ML030340541

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Retake Exam - 07/2002- Final Outline
ML030340541
Person / Time
Site: Waterford Entergy icon.png
Issue date: 05/23/2002
From: Gody A
Division of Reactor Safety IV
To: Venable J
Entergy Operations
References
50-382/02-302 50-382/02-302
Download: ML030340541 (16)
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Text

ES-401 PWR RO Examination Outline Form ES-401-4 Facility: Waterford 3 Date of Exam: July 29, 2002 Exam level: RO Tier Group K/A Category Points Point Total K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G*

1. 1 2 2 3 4 3 2 16 Emergency & 2 3 3 5 2 3 1 17 Abnormal Plant 3 1 0 1 0 1 0 3 Evolutions Tier Totals 6 5 9 6 7 3 36
2. 1 4 2 2 3 3 2 1 2 2 1 1 23 Plant 2 2 1 1 4 0 2 2 3 2 1 2 20 Systems 3 1 0 1 0 1 0 0 2 2 0 1 8 Tier Totals 7 3 4 7 4 4 3 7 6 2 4 51 Cat 1 Cat 2 Cat 3 Cat 4
3. Generic Knowledge and Abilities 13 3 3 3 4 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., the Tier Totals in each K/A category shall not be less than two).
2. Actual point totals must match those specified in the table.
3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
4. Systems/evolutions within each group are identified on the associated outline.
5. The shaded areas are not applicable to the category/tier.
6. The generic 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.
7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the RO license level, and the point totals for each system and category.

K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.

NUREG-1021, Revision 8, Supplement 1

ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Points 000005 Inoperable/Stuck Control Rod / 1 X AK3.04 - Knowledge of the reasons for the following responses as they 3.4 1 apply to the Inoperable/Stuck Control Rod: Tech Spec Limits for inoperable rods. (CFR: 41.5, 41.10/45.6/45.13) 000015/17 RCP Malfunctions / I4 X AA1.22 - Ability to operate and/or monitor the following as they apply to 4.0 1 the Reactor Coolant Pump Malfunctions (Loss of RC Flow): RCP seal failure/malfunction (CFR: 41.7/45.5/45.6)

BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 X AK1.3 - Knowledge of the operational implications of the following 3.1 1 concepts as they apply to the (Natural Circulation Operations):

Annunciators and conditions indicating signals, and remedial actions associated with the (Natural Circulation Operations).

(CFR: 41.8/41.10/45.3) 000024 Emergency Boration / 1 X AA2.05 - Ability to determine and interpret the following as they apply to 3.3 1 the Emergency Boration: Amount of boron to add to achieve required SDM. (CFR: 43.5/45.13) 000026 Loss of Component Cooling Water / 8 X AK3.02 - Knowledge of the reasons for the following responses as they 3.6 1 apply to the Loss of Component Cooling Water: The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS. (CFR: 41.5/41.10/45.13) 000027 Pressurizer Pressure Control System Not used. N/A 0 Malfunction / 3 000040 (BW/E05; CE/E05; W/E12) Steam Line X AK1.07 - Knowledge of the operational implications of the following 3.4 1 Rupture - Excessive Heat Transfer / 4 concepts as they apply to Steam Line Rupture: Effects of feedwater introduction on dry S/G. (CFR: 41.8/41.10/45.3)

CE/A11; W/E08 RCS Overcooling - PTS / 4 X AK2.2 - Knowledge of the interrelations between the (RCS Overcooling) 3.2 1 and the following: Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and the relations between the proper operation of these systems to the operation of the facility. (CFR: 41.7/45.7) 000051 Loss of Condenser Vacuum / 4 X G2.4.11 - Emergency Procedures/Plan: Knowledge of abnormal 3.4 1 condition procedures. (CFR: 41.10/43.5/45.13) 000055 Station Blackout / 6 X EK3.02 - Knowledge of the reasons for the following responses as the 4.3 1 apply to the Station Blackout: Actions contained in EOP for loss of offsite and onsite power (CFR: 41.5/41.10/45.6/45.13) 000057 Loss of Vital AC Elec. Inst. Bus / 4 X AA2.03 - Ability to determine and interpret the following as they apply to 3.7 1 the Loss of Vital AC Instrument Bus: RPS panel alarm annunciators and trip indicators. (CFR: 43.5/45.13) 000062 Loss of Nuclear Service Water / 4 X AA1.02 - Ability to operate and/or monitor the following as they apply to 3.2 1 the Loss of Nuclear Service Water: Loads on the SWS in the control room. (CFR: 41.7/45.5/45.6)

