 41.7 / 45.7)
K6.04 Fire, smoke, and heat detectors K/A Category Point Totals: 1 1 1 1 1 1 1 0 1 1 1 Group Point Total: 10 Rev 3 13 of 23
ES-401 2 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO)
E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #
1 2 3 1 2 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery / 1 000008 Pressurizer Vapor Space Accident / 3 Ability to determine or interpret the 000009 Small Break LOCA / 3 X 3.5 76 following as they apply to a small break LOCA:
(CFR 43.5 / 45.13)
EA2.02 Possible leak paths 000011 Large Break LOCA / 3 000015/17 RCP Malfunctions / 4 000022 Loss of Rx Coolant Makeup / 2 000025 Loss of RHR System / 4 000026 Loss of Component Cooling Water / 8 000027 Pressurizer Pressure Control System Malfunction / 3 000029 ATWS / 1 000038 Steam Gen. Tube Rupture / 3 X Ability to determine or interpret the 4.2 78 following as they apply to a SGTR:
(CFR 43.5 / 45.13)
EA2.09 Existence of natural circulation, using plant parameters 2.1.7 Ability to evaluate plant performance 000040 (BW/E05; CE/E05; W/E12) X 4.7 79 Steam Line Rupture - Excessive Heat and make operational judgments based on Transfer / 4 operating characteristics, reactor behavior, and instrument interpretation.
(CFR: 41.5 / 43.5 / 45.12 / 45.13) 2.4.6 Knowledge of EOP mitigation 000054 (CE/E06) Loss of Main X 4.7 80 Feedwater / 4 strategies.
(CFR: 41.10 / 43.5 / 45.13) 2.1.32 Ability to explain and apply system 000055 Station Blackout / 6 X 4.0 81 limits and precautions.
(CFR: 41.10 / 43.2 / 45.12) 000056 Loss of Off-site Power / 6 000057 Loss of Vital AC Inst. Bus / 6 000058 Loss of DC Power / 6 Rev 3 14 of 23
ES-401 2 Form ES-401-2 000062 Loss of Nuclear Svc Water / 4 X Ability to determine and interpret the 3.6 77 following as they apply to the Loss of Nuclear Service Water:
(CFR 43.5 / 45.13)
AA2.02 The cause of possible SWS loss 000065 Loss of Instrument Air / 8 W/E04 LOCA Outside Containment / 3 W/E11 Loss of Emergency Coolant Recirc. / 4 BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 000077 Generator Voltage and Electric Grid Disturbances / 6 K/A Category Totals: 3 3 Group Point Total: 6 Rev 3 15 of 23
ES-401 3 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)
E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #
1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod / 1 X 2.1.23 Ability to perform specific 4.4 82 system and integrated plant procedures during all modes of plant operation.
(CFR: 41.10 / 43.5 / 45.2 / 45.6) 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 000036 (BW/A08) Fuel Handling Accident / 8 000037 Steam Generator Tube Leak / 3 X Ability to determine and interpret 4.3 83 the following as they apply to the Steam Generator Tube Leak:
(CFR: 43.5 / 45.13)
AA2.16 Pressure at which to maintain RCS during S/G cooldown 000051 Loss of Condenser Vacuum / 4 X 2.4.46 Ability to verify that the 4.2 84 alarms are consistent with the plant conditions.
(CFR: 41.10 / 43.5 / 45.3 / 45.12) 000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8 X Ability to determine and interpret 3.5 85 the following as they apply to the Plant Fire on Site:
(CFR: 43.5 / 45.13)
AA2.03 Fire alarm 000068 (BW/A06) Control Room Evac. / 8 000069 (W/E14) Loss of CTMT Integrity / 5 000074 (W/E06&E07) Inad. Core Cooling / 4 000076 High Reactor Coolant Activity / 9 W/EO1 & E02 Rediagnosis & SI Termination / 3 W/E13 Steam Generator Over-pressure / 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 Rev 3 16 of 23
ES-401 3 Form ES-401-2 BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8 BW/E03 Inadequate Subcooling Margin / 4 BW/E08; W/E03 LOCA Cooldown - Depress. / 4 BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 BW/E13&E14 EOP Rules and Enclosures CE/A11; W/E08 RCS Overcooling - PTS / 4 CE/A16 Excess RCS Leakage / 2 CE/E09 Functional Recovery K/A Category Point Totals: 2 2 Group Point Total: 4 Rev 3 17 of 23
ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO)
System # / Name K K K K K K A A A A G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 Ability to (a) predict the impacts 003 Reactor Coolant Pump X 3.9 86 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:
(CFR: 41.5 / 43.5/ 45.3 / 45/13)
A2.02 Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP 004 Chemical and Volume Control 2.2.25 Knowledge of the bases in 005 Residual Heat Removal X 4.2 87 Technical Specifications for limiting conditions for operations and safety limits.
