ML13343A275

2013-11 Draft Outlines

ML13343A275
Person / Time
Site:	Palo Verde
Issue date:	11/09/2013
From:	Kelly Clayton Operations Branch IV
To:	Arizona Public Service Co
laura hurley
References
ES-401, ES-401-2
Download: ML13343A275 (47)

Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Palo Verde Date of Exam: November 1, 2013 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G Total A2 G* Total 1 2 3 4 5 6 1 2 3 4 *

1. 1 3 2 3 3 4 3 18 3 3 6 Emergency &

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

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

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

PV-2013-11-Written Exam Outline Rev 1

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)

E/APE # / Name / Safety Function K K K A A G K/A Topic(s) IR #

1 2 3 1 2 EK1.3 Knowledge of the operational implications of the following concepts as they 3.0 1 000007 (BW/E02&E10; CE/E02) Reactor X Trip - Stabilization - Recovery / 1 apply to the (Reactor Trip Recovery): Annunciators and conditions indicating signals, and remedial actions associated with the (Reactor Trip Recovery).

AA2.30 Ability to determine and interpret the following as they apply to 4.3 2 000008 Pressurizer Vapor Space X Accident / 3 the Pressurizer Vapor Space Accident: Inadequate core cooling 2.1.19 Ability to use plant computers to evaluate system or component status. 3.9 3 000009 Small Break LOCA / 3 X 000011 Large Break LOCA / 3 Not Selected AK1.01 Knowledge of the operational implications of the following concepts as they 4.4 4 000015/17 RCP Malfunctions / 4 X apply to Reactor Coolant Pump Malfunctions (Loss of RC Flow): Natural circulation in a nuclear reactor power plant 2.4.1 Knowledge of EOP entry conditions and immediate action steps. 4.6 5 000022 Loss of Rx Coolant Makeup / 2 X AA1.03 Ability to operate and / or monitor the following as they apply to 3.4 6 000025 Loss of RHR System / 4 X the Loss of Residual Heat Removal System: LPI pumps AK3.02 Knowledge of the reasons for the following responses as they apply to 3.6 7 000026 Loss of Component Cooling X Water / 8 the Loss of Component Cooling Water: The automatic actions (alignments) within the CCWS resulting from the actuation of the ESFAS AK2.03 Knowledge of the interrelations between the Pressurizer Pressure Control 2.6 8 000027 Pressurizer Pressure Control X System Malfunction / 3 Malfunctions and the following: Controllers and positioners PV-2013-11-Written Exam Outline 2 Rev 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)

EA1.12 Ability to operate and monitor the following as they apply to a ATWS: M/G 4.1 9 000029 ATWS / 1 X set power supply and reactor trip breakers 2.2.42 Ability to recognize system parameters that are entry-level conditions for 3.9 10 000038 Steam Gen. Tube Rupture / 3 X Technical Specifications.

EA2.2 Adherence to appropriate procedures and operation within the limitations in 3.4 11 000040 (BW/E05; CE/E05; W/E12) X Steam Line Rupture - Excessive Heat the facility*s license and amendments.

Transfer / 4 EK2.1 Knowledge of the interrelations between the (Loss of Feedwater) and the 3.3 12 000054 (CE/E06) Loss of Main X Feedwater / 4 following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

EK3.02 Knowledge of the reasons for the following responses as the apply to the 4.3 13 000055 Station Blackout / 6 X Station Blackout: Actions contained in EOP for loss of offsite and onsite power AA2.46 Ability to determine and interpret the following as they apply to 4.2 14 000056 Loss of Off-site Power / 6 X the Loss of Offsite Power: That the ED/Gs have started automatically and that the bus tie breakers are closed AA2.17 Ability to determine and interpret the following as they apply to 3.1 15 000057 Loss of Vital AC Inst. Bus / 6 X the Loss of Vital AC Instrument Bus: System and component status, using local or remote controls AA1.02 Ability to operate and / or monitor the following as they apply to 3.1 16 000058 Loss of DC Power / 6 X the Loss of DC Power: Static inverter dc input breaker, frequency meter, ac output breaker, and ground fault detector AK3.03 Knowledge of the reasons for the following responses as they apply to 4.0 17 000062 Loss of Nuclear Svc Water / 4 X the Loss of Nuclear Service Water: Guidance actions contained in EOP for Loss of nuclear service water 000065 Loss of Instrument Air / 8 Not Selected PV-2013-11-Written Exam Outline 3 Rev 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO)