NUREG-1021, Revision 8, Supplement 1

ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Points 000067 Plant Fire On-site / 9 X AA1.09 - Ability to operate and/or monitor the following as they apply to 3.0 1 the Plant Fire on Site: Plant fire zone panel (including detector location)

(CFR: 41.7/45.5/45.6) 000068 (BW/A06) Control Room Evac. / 8 X AK2.07 - Knowledge of interrelations between the Control Room 3.3 1 Evacuation and the following: ED/G (CFR: 41.7/45.7) 000069 (W/E14) Loss of CTMT Integrity / 5 X AA2.02 - Ability to determine and interpret the following as they apply to 3.9 1 the Loss of Containment Integrity: Verification of automatic and manual means of restoring integrity. (CFR: 43.5/45.13) 000074 (W/E06&E07) Inad. Core Cooling / 4 X EA1.12 - Ability to operate and monitor the following as they apply to a 4.1 1 Inadequate Core Cooling: RCS temperature and pressure indicators.

(CFR: 41.7/45.5/45.6)

BW/E03 Inadequate Subcooling Margin / 4 000076 High Reactor Coolant Activity / 9 X G2.2.25 - Equipment Control: Knowledge of bases in technical 2.5 1 specifications for limiting conditions for operations and safety limits.

(CFR: 43.2)

BW/A02&A03 Loss of NNI-X/Y / 7 K/A Category Totals: 2 2 3 4 3 2 Group Point Total: 16 NUREG-1021, Revision 8, Supplement 1

ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Points 000001 Continuous Rod Withdrawal / 1 X AK1.04 - Knowledge of the operational implications of the following 3.7 1 concepts as they apply to Continuous Rod Withdrawal: Effect of continuous rod withdrawal on insertion limits and SDM.

(CFR: 41.8/41.10/45.3) 000003 Dropped Control Rod / 1 X AA2.03 - Ability to determine and interpret the following as they apply to 3.6 1 the Dropped Control Rod: Dropped rod, using in-core/ex-core instrumentation, in-core or loop temperature instrumentation.

(CFR: 43.5/45.13) 000007 (BW/E02&E10; CE/E02) Reactor Trip - X EK3.01 - Knowledge of the reasons for the following as they apply to a 4.0 1 Stabilization - Recovery / 1 reactor trip: Actions contained in EOP for reactor trip.

(CFR: 41.5/41.10/45.6/45.13)

BW/A01 Plant Runback / 1 BW/A04 Turbine Trip / 4 000008 Pressurizer Vapor Space Accident / 3 X AK1.02 - Knowledge of the operational implications of the following 3.1 1 concepts as they apply to a Pressurizer Vapor Space Accident: Change in leak rate with change in pressure . (CFR: 41.8/41.10/45.3) 000009 Small Break LOCA / 3 X EK2.03 - Knowledge of the interrelations between the small break LOCA 3.0 1 and the following: S/Gs (CFR: 41.7/45.7) 000011 Large Break LOCA / 3 X EA2.13 - Ability to determine or interpret the following as they apply to a 3.7* 1 Large Break LOCA: Difference between overcooling and LOCA indications. (CFR: 43.5/45.13)

W/E04 LOCA Outside Containment / 3 BW/E08; W/E03 LOCA Cooldown/Depress. / 4 W/E11 Loss of Emergency Coolant Recirc. / 4 W/E02 SI Termination / 3 000022 Loss of Reactor Coolant Makeup / 2 X AA1.08 - Ability to operate and/or monitor the following as they apply to 3.4 1 the Loss of Reactor Coolant Pump Makeup: VCT level.

(CFR: 43.5/45.13) 000025 Loss of RHR System / 4 X AK2.02 - Knowledge of the interrelations between the Loss of Residual 3.2* 1 Heat Removal System and the following: LPI or Decay Heat Removal/RHR pumps. (CFR: 41.7/45.7) 000029 Anticipated Transient w/o Scram / 1 X EK3.10 - Knowledge of the reasons for the following responses as the 4.1 1 apply to the ATWS: Manual rod insertion. (CFR: 41.5/41.10/45.6/45.13) 000032 Loss of Source Range NI / 7 X AA1.01 - Ability to operate and/or monitor the following as they apply to 3.1* 1 the loss of source range instrumentation: Manual restoration of power.