(CFR: 41.5 / 41.7 / 43.2) 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank Ability to (a) predict the impacts 008 Component Cooling Water X 2.8 88 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:
(CFR: 41.5 / 43.5 / 45.3 / 45.13)
A2.09 Results of excessive exit temperature from the letdown cooler, including the temperature effects on ion-exchange resins 010 Pressurizer Pressure Control 012 Reactor Protection 013 Engineered Safety Features Actuation 022 Containment Cooling 025 Ice Condenser Rev 3 18 of 23
ES-401 4 Form ES-401-2 Ability to (a) predict the impacts 026 Containment Spray X 3.9 89 of the following malfunctions or operations on the CSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
(CFR: 41.5 / 43.5 / 45.3 / 45.13)
A2.07 Loss of containment spray pump suction when in recirculation mode, possibly caused by clogged sump screen, pump inlet high temperature exceeded cavitation, voiding), or sump level below cutoff (interlock) limit 039 Main and Reheat Steam 059 Main Feedwater 2.4.23 Knowledge of the bases for 061 Auxiliary/Emergency X 4.4 90 Feedwater prioritizing emergency procedure implementation During emergency operations.
(CFR: 41.10 / 43.5 / 45.13) 062 AC Electrical Distribution 063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Monitoring 076 Service Water 078 Instrument Air 103 Containment K/A Category Point Totals: 3 2 Group Point Total: 5 Rev 3 19 of 23
ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (SRO)
System # / Name K K K K K K A A A A G K/A Topic(s) IR #
1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive 002 Reactor Coolant 011 Pressurizer Level Control 014 Rod Position Indication Ability to (a) predict the impacts of 015 Nuclear Instrumentation X 3.9 91 the following malfunctions or operations on the NIS; and (b based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:
(CFR: 41.5 / 43.5 / 45.3 / 45.5)
A2.01 Power supply loss or erratic operation 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 2.2.25 Knowledge of the bases in 033 Spent Fuel Pool Cooling X 4.2 92 Technical Specifications for limiting conditions for operations and safety limits.
(CFR: 41.5 / 41.7 / 43.2) 2.1.42 Knowledge of new and spent 034 Fuel Handling Equipment X 3.4 93 fuel movement procedures.
(CFR: 41.10 / 43.7 / 45.13) 035 Steam Generator 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water Rev 3 20 of 23
ES-401 5 Form ES-401-2 079 Station Air 086 Fire Protection K/A Category Point Totals: 1 2 Group Point Total: 3 Rev 3 21 of 23
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: ANO-2 Date of Exam: July 31, 2014 Category K/A # Topic RO SRO-Only IR # IR #
2.1. 2.1.26 Knowledge of industrial safety procedures 3.4 66 (such as rotating equipment, electrical, high
of Operations (CFR: 41.10 / 45.12) 2.1. 2.1.3 Knowledge of shift or short-term relief turnover 3.7 67 practices.
(CFR: 41.10 / 45.13) 2.1. 2.1.4 Knowledge of individual licensed operator 3.3 68 responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.l (CFR: 41.10 / 43.2) 2.1. 2.1.37 Knowledge of procedures, guidelines, or 4.6 94 limitations associated with reactivity management.
(CFR: 41.1 / 43.6 / 45.6) 2.1.
2.1.
Subtotal 3 1 2.2. 2.2.13 Knowledge of tagging and clearance 4.1 69 procedures.
(CFR: 41.10 / 45.13) 2.
2.2. 2.2.37 Ability to determine operability and/or 3.6 70 Equipment Control availability of safety related equipment.
(CFR: 41.7 / 43.5 / 45.12) 2.2. 2.2.42 Ability to recognize system parameters that are 4.6 95 entry-level conditions for Technical Specifications.