W/E04 LOCA Outside Containment / 3 Not Applicable W/E11 Loss of Emergency Coolant Not Applicable Recirc. / 4 BW/E04; W/E05 Inadequate Heat Not Applicable Transfer - Loss of Secondary Heat Sink / 4 AK1.02 Knowledge of the operational implications of the following concepts as l 3.3 18 000077 Generator Voltage and Electric X Grid Disturbances / 6 they apply to Generator Voltage and Electric Grid Disturbances: Over-excitation K/A Category Totals: 3 2 3 3 4 3 Group Point Total: 18 PV-2013-11-Written Exam Outline 4 Rev 1

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)

E/APE # / Name / Safety Function K K K A A K/A Topic(s) IR #

G 1 2 3 1 2 000001 Continuous Rod Withdrawal / 1 AA1.01 Ability to operate and / or monitor the following as they apply to X 3.5 19 the Continuous Rod Withdrawal: Bank select switch 000003 Dropped Control Rod / 1 Not Selected 000005 Inoperable/Stuck Control Rod / 1 Not Selected 000024 Emergency Boration / 1 AK2.01 Knowledge of the interrelations between Emergency Boration and X 2.7 20 the following: Valves 000028 Pressurizer Level Malfunction / 2 Not Selected 000032 Loss of Source Range NI / 7 Not Selected 000033 Loss of Intermediate Range NI / 7 AK3.01 Knowledge of the reasons for the following responses as they 3.2 21 apply to the Loss of Intermediate Range Nuclear Instrumentation:

X Termination of startup following loss of intermediate range instrumentation 000036 (BW/A08) Fuel Handling Accident / 8 AK1.03 Knowledge of the operational implications of the following 4.0 22 X concepts as they apply to Fuel Handling Incidents: Indications of approaching criticality 000037 Steam Generator Tube Leak / 3 Not Selected 000051 Loss of Condenser Vacuum / 4 AA2.02 Ability to determine and interpret the following as they apply to the 3.9 23 X Loss of Condenser Vacuum: Conditions requiring reactor and/or turbine trip PV-2013-11-Written Exam Outline 5 Rev 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO) 000059 Accidental Liquid RadWaste Rel. / 9 Not Selected 000060 Accidental Gaseous Radwaste Rel. / 9 Not Selected 000061 ARM System Alarms / 7 Not Selected 000067 Plant Fire On-site / 8 2.4.34 Knowledge of RO tasks performed outside the main control room X 4.2 24 during an emergency and the resultant operational effects.

000068 (BW/A06) Control Room Evac. / 8 AK3.12 Knowledge of the reasons for the following responses as they 4.1 25 X apply to the Control Room Evacuation: Required sequence of actions for emergency evacuation of control room 000069 (W/E14) Loss of CTMT Integrity / 5 Not Selected 000074 (W/E06&E07) Inad. Core Cooling / 4 EA1.27 Ability to operate and monitor the following as they apply to a X 4.2 26 Inadequate Core Cooling: ECCS valve control switches and indicators 000076 High Reactor Coolant Activity / 9 Not Selected W/EO1 & E02 Rediagnosis & SI Termination / 3 Not Applicable W/E13 Steam Generator Over-pressure / 4 Not Applicable W/E15 Containment Flooding / 5 Not Applicable W/E16 High Containment Radiation / 9 Not Applicable BW/A01 Plant Runback / 1 Not Applicable BW/A02&A03 Loss of NNI-X/Y / 7 Not Applicable BW/A04 Turbine Trip / 4 Not Applicable BW/A05 Emergency Diesel Actuation / 6 Not Applicable PV-2013-11-Written Exam Outline 6 Rev 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (RO)

BW/A07 Flooding / 8 Not Applicable BW/E03 Inadequate Subcooling Margin / 4 Not Applicable BW/E08; W/E03 LOCA Cooldown - Depress. / 4 Not Applicable BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 AK1.3 Knowledge of the operational implications of the following concepts 3.1 27 as they apply to the (Natural Circulation Operations): Annunciators and X conditions indicating signals, and remedial actions associated with the (Natural Circulation Operations).