(CFR: 41.7/45.5/45.6) 000033 Loss of Intermediate Range NI / 7 Not Used N/A 0 NUREG-1021, Revision 8, Supplement 1

ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Points 000037 Steam Generator Tube Leak / 3 X G2.3.11 - Radiation Control: Ability to control radiation releases. 2.7 1 (CFR: 45.9/45.10) 000038 Steam Generator Tube Rupture / 3 X EA2.09 - Ability to determine or interpret the following as they apply to a 4.2 1 SGTR: Existence of natural circulation using plant parameters.

(CFR: 43.5/45.13) 000054 (CE/E06) Loss of Main Feedwater / 4 X CE/EO6 EK2.1 - Knowledge of the interrelations between the (Loss of 3.3 1 Feedwater) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features. (CFR: 41.7/45.7)

BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 000058 Loss of DC Power / 6 X AK1.01 - Knowledge of the operational implications of the following 2.8 1 concepts as they apply to Loss of DC Power: Battery charger equipment and instrumentation. (CFR: 41.8/41.10/45.3))

000059 Accidental Liquid RadWaste Rel. / 9 Not Used N/A 0 000060 Accidental Gaseous Radwaste Rel. / 9 X AK3.01 - Knowledge of the reasons for the following responses as they 2.9 1 apply to the Accidental Gaseous Radwaste: Implementation of the E-Plan. (CFR: 41.5, 41.10/45.6/45.13) 000061 ARM System Alarms / 7 X AK3.02 - Knowledge of the reasons for the following responses as they 3.4 1 apply to the Area Radiation Monitoring (ARM) System Alarms:

Guidance contained in alarm response for ARM system.

(CFR: 41.5, 41.10/45.6/45.13)

W/E16 High Containment Radiation / 9 CE/E09 Functional Recovery X EK3.2 - Knowledge of the reason for the following responses as they 3.0 1 apply to the (Functional Recovery): Normal, abnormal and emergency operating procedures associated with (Functional Recovery).

(CFR: 41.5/41.10, 45.6, 45.13)

K/A Category Point Totals: 3 3 5 2 3 1 Group Point Total: 17 NUREG-1021, Revision 8, Supplement 1

ES-401 PWR RO Examination Outline Form ES-401-4 Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G K/A Topic(s) Imp. Points 000028 Pressurizer Level Malfunction / 2 X AK3.04 - Knowledge of the reasons for the following responses as they 2.9* 1 apply to the Pressurizer Level Control Malfunctions: Change in PZR level with power change, even though RCS T-ave. constant, due to loop size difference. (CFR: 41.5, 41.10/45.6/45.13) 000036 (BW/A08) Fuel Handling Accident / 8 Not Used N/A 0 000056 Loss of Off-site Power / 6 Not Used N/A 0 000065 Loss of Instrument Air / 8 X AA2.06 - Ability to determine and interpret the following as they apply to 3.6* 1 the Loss of Instrument Air: Whether to trip reactor if instrument air pressure is de-creasing. (CFR: 43.5/45.13)

BW/E13&E14 EOP Rules and Enclosures BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8 CE/A16 Excess RCS Leakage / 2 X AK1.3 - Knowledge of the operational implications of the following 3.2 1 concepts as they apply to the (Excess RCS Leakage): Annunicators and conditions indicating signals, and remedial action associated with the (Excess RCS Leakage). (CFR: 41.8/41.10/45.3)

W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5 K/A Category Point Totals: 1 0 1 0 1 0 Group Point Total: 3 NUREG-1021, Revision 8, Supplement 1

ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 1 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Points 001 Control Rod Drive X K4.01 - Knowledge of CRDS design 3.5 1 feature(s) and/or interlock(s) which provide for the following: Rod position indication.

(CFR: 41.7) 001 Control Rod Drive X K5.85 - Knowledge of the following 3.5 1 operational implications as they apply to the CRDS: Estimation of xenon reactivity based on time to reach peak xenon after trip/shutdown, approximate xenon reactivities after shutdown from various power levels, approximate xenon worth during the decay process following peak worth. (CFR: 41.5/45.7) 003 Reactor Coolant Pump X K6.04 - Knowledge of the effect of a loss or 2.8 1 malfunction on the following will have on the RCPS: Containment isolation valves affecting RCP operation. (CFR: 41.7/45.5) 004 Chemical and Volume Control X K3.06 - Knowledge of the effect that a loss 3.4 1 or malfunction of the CVCS will have on the following: RCS temperature and pressure.