(CFR: 41.7 / 41.10 / 43.2 / 43.3 / 45.3) 2.2. 2.2.20 Knowledge of the process for managing 3.8 96 troubleshooting activities.
(CFR: 41.10 / 43.5 / 45.13) 2.2.
2.2.
Subtotal 2 2 Rev 3 22 of 23
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 2.3. 2.3.5 Ability to use radiation monitoring systems, 2.9 71 such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment,
- 3. etc.
Radiation (CFR: 41.11 / 41.12 / 43.4 / 45.9)
Control 2.3.14 Knowledge of radiation or contamination 2.3. 3.4 72 hazards that may arise during normal, abnormal, or emergency conditions or activities.
(CFR: 41.12 / 43.4 / 45.10) 2.3. 2.3.12 Knowledge of radiological safety principles 3.2 73 pertaining to licensed operator 0 duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.
(CFR: 41.12 / 45.9 / 45.10) 2.3. 2.3.11 Ability to control radiation releases. 4.3 97 (CFR: 41.11 / 43.4 / 45.10) 2.3. 2.3.6 Ability to approve release permits. 3.8 98 (CFR: 41.13 / 43.4 / 45.10) 2.3.
Subtotal 3 2 2.4. 2.4.6 Knowledge of EOP mitigation strategies. 3.7 74 (CFR: 41.10 / 43.5 / 45.13)
- 4. 2.4.32 Knowledge of operator response to loss of all Emergency 2.4. 3.6 75 annunciators.
Procedures /
Plan (CFR: 41.10 / 43.5 / 45.13) 2.4. 2.4.20 Knowledge of the operational implications of 4.3 99 EOP warnings, cautions, and notes.
(CFR: 41.10 / 43.5 / 45.13) 2.4. 2.4.16 Knowledge of EOP implementation hierarchy 4.4 100 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) 2.4.
2.4.
Subtotal 2 2 Tier 3 Point Total 10 10 7 7 Rev 3 23 of 23
ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Selected Reason for Rejection Group K/A Although a different K/A, this is redundant to the K/A selection for Q48 011 Large Break LOCA (Ability to monitor automatic operation of the containment system, including:
Ability to operate and A3.01 Containment isolation).
1/1 monitor the following as Chose this K/A to replace due to no other A3 to choose from in the RO they apply to a Large Containment System list and maintain tier/group K/A balance.
Q4 Break LOCA:
EA1.07 Containment Replaced with isolation system EA1.06 D/Gs 032 Loss of Source Range NI Knowledge of the This K/A was used on the first exam for these applicants. Bank question reasons for the choices are limited on the topic without overlap.
1/2 following responses as No other credible AK3 choices available so another E/APE in the tier/group RO they apply to the Loss of was selected to maintain the AK3 count.
Q22 Source Range Nuclear Instrumentation: Replaced with 051 Loss of Condenser Vacuum AK3.01 Startup AK3.01 Loss of steam dump capability upon loss of condenser vacuum termination on source-range loss 010 Pressurizer Pressure Control Ability to (a) predict the impacts of the following malfunctions or 2/1 operations on the PZR PORVs are not applicable to ANO Unit 2.
RO PCS; and (b) based on Q34 those predictions, use Replaced with procedures to correct, A2.01 Heater Failures control, or mitigate the consequences of those malfunctions or operations:
A2.03 PORV failures 059 Main Feedwater Ability to (a) predict the impacts of the following malfunctions or operations on the MFW; 2/1 Due to ANO Unit 2 S/G system design, this is not an expected malfunction and (b) based on those with a mitigation strategy for MFW.
RO predictions, use Q40 procedures to correct, Replaced with control, or mitigate the A2.12 Failure of feedwater regulating valves consequences of those malfunctions or operations:
A2.04 Feeding a dry S/G Rev 2 1 of 5
ES-401 Record of Rejected K/As Form ES-401-4 078 Instrument Air Knowledge of the 2/1 physical connections ANO Unit 2 design does not have an IAS to Service Air interface.
RO and/or cause-effect relationships between Replaced with Q47 K1.05 MSIV air the IAS and the following systems:
K1.02 Service air 033 Spent Fuel Pool Cooling Generic K/A 2.4.49 There are no Immediate actions (as defined by plant procedures) associated 2/2 with the Spent Fuel Pool Cooling system.
Ability to perform RO without reference to Replaced with Q61 procedures those G 2.4.31 Knowledge of annunciator alarms, indications, or response actions that require procedures immediate operation of system components and controls.