BW/E13&E14 EOP Rules and Enclosures Not Applicable CE/A11; W/E08 RCS Overcooling - PTS / 4 Not Selected CE/A16 Excess RCS Leakage / 2 Not Selected CE/E09 Functional Recovery Not Selected K/A Category Point Totals: 2 1 2 2 1 1 Group Point Total: 9 PV-2013-11-Written Exam Outline 7 Rev 1

ES-401 4 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO)

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 4 003 Reactor Coolant Pump K3.02 Knowledge of the effect that a loss or malfunction of the RCPS X 3.5 28 will have on the following: S/G 004 Chemical and Volume K5.30 Knowledge of the operational implications of the following Control X concepts as they apply to the CVCS: Relationship between temperature 3.8 29 and pressure in CVCS components during solid plant operation 005 Residual Heat Removal X K2.01 Knowledge of bus power supplies to the following: RHR pumps 3.0 30 006 Emergency Core Cooling K4.11 Knowledge of ECCS design feature(s) and/or interlock(s) 3.9 31 which provide for the following: Reset of SIS X X A2.11 Ability to (a) predict the impacts of the following malfunctions or 4.0 32 operations on the ECCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Rupture of ECCS header 007 Pressurizer Relief/Quench A1.02 Ability to predict and/or monitor changes in parameters (to Tank X prevent exceeding design limits) associated with operating the PRTS 2.7 33 controls including: Maintaining quench tank pressure 008 Component Cooling Water K1.05 Knowledge of the physical connections and/or cause-effect 3.0 34 relationships between the CCWS and the following systems: Sources of X X makeup water 2.2.12 Knowledge of surveillance procedures. 3.7 35 010 Pressurizer Pressure Control K6.01 Knowledge of the effect of a loss or malfunction of the following X 2.7 36 will have on the PZR PCS: Pressure detection systems PV-2013-11-Written Exam Outline 8 Rev 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO) 012 Reactor Protection A4.03 Ability to manually operate and/or monitor in the control room:

X 3.6 37 Channel blocks and bypasses 013 Engineered Safety Features K3.01 Knowledge of the effect that a loss or malfunction of the ESFAS 4.4 38 Actuation will have on the following: Fuel X X A3.01 Ability to monitor automatic operation of the ESFAS including: 3.7 39 Input channels and logic 022 Containment Cooling K4.04 Knowledge of CCS design feature(s) and/or interlock(s)

X 2.8 40 which provide for the following: Cooling of control rod drive motors 025 Ice Condenser Not Applicable 026 Containment Spray K1.01 Knowledge of the physical connections and/or cause effect X 4.2 41 relationships between the CSS and the following systems: ECCS 039 Main and Reheat Steam A4.04 Ability to manually operate and/or monitor in the control X 3.8 42 room: Emergency feedwater pump turbines 059 Main Feedwater K3.02 Knowledge of the effect that a loss or malfunction of the MFW will 3.6 43 have on the following: AFW system X X A2.11 Ability to (a) predict the impacts of the following malfunctions or 3.0 44 operations on the MFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of feedwater control system 061 Auxiliary/Emergency K5.02 Knowledge of the operational implications of the following 3.2 45 Feedwater concepts as the apply to the AFW: Decay heat sources and magnitude X X A3.03 Ability to monitor automatic operation of the AFW, including: 3.9 46 AFW S/G level control on automatic start PV-2013-11-Written Exam Outline 9 Rev 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO) 062 AC Electrical Distribution K2.01 Knowledge of bus power supplies to the following: Major system 3.0 47 loads A2.12 Ability to (a) predict the impacts of the following malfunctions or 3.2 48 X X 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: Restoration of power to a system with a fault on it 063 DC Electrical Distribution K4.02 Knowledge of DC electrical system design feature(s) and/

X or interlock(s) which provide for the following: Breaker interlocks, 2.9 49 permissives, bypasses and cross-ties 064 Emergency Diesel Generator K6.07 Knowledge of the effect of a loss or malfunction of the 2.7 50 following will have on the ED/G system: Air receivers X X A4.01 Ability to manually operate and/or monitor in the control room: 4.0 51 Local and remote operation of the ED/G 073 Process Radiation K1.01 Knowledge of the physical connections and/or cause effect Monitoring X relationships between the PRM system and the following systems: 3.6 52 Those systems served by PRMs 076 Service Water A3.02 Ability to monitor automatic operation of the SWS, including:

X 3.7 53 Emergency heat loads 078 Instrument Air X 2.1.30 Ability to locate and operate components, including local controls. 4.4 54 103 Containment A1.01 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the X 3.7 55 containment system controls including: Containment pressure, temperature, and humidity K/A Category Point Totals: 3 2 3 3 2 2 2 3 3 3 2 Group Point Total: 28 PV-2013-11-Written Exam Outline 10 Rev 1

ES-401 5 Form ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO)

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 Not Selected 2.4.11 Knowledge of abnormal condition procedures. 4.0 56 002 Reactor Coolant X K2.01 Knowledge of bus power supplies to the following: Charging 011 Pressurizer Level Control X 3.1 57 pumps K5.02 Knowledge of the operational implications of the following 014 Rod Position Indication X concepts as they apply to the RPIS: RPIS independent of demand 2.8 58 position 015 Nuclear Instrumentation Not Selected K3.02 Knowledge of the effect that a loss or malfunction of the 016 Non-nuclear Instrumentation X 3.4 59 NNIS will have on the following: PZR LCS 017 In-core Temperature Monitor Not Selected 027 Containment Iodine Removal Not Selected A2.02 Malfunctions or operations on the HRPS; and (b) based 028 Hydrogen Recombiner on those predictions, use procedures to correct, control or mitigate the and Purge Control X 3.5 60 consequences of those malfunctions or operations: LOCA condition and related concern over hydrogen 029 Containment Purge Not Selected PV-2013-11-Written Exam Outline 11 Rev 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO)

K4.01 Knowledge of design feature(s) and/or interlock(s) 033 Spent Fuel Pool Cooling X 2.9 61 which provide for the following: Maintenance of spent fuel level A4.02 Ability to manually operate and/or monitor in the control room:

034 Fuel Handling Equipment X 3.5 62 Neutron levels 035 Steam Generator Not Selected A3.02 Ability to monitor automatic operation of the SDS, including: RCS 041 Steam Dump/Turbine 3.3 63 X pressure, RCS temperature, and reactor power Bypass Control K1.06 Knowledge of the physical connections and/or cause-effect 045 Main Turbine Generator X relationships between the MT/G system and the following systems: RCS, 2.6 64 during steam valve test 055 Condenser Air Removal Not Selected 056 Condensate Not Selected 068 Liquid Radwaste Not Selected 071 Waste Gas Disposal Not Selected 072 Area Radiation Monitoring Not Selected 075 Circulating Water Not Selected 079 Station Air Not Selected A1.05 Ability to predict and/or monitor changes in parameters 086 Fire Protection X (to prevent exceeding design limits) associated with Fire Protection 2.9 65 System operating the controls including: FPS lineups K/A Category Point Totals: 1 1 1 1 1 0 1 1 1 1 1 Group Point Total: 10 PV-2013-11-Written Exam Outline 12 Rev 1

PV-2013-11-Written Exam Outline 13 Rev 1 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 Not Selected Trip - Stabilization - Recovery / 1 AA2.29 Ability to determine and interpret the following as they apply to 000008 Pressurizer Vapor Space X Accident / 3 the Pressurizer Vapor Space Accident: The effects of bubble in reactor vessel 4.2 1 000009 Small Break LOCA / 3 Not Selected 000011 Large Break LOCA / 3 X 2.1.20 Ability to interpret and execute procedure steps.

4.6 2 (New) 000015/17 RCP Malfunctions / 4 Not Selected 000022 Loss of Rx Coolant Makeup / 2 Not Selected 000025 Loss of RHR System / 4 Not Selected 000026 Loss of Component Cooling Not Selected Water / 8 000027 Pressurizer Pressure Control Not Selected System Malfunction / 3 2.4.2 Knowledge of system set points, interlocks and automatic actions associated 000029 ATWS / 1 X with EOP entry conditions 4.6 2 (Rejected) 000038 Steam Gen. Tube Rupture / 3 Not Selected PV-2013-11-Written Exam Outline 14 Rev 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO) 000040 (BW/E05; CE/E05; W/E12) Not Selected Steam Line Rupture - Excessive Heat Transfer / 4 000054 (CE/E06) Loss of Main Not Selected Feedwater / 4 000055 Station Blackout / 6 X EA2.06 Ability to determine or interpret the following as they apply to a Station Blackout: Faults and lockouts that must be cleared prior to re-energizing buses (Rejected) 4.1 EA 2.02 Ability to determine or interpret the following as they apply to a 4.6 3 Station Blackout: RCS core cooling through natural circulation cooling to S/G cooling (New) 000056 Loss of Off-site Power / 6 Not Selected 000057 Loss of Vital AC Inst. Bus / 6 Not Selected AA2.03 Ability to determine and interpret the following as they apply to 000058 Loss of DC Power / 6 X the Loss of DC Power: DC loads lost; impact on ability to operate and monitor plant 3.9 4 systems 2.1.32 Ability to explain and apply system limits and precautions.