(CFR: 41.7/45.6) 004 Chemical and Volume Control X A2.07 - Ability to (a) predict the impacts of 3.4 1 the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Isolation of letdown/makeup.

(CFR: 41.5/43.5/45.3/45.5) 013 Engineered Safety Features Actuation X K2.01 - Knowledge of bus power supplies to 3.6* 1 the following: ESFAS/safeguards equipment control. (CFR: 41.7) 013 Engineered Safety Features Actuation X A2.06 - Ability to (a) predict the impacts of 3.7* 1 the following malfunctions or operations on the ESFAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Inadvertent ESFAS actuation (CFR: 41.5/43.5/45.3/45.13) 015 Nuclear Instrumentation X K5.05 - Knowledge of the operational 4.1 1 implications of the following concepts as they apply to the NIS: Criticality and its indications. (CFR: 41.5/45.7)

NUREG-1021, Revision 8, Supplement 1

ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 1 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Points 015 Nuclear Instrumentation X A3.03 - Ability to monitor automatic 3.9 1 operation of the NIS, including: Verification of proper functioning/operability.

(CFR: 41.7/45.5) 017 In-core Temperature Monitor X K5.03 - Knowledge of the operational 3.7 1 implications of the following concepts as they apply to the ITM system: Indication of superheating. (CFR: 41.5/45.7) 022 Containment Cooling X K2.01 - Knowledge of the power supplies to 3.0* 1 the following: Containment Cooling fans (CFR: 41.7) 022 Containment Cooling X K4.04 - Knowledge of CCS design 2.8 1 feature(s) and/or interlocks which provide for the following: Cooling of control rod drive motors. (CFR: 41.7) 025 Ice Condenser 056 Condensate X K1.03 - Knowledge of the physical 2.6* 1 connections and/or cause-effect relationships between the Condensate System and the following systems: MFW (CFR: 41.2 to 41.9/45.7 to 45.8) 056 Condensate X G2.1.24 - Conduct of Operations: Ability to 2.8 1 obtain and interpret station electrical and mechanical drawings. (CFR: 45.12/45.13) 059 Main Feedwater X K4.16 - Knowledge of MFW design 3.1* 1 feature(s) and/or interlock(s) which provide the following: Automatic trips for MFW pumps. (CFR: 41.7) 059 Main Feedwater X A1.03 - Ability to predict and/or monitor 2.7* 1 changes in parameters (to prevent exceeding design limits) associated with operating the MFW controls including:

Power level restrictions for operation of MFW pumps and valves. (CFR: 41.5/45.5) 061 Auxiliary/Emergency Feedwater X K1.07 - Knowledge of the physical 3.6 1 connections and/or cause-effect relationships between the AFW and the following systems: Emergency water source. (CFR: 41.2 to 41.9/45.7 to 45.8) 061 Auxiliary/Emergency Feedwater X K6.02 - Knowledge of the effect of a loss or 2.6 1 malfunction of the following will have on the AFW components: Pumps (CFR: 41.7/45.7)

NUREG-1021, Revision 8, Supplement 1

ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 1 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Points 068 Liquid Radwaste X K1.02 - Knowledge of the physical 2.5 1 connections and/or cause effect relationships between the Liquid Radwaste System and the following systems: Waste Gas Vent Header.

(CFR: 41.2 to 41.9/45.7 to 45.8) 071 Waste Gas Disposal X K3.04 - Knowledge of the effect that a loss 2.7 1 or malfunction of the Waste Gas Disposal System will have on the following:

Ventilation system. (CFR: 41.7/45.6) 071 Waste Gas Disposal X A4.06 - Ability to manually operate and/or 2.8 1 monitor in the control room: Meteorological charts and recorders, along with the stop time and waste-gas release number.

(CFR: 41.7/45.5 to 45.8 )

072 Area Radiation Monitoring X K1.03 - Knowledge of the physical 3.6* 1 connection and/or cause effect relationship between the ARM system and the following systems: Fuel building isolation.

(CFR: 41.2 to 41.9/45.7 to 45.8) 072 Area Radiation Monitoring X A3.01 - Ability to monitor automatic 2.9* 1 operation of the ARM system, including:

Changes in ventilation alignment.