Ability to determine and interpret the following Rejected for balance due to over sampling of RCP system/malfunction K/As as they apply to the when combined with the RO section. Replaced with an un-sampled E/APE 1/1 Reactor Coolant Pump in the same tier/group. Randomly selected from the AA2 K/A section to preserve the tier profile.
SRO Malfunctions (Loss of Q77 RC Flow): Replaced with 0062 Loss of Nuclear Svc Water AA2.07 Calculation of AA2.02 The cause of possible SWS loss expected values of flow in the loop with RCP secured 054 Loss of Main Feedwater Generic K/A 2.4.49 1/1 There are no Immediate actions (as defined by plant procedures) associated Ability to perform with Loss of Main Feedwater.
SRO without reference to Q80 procedures those Replaced with actions that require G 2.4.6 Knowledge of EOP mitigation strategies.
immediate operation of system components and controls.
Rev 2 2 of 5
ES-401 Record of Rejected K/As Form ES-401-4 026 Containment Spray Ability to (a) predict the impacts of the following malfunctions or operations on the CSS; ANO Unit 2 has a passive chemical mixing system associated with 2/1 and (b) based on those containment spray. K/A is not applicable.
SRO predictions, use procedures to correct, Replaced with Q89 A2.07 Loss of containment spray pump suction when in recirculation mode, control, or mitigate the possibly caused by clogged sump screen, pump inlet high temperature consequences of those exceeded cavitation, voiding), or sump level below cutoff (interlock) limit malfunctions or operations:
A2.05 Failure of chemical addition tanks to inject Tier 3 2.2.14 Knowledge of the Over sampling of category 2.2 and none selected for 2.1 for the SRO exam.
SRO process for controlling Q94 equipment configuration Replaced with or status. 2.1.36 Knowledge of procedures and limitations involved in core alterations.
037 Steam Generator Tube Leak Ability to operate and /
SG depressurization rates not applicable to ANO Unit 2 mitigation and 1/2 or monitor the following control strategy. Reselected from remaining AA1 K/As in the same system.
RO as they apply to the Q23 Steam Generator Tube Replaced with Leak: AA1.05 Radiation Monitor for auxiliary building exhaust processes AA1.01 Maximum controlled depressurization rate for affected S/G 003 Reactor Coolant Pump Ability to predict and/or monitor changes in K/A is redundant to topic for Q5. Reselected from the remaining A1 K/As in 2/1 parameters (to prevent the same system.
RO exceeding design limits)
Q49 associated with Replaced with operating the RCPS A1.03 RCP motor stator winding temperatures controls including:
A1.02 RCP pump and motor bearing temperatures 028 Pressurizer Level Malfunction Over sampling of PZR system topics over entire exam. Reselected from Tier Ability to determine and 1 Group 2 systems that were not selected for SRO but remained in the AA2 1/2 interpret the following K/A topic to keep outline profile.
SRO as they apply to the Q83 Replaced with Pressurizer Level 037 Steam Generator Tube Leak Control Malfunction: AA2.16 Pressure at which to maintain RCS during S/G cooldown AA2.08 PZR level as a function of power level Rev 2 3 of 5
ES-401 Record of Rejected K/As Form ES-401-4 003 Reactor Coolant Pump Ability to (a) predict the impacts of the following malfunctions or operations on the Limited applicability to ANO Unit 2 inhibits quality question development.
2/1 RCPS; and (b) based on Reselected from remaining A2 K/As in the RCP system.
SRO those predictions, use procedures to correct, Replaced with Q86 A2.02 Conditions which exist for an abnormal shutdown of an RCP in control, or mitigate the comparison to a normal shutdown of an RCP consequences of those malfunctions or operations:
A2.05 Effects of VCT pressure on RCP seal leakoff flows 055 Station Blackout Knowledge of the Limited options for question construction that is above difficulty of 1. No other viable options in the K1 list without over sampling on natural circulation operational implications 1/1 questions. Reselected from the K3 area.
of the following RO concepts as they apply Replaced with:
Q14 to the Station Blackout: Knowledge of the reasons for the following responses as they apply to the Station Blackout:
EK1.01 Effect of battery EK3.02 Actions contained in EOP for loss of offsite and onsite power discharge rates on capacity 057 Loss of Vital AC Instrument Bus Knowledge of the Difficulty constructing a discriminating, quality question. No other K3 reasons for the statements to choose from. Reselected from the A1 category in the same 1/1 following responses as topic.