000062 Loss of Nuclear Svc Water / 4 X 4.0 5 000065 Loss of Instrument Air / 8 Not Selected W/E04 LOCA Outside Containment / 3 Not Applicable W/E11 Loss of Emergency Coolant Not Applicable Recirc. / 4 BW/E04; W/E05 Inadequate Heat Not Applicable Transfer - Loss of Secondary Heat Sink / 4 PV-2013-11-Written Exam Outline 15 Rev 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (SRO) 2.2.36 Ability to analyze the effect of maintenance activities, such as degraded 000077 Generator Voltage and Electric X Grid Disturbances / 6 power sources, on the status of limiting conditions for operations. 4.2 6 K/A Category Totals: 3 3 Group Point Total: 6 PV-2013-11-Written Exam Outline 16 Rev 1

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 Not Selected 000003 Dropped Control Rod / 1 Not Selected 000005 Inoperable/Stuck Control Rod / 1 Not Selected 000024 Emergency Boration / 1 Not Selected 000028 Pressurizer Level Malfunction / 2 Not Selected 000032 Loss of Source Range NI / 7 Not Selected 000033 Loss of Intermediate Range NI / 7 Not Selected 000036 (BW/A08) Fuel Handling Accident / 8 X 2.4.41 Knowledge of the emergency action level thresholds and 4.6 7 classifications.

000037 Steam Generator Tube Leak / 3 X 2.1.23 Ability to perform specific system and integrated plant procedures 4.4 8 during all modes of plant operation.

000051 Loss of Condenser Vacuum / 4 Not Selected 000059 Accidental Liquid RadWaste Rel. / 9 Not Selected 000060 Accidental Gaseous Radwaste Rel. / 9 Not Selected 000061 ARM System Alarms / 7 Not Selected PV-2013-11-Written Exam Outline 17 Rev 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO) 000067 Plant Fire On-site / 8 Not Selected 000068 (BW/A06) Control Room Evac. / 8 Not Selected 000069 (W/E14) Loss of CTMT Integrity / 5 X EA2.02 Ability to determine or interpret the following as they apply to the Loss of Containment Integrity: Verification of automatic and manual 4.4 9 means of restoring integrity 000074 (W/E06&E07) Inad. Core Cooling / 4 Not Selected 000076 High Reactor Coolant Activity / 9 Not Selected W/EO1 & E02 Rediagnosis & SI Termination / 3 Not Applicable W/E13 Steam Generator Over-pressure / 4 Not Applicable W/E15 Containment Flooding / 5 Not Applicable W/E16 High Containment Radiation / 9 Not Applicable BW/A01 Plant Runback / 1 Not Applicable BW/A02&A03 Loss of NNI-X/Y / 7 Not Applicable BW/A04 Turbine Trip / 4 Not Applicable BW/A05 Emergency Diesel Actuation / 6 Not Applicable BW/A07 Flooding / 8 Not Applicable BW/E03 Inadequate Subcooling Margin / 4 Not Applicable BW/E08; W/E03 LOCA Cooldown - Depress. / 4 Not Applicable BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 Not Selected PV-2013-11-Written Exam Outline 18 Rev 1

ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 (SRO)

BW/E13&E14 EOP Rules and Enclosures Not Applicable CE/A11; W/E08 RCS Overcooling - PTS / 4 Not Selected CE/A16 Excess RCS Leakage / 2 Not Selected CE/E09 Functional Recovery X EA2.1 Ability to determine and interpret the following as they apply to the (Functional Recovery): Facility conditions and selection of appropriate 4.4 10 procedures during abnormal and emergency operations.

K/A Category Point Totals: 2 2 Group Point Total: 4 PV-2013-11-Written Exam Outline 19 Rev 1

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 4 003 Reactor Coolant Pump A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those (New 14) predictions, use procedures to correct, control, or mitigate the X 3.9 14 consequences of those malfunctions or operations: Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP 004 Chemical and Volume Not Selected Control 005 Residual Heat Removal Not Selected 006 Emergency Core Cooling A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the ECCS; and (b) based on those predictions, use X 4.3 11 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of flow path 007 Pressurizer Relief/Quench Not Selected Tank 008 Component Cooling Water Not Selected 010 Pressurizer Pressure Control Not Selected 012 Reactor Protection Not Selected 013 Engineered Safety Features 2.2.22 Knowledge of limiting conditions for operations and safety limits.

Actuation X 4.7 12 022 Containment Cooling Not Selected 025 Ice Condenser Not Applicable PV-2013-11-Written Exam Outline 20 Rev 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (SRO) 026 Containment Spray X 2.1.20 Ability to interpret and execute procedure steps. 4.6 13 039 Main and Reheat Steam Not Selected 059 Main Feedwater Not Selected 061 Auxiliary/Emergency Not Selected Feedwater 062 AC Electrical Distribution Not Selected 063 DC Electrical Distribution Not Selected 064 Emergency Diesel Generator A2.06 Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use (Rejected) X procedures to correct, control, or mitigate the consequences of those 3.3 14 malfunctions or operations: Operating unloaded, lightly loaded, and highly loaded time limit 073 Process Radiation Not Selected Monitoring 076 Service Water Not Selected 078 Instrument Air Not Selected 103 Containment A2.03 Ability to (a) predict the impacts of the following malfunctions or operations on the containment system and X (b) based on those predictions, use procedures to correct, control, or 3.8 15 mitigate the consequences of those malfunctions or operations: Phase A and B isolation K/A Category Point Totals: 3 2 Group Point Total: 5 PV-2013-11-Written Exam Outline 21 Rev 1

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 Not Selected 002 Reactor Coolant Not Selected 011 Pressurizer Level Control Not Selected 014 Rod Position Indication Not Selected 015 Nuclear Instrumentation X 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and 4.7 16 instrument interpretation.

016 Non-nuclear Instrumentation Not Selected 017 In-core Temperature Monitor X A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the ITM System ; and (b) based on those predictions, use 4.1 17 procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Core damage 027 Containment Iodine Removal Not Selected 028 Hydrogen Recombiner Not Selected and Purge Control 029 Containment Purge Not Selected 033 Spent Fuel Pool Cooling Not Selected 034 Fuel Handling Equipment X K4.02 Knowledge of design feature(s) and/or interlock(s) which provide for 3.3 18 the following: Fuel movement PV-2013-11-Written Exam Outline 22 Rev 1

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (SRO) 035 Steam Generator Not Selected 041 Steam Dump/Turbine Not Selected Bypass Control 045 Main Turbine Generator Not Selected 055 Condenser Air Removal Not Selected 056 Condensate Not Selected 068 Liquid Radwaste Not Selected 071 Waste Gas Disposal Not Selected 072 Area Radiation Monitoring Not Selected 075 Circulating Water Not Selected 079 Station Air Not Selected 086 Fire Protection Not Selected K/A Category Point Totals: 1 1 1 Group Point Total: 3 PV-2013-11-Written Exam Outline 23 Rev 1

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Palo Verde Date of Exam: November 1, 2013 RO SRO-Only Category K/A # Topic IR # IR #

2.1.1 Knowledge of conduct of operations requirements. 3.8 66

1. Knowledge of shift or short-term relief turnover practices. 3.7 67 Conduct 2.1.3 of Operations Knowledge of RO duties in the control room during fuel handling, such as responding to alarms 2.1.44 from the fuel handling area, communication with the fuel storage facility, systems operated from 3.9 68 the control room in support of fueling operations, and supporting instrumentation.

Ability to use procedures related to shift staffing, such as minimum crew complement, overtime 2.1.5 3.9 19 limitations, etc.

2.1.36 Knowledge of procedures and limitations involved in core alterations. (Rejected) 4.1 20 2.1.34 Knowledge of primary and secondary plant chemistry limits. (New) 3.5 Subtotal 3 2 2.2.6 Knowledge of the process for making changes to procedures. 3.0 69 2.2.13 Knowledge of tagging and clearance procedures. 4.1 70 2.

Equipment Control 2.2.14 Knowledge of the process for controlling equipment configuration or status. 3.9 71 PV-2013-11-Written Exam Outline 24 Rev 1

Facility: Palo Verde Date of Exam: November 1, 2013 RO SRO-Only Category K/A # Topic IR # IR #

2.2.7 Knowledge of the process for conducting special or infrequent tests. (Rejected) 3.6 21 2.2.23 Ability to track Technical Specification limiting conditions for operations. (New) 4.6 Knowledge of the process for managing maintenance activities during power operations, such 2.2.17 3.8 22 as risk assessments, work prioritization, and coordination with the transmission system operator.

Subtotal 3 2 Knowledge of radiation exposure limits under normal or emergency conditions.

2.3.4 3.2 72 Knowledge of radiological safety procedures pertaining to licensed operator duties, such as

3. 2.3.13 3.4 73 response to radiation monitor alarms, containment entry requirements, fuel handling Radiation responsibilities, access to locked high-radiation areas, aligning filters, etc.

Control Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or 2.3.14 3.8 23 emergency conditions or activities.

Subtotal 2 1 Knowledge of the organization of the operating procedures network for normal, abnormal, and 2.4.5 3.7 74 emergency evolutions.

4.

Emergency Knowledge of general guidelines for EOP usage.

2.4.14 3.8 75 Procedures /

Plan Knowledge of low power/shutdown implications in accident (e.g., loss of coolant accident or loss 2.4.9 4.2 24 of residual heat removal) mitigation strategies.

Knowledge of procedures relating to a security event (non-safeguards information).

2.4.28 4.1 25 PV-2013-11-Written Exam Outline 25 Rev 1

Facility: Palo Verde Date of Exam: November 1, 2013 RO SRO-Only Category K/A # Topic IR # IR #

Subtotal 2 2 Tier 3 Point Total 10 7 PV-2013-11-Written Exam Outline 26 Rev 1

ES-401 Record of Rejected K/As Form ES-401-4 Tier / Randomly Selected K/A Reason for Rejection Group 2.4.2 System setpoints, interlocks and EOP entry conditions

1. 2 (77)

Knowledge of system set points, is RO knowledge T1/G1 interlocks and automatic actions associated with EOP entry conditions. ATWS 4.1 055 EA2.06 Was not able to develop a discriminating SRO level

1. 3 (78)

Ability to determine or interpret the question, this KA is better suited to RO knowledge T1/G1 following as they apply to a Station Blackout: Faults and lockouts that must be cleared prior to re-energizing buses 3.6 064 A2.06 Operating a DG is an RO task; I was not able to

1. 14 (89)

Ability to (a) predict the impacts of develop a discriminating SRO level question.

T2/G1 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:

Operating unloaded, lightly loaded, and highly loaded time limit 2.1.36 Was not able to develop a discriminating SRO level

1. 20 (95)

Knowledge of procedures and question. Tried to incorporate TS definitions and LCOs G3 limitations involved in core but they are RO knowledge.

alterations.

2.2.7 Was not able to develop a discriminating SRO level

1. 21 (96)

Knowledge of the process for question.

G3 conducting special or infrequent tests.

When a K/A has been rejected, a new one is chosen using NKEG (NRC K/A Exam Generator)

Version 1.1. It is noted which tier and group the rejected K/A is in, then a New random outline is generated using the aforementioned software. A corresponding tier and group K/A is chosen from the generated outline that is the same type of K/A (i.e. Generic for a Generic, A2 for an A2, etc. - within the applicable bounds of NUREGs 1021 and 1122). A question is now attempted with this K/A. If a question cannot be written or the K/A is not applicable, another randomly generated outline is created and the process is repeated.

Revision 0

ES-301 Administrative Topics Outline Form ES-301-1 Palo Verde Facility: _______________________________ 11/04/13 Date of Examination: _____________

Examination Level: RO SRO Operating Test Number: __________

Administrative Topic Type Describe activity to be performed (see Note) Code*

[RO A-1] Calculate a dilution for a power ascension.

K/A: 2.1.37 Knowledge of procedures, guidelines, or limitations Conduct of Operations R, D associated with reactivity management.

Importance Rating: 4.3

[RO A-2] Determine faults and required actions in Reactor Coolant System cooldown rate data.

Conduct of Operations R, M K/A: 2.1.32 Ability to explain and apply system limits and precautions.

Importance Rating: 3.8

[RO A-3] Determine and evaluate total identified RCS leakage in accordance with 40ST-9RC05, Manual Calculation of RCS Water Equipment Control R, N Inventory.

K/A: 2.2.12 Knowledge of surveillance procedures.

Importance Rating: 3.7

[RO A-4] Determine entry requirements for HRA in the RCA.

K/A: 2.3.7 Ability to comply with radiation work permit requirements R, D during normal or abnormal conditions.

Radiation Control Importance Rating: 3.5 N/A N/A l Emergency Procedures/Plan 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)

ES-301, Page 22 of 27 REV 0

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 PVNGS Facility: _____________________________ 11/04/13 Date of Examination: ______________

Exam Level: RO SRO-I SRO-U Operating Test No.: _______________

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

[S-1] Throttle HPSI, Restore HPSI Flow In Response to Degrading Condition a.

(K/A: 3.2 006 A4.07)

A, EN, N, L, S 2

b. [S-2] SG Level Reduction (K/A: 3.4 035 A2.01) D, L, S 4P

c. [S-3] Fill a SIT (K/A: 3.3 006 A1.13) P, S 3

d. [S-4] Reduce to Two CW Pumps and Two Cooling Towers (K/A: 3.8 075 A2.02) A, N, S 8

e. [S-5] Transfer 13.8 kV buses (K/A: 3.6 062 K1.04) A, D, S 6

f. [S-6] Calibration of Control Channel NI - 40OP-9NI01 (K/A: 3.7 015 A4.02) N, S 7

[S-7] Emergency Borate Using HPSI (K/A: 4.2 024 AK3.02)

g. A, D, L, S 1

[S-8] Respond to Containment Sump Trouble Excessive Runtime Alarm

h. (K/A: 3.5 103 A4.01) D, L, S 5 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. [P-1] Start AFN Locally (K/A: 3.4 061 A2.03) A, D, E, L 4S

j. [P-2] X-tie EW Train B to SFP cooling (K/A: 3.8 033 A2.02) D, E, R 8

k. [P-3] Line Up OW Sumps During SGTR (K/A: 4.2 037 AK3.06) D, E 3

@ 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 l (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 (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 ES-301, Page 23 of 27 REV 0

ES-301 Transient and Event Checklist Form ES-301-5 Facility: PVNGS Date of Exam: 11/4/2013 Operating Test No.:

A E Scenarios P V 1 2 3 4 T M P E O I L N CREW POSITION CREW POSITION CREW POSITION CREW T N I T POSITION I

C S A B S A B S A B S A B A M

A T R T O R T O R T O R T O L U N Y O C P O C P O C P O C P M(*)

T P E R I U RO RX 5 1 1 1 0 R1 NOR 1 1 1 1 1 I/C 2, 3, 8 3, 5, 7, 2, 4, 11 4 4 2 10 7, 8 MAJ 6, 7 6, 9 6 5 2 2 1 TS 0 2 2 RO RX 5 1 1 1 0 NOR 1 1 2 1 1 1 R2, R4 I/C 3, 4, 3, 5, 7, 2, 4, 12 4 4 2 5, 9 10 7, 8 MAJ 6, 7 6, 9 6 5 2 2 1 TS 0 2 2 RO RX 0 1 1 0 NOR 1 1 1 1 1 R3, R5 I/C 2, 3, 8 3, 5, 7, 7 4 4 2 10 MAJ 6, 7 6, 9 4 2 2 1 TS 0 2 2 RO RX 0 1 1 0 R6, R8, NOR 1 1 1 1 1 R10, R11 I/C 3, 4, 2, 4, 5, 9 4 4 2 5, 9 8, 10 MAJ 6, 7 6, 9 4 2 2 1 TS 0 2 2 RO RX 0 1 1 0 R7, R9 NOR 1 1 2 1 1 1 I/C 2, 3, 8 3, 5, 7, 3, 5 9 4 4 2 10 MAJ 6, 7 6, 9 6 5 2 2 1 TS 0 2 2 7 Evaluator Schedule Revision 0

ES-301 Transient and Event Checklist Form ES-301-5 Facility: PVNGS