(CFR: 41.7/45.5)

K/A Category Point Totals: 4 2 2 3 3 2 1 2 2 1 1 Group Point Total: 23 NUREG-1021, Revision 8, Supplement 1

ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 2 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Points 002 Reactor Coolant X K6.02 - Knowledge of the effect or a loss or 3.6 1 malfunction on the following RCS components:

RCP. (CFR: 41.7/45.7) 006 Emergency Core Cooling X K4.21 - Knowledge of ECCS design feature(s) 4.1 1 and/or interlock(s) which provide for the following:

Bypassing/blocking ESF channels. (CFR: 41.7) 010 Pressurizer Pressure Control X K6.03 - Knowledge of the effect of a loss or 3.2 1 malfunction of the following will have on the PZR PCS: PZR sprays and heaters. (CFR: 41.7/45.7) 011 Pressurizer Level Control X A2.04 - Ability to (a) predict the impacts of the 3.5 1 following malfunctions or operations on the PZR LCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Loss of one, two or three charging pumps.

(CFR: 41.5/43.5/45.3/45.13) 011 Pressurizer Level Control X G2.4.1 - Emergency Procedures/Plan: 4.3 1 Knowledge of EOP entry conditions and immediate action steps. (CFR: 41.10/43.5/45.13) 012 Reactor Protection X A3.06 - Ability to monitor automatic operation of 3.7 1 the RPS, including: Trip logic. (CFR: 41.7/45.5) 014 Rod Position Indication X K4.03 - Knowledge of RPIS design feature(s) 3.2 1 and/or interlock(s) which provide for the following:

Rod bottom lights. (CFR: 41.5/45.7) 016 Non-nuclear Instrumentation X A2.01 - Ability to (a) predict the impacts of the 3.0 1 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:

Detector failure. (CFR: 41.5/43.5/45.3/45.5) 026 Containment Spray X A1.03 - Ability to predict and/or monitor changes 3.5 1 in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: Containment sump level.

(CFR: 41.5/45.5) 029 Containment Purge X K4.03 - Knowledge of design feature(s) and/or 2.9 1 interlocks which provide for the following:

Automatic Purge Isolation. (CFR: 41.7) 033 Spent Fuel Pool Cooling X K3.03 - Knowledge of the effect that a loss or 3.0 1 malfunction of the Spent Fuel Cooling System will have on the following: Spent Fuel Temperature.

(CFR: 41.7/45.6)

NUREG-1021, Revision 8, Supplement 1

ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 2 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Points 035 Steam Generator X K1.14 - Knowledge of the physical connections 3.9 1 and/or cause-effect relationships between the S/GS and the following systems: ESF.

(CFR: 41.2 to 41.9/45.7 to 45.8) 035 Steam Generator X A4.06 - Ability to manually operate and/or monitor 4.5 1 in the control room: S/G isolation on steam leak or tube rupture/leak. (CFR: 41.7/45.5 to 45.8) 039 Main and Reheat Steam X A2.04 - Ability to (a) predict the impacts of the 3.4 1 following malfunctions or operations on the MRSS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Malfunctioning steam dump.

(CFR: 41.5/43.5/45.3/45.13) 055 Condenser Air Removal Not Used N/A N/A 062 AC Electrical Distribution X K1.04 - Knowledge of the physical connection 3.7 1 and/or cause-effect relationship between the AC distribution system and the following systems: Off-site power sources. (CFR: 41.2 to 41.9) 063 DC Electrical Distribution X K2.01 - Knowledge of bus power supplies to the 2.9 1 following: Major DC Loads. (CFR: 41.7) 064 Emergency Diesel Generator X A3.01 - Ability to monitor automatic ED/G system, 4.1 1 including: Automatic start of compressor and ED/G. (CFR: 41.7/45.5) 073 Process Radiation Monitoring X K4.01 - Knowledge of PRM system design 4.0 1 feature(s) and/or interlock(s) which provide for the following: Release termination when radiation exceeds setpoint. (CFR: 41.7) 075 Circulating Water X G2.1.20 - Conduct of Operations: Ability to 4.3 1 execute procedure steps. (CFR: 41.10/43.5/45.12) 079 Station Air Not Used N/A N/A 086 Fire Protection X A1.03 - Ability to predict and/or monitor changes 2.7 1 in parameters (to prevent exceeding design limits) associated with the Fire Protection System operating the controls including: Fire doors.