RO they apply to the Loss of Replaced with:
Q16 Vital AC Instrument Bus: Ability to operate and / or monitor the following as they apply to the Loss of Vital AC Instrument Bus:
AK3.01 Actions contained AA1.01 Manual Inverter Swapping in EOP for loss of vital ac electrical instrument bus 039 Main and Reheat Steam Knowledge of the Plant design limits applicability to atmospheric relief dump valves outside of 1/2 physical connections SDBCS which is already addressed in Tier 2. Reselected within the K1 and/or cause-effect group.
RO Q39 relationships between Replaced with:
the MRSS and the K1.08 MFW following systems:
K1.02 Atmospheric relief dump valves Rev 2 4 of 5
ES-401 Record of Rejected K/As Form ES-401-4 2.1.36 Knowledge of The K/A for this question was rejected for the original outline submittal but 3 procedures and the wrong replacement K/A was entered in the revised sample plan and limitations involved in rejection record.
SRO Q94 core alterations.
Replaced with:
2.1.37 Rev 2 5 of 5
ES-301 Administrative Topics Outline Form ES-301-1 Facility: Arkansas Nuclear One Unit 2 Date of Examination: July 2014 Examination Level: RO SRO X Operating Test Number: 2014-2 Administrative Topic Type Describe activity to be performed (see Note) Code*
Determine if COLR DNBR limit is being met during a loss of COLSS and what action is required.
A1. Conduct of Operations D/R ANO-2-JPM-NRC-ADMIN-DNBRL 2.1.25 SRO (4.2)
Apply Steam Generator Chemistry limits A2. Conduct of Operations N/R ANO-2-JPM-NRC-ADMIN-SGCHEM 2.1.34 SRO (3.5)
Apply Tech Specs.
A3. Equipment Control D/R ANO-2-JPM-NRC-ADMIN-EDGTS 2.2.37 SRO (4.6)
Administration of Potassium Iodide.
A4. Radiation Control M/R ANO-2-JPM-NRC-ADMIN-KI2 2.3.14 SRO (3.8)
Determine Emergency Action Level A5. Emergency M/R ANO-2-JPM-NRC-ADMIN- EAL13 Procedures/Plan 2.4.41 SRO (4.6)
NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.
- Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank ( 3 for ROs; 4 for SROs & RO retakes)
(N)ew or (M)odified from bank ( 1)
(P)revious 2 exams ( 1; randomly selected)
Revision 0
ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Arkansas Nuclear One Unit 2 Date of Examination: July 2014 Exam Level: RO SRO-I SRO-U X Operating Test No.: 2014-2 Control Room Systems@ (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF)
System / JPM Title Type Code* Safety Function S1. ANO-2-JPM-NRC-AOP2 5 022 A4.04 RO-3.1/SRO-3.2 D/EN/S Containment Reset CIAS and restore cooling water to containment S2. ANO-2-JPM-NRC-AOP5 3 027 AA1.01 RO-4.0/SRO-3.9 A/N/S Pressure Control Respond to a failed close PZR spray valve S3. ANO-2-JPM-NRC-RCP02 4 003 A4.08 RO-3.2/SRO-2.9 A/D/S RCS Heat Removal Restore component cooling water to reactor coolant pumps S4.
S5.
S6.
S7.
S8.
In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)
P1. ANO-2-JPM-AACFO 6 064 K1.03 RO-3.6/SRO-4.0 A/D/E/L Control AAC diesel fuel oil day tank level manually. Electrical P2. ANO-2-JPM-NRC-FPEM1 8 033 A2.03 RO-3.1/SRO-3.5 E/L/P/R Plant service Perform emergency SW make up to SFP systems P3.
@ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.
- Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 (C)ontrol room (D)irect from bank 9/ 8/ 4 (E)mergency or abnormal in-plant 1/ 1/ 1 (EN)gineered safety feature - / - / 1 (control room system)
(L)ow-Power / Shutdown 1/ 1/ 1 (N)ew or (M)odified from bank including 1(A) 2/ 2/ 1 (P)revious 2 exams 3 / 3 / 2 (randomly selected)
(R)CA 1/ 1/ 1 (S)imulator Revision 1