(CFR: 41.5/45.5)

K/A Category Point Totals: 2 1 1 4 0 2 2 3 2 1 2 Group Point Total: 20 NUREG-1021, Revision 8, Supplement 1

ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 3 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Points 005 Residual Heat Removal X K5.01 - Knowledge of the operational 2.6 1 implications of the following concepts as they apply to RHRS: Nil ductility transition temperature (brittle fracture).

(CFR: 41.5/45.7) 007 Pressurizer Relief/Quench Tank X K3.01 - Knowledge of the effect that a loss 3.3 1 or malfunction of the PRTS will have on the following: Containment. (CFR: 41.7/45.6) 008 Component Cooling Water X A3.08 - Ability to monitor automatic 3.6* 1 operation of the CCWS, including:

Automatic actions associated with the CCWS that occur as a result of a safety injection signal. (CFR: 41.7/45.5) 027 Containment Iodine Removal Not Used N/A 0 028 Hydrogen Recombiner and Purge Control X A2.02 - Ability to (a) predict the impacts of 3.5 1 the following malfunctions or operations on the HRPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: LOCA condition and related concern over hydrogen. (CFR: 41.5/43.5/45.3/45.13) 034 Fuel Handling Equipment Not Used N/A 0 041 Steam Dump/Turbine Bypass Control X K1.05 - Knowledge of the physical 3.5 1 connections and/or cause-effect relationships between the SDS and the following systems: RCS.

(CFR: 41.2 to 41.9/45.7 to 45.8) 045 Main Turbine Generator X G2.1.32 - Conduct of Operations: Ability to 3.4 1 explain and apply all system limits and precautions. (CFR: 41.10/43.2/45.12) 076 Service Water (Auxiliary Component X A2.01 - Ability to (a) predict the impacts of 3.5* 0 Cooling Water) the following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of SWS. (CFR: 41.5/43.5/45.3/45.13) 078 Instrument Air X A3.01 - Ability to monitor automatic 3.1 1 operation of the IAS, including: Air pressure. (CFR: 41.7/45.5) 103 Containment Not Used N/A 0 NUREG-1021, Revision 8, Supplement 1

ES-401 PWR RO Examination Outline Form ES-401-4 Plant Systems - Tier 2/Group 3 System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G K/A Topic(s) Imp. Points K/A Category Point Totals: 1 0 1 0 1 0 0 2 2 0 1 Group Point Total: 8 NUREG-1021, Revision 8, Supplement 1

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 Facility: Waterford 3 Date of Exam: July 29, 2002 Exam Level: RO Category K/A # Topic Imp. Points 2.1.1 Knowledge of conduct of operations requirements. 3.7 1 Conduct of (CFR: 41.10/45.13)

Operations 2.1.12 Ability to apply technical specifications to a system. 2.9 1 (CFR: 43.2/43.5/45.3) 2.1.22 Ability to determine Mode of Operation. 2.8 1 (CFR: 43.5/45.13)

Total 3 2.2.13 Knowledge of tagging and clearance procedures. 3.6 1 (CFR: 41.10/45.13)

Equipment 2.2.22 Knowledge of limiting conditions for operations and 3.4 1 Control safety limits. (CFR: 43.2/45.2) 2.2.26 Knowledge of refueling administrative procedures. 2.5 1 (CFR: 43.5/45.13)

Total 3 2.3.1 Knowledge of 10 CFR: 20 and related facility 2.6 1 radiation control requirements.

(CFR: 41.12/43.4/45.9/45.10)

Radiation Control 2.3.2 Knowledge of facility ALARA program. (CFR: 2.5 1 41.12/43.4/45.9/45.10) 2.3.9 Knowledge of the process for performing a 2.5 1 containment purge. (CFR: 43.4/45.10)

Total 3 2.4.2 Knowledge of system setpoints, interlocks and 3.9 1 automatic actions associated with EOP entry conditions. (CFR: 41.7/45.7/45.8)

Emergency 2.4.17 Knowledge of EOP terms and definitions. 3.1 1 Procedures/ (CFR: 41.10/43.5/45.13)

Plan 2.4.3 Ability to identify post-accident instrumentation. 3.5 1 (CFR: 41.6/45.4) 2.4.49 Ability to perform without reference to procedures 4.0 1 those actions that require immediate operator action of system components and controls.

(CFR: 41.10/43.2/45.6)

Total 4 Tier 3 Point Total 13 NUREG-1021, Revision 8, Supplement 1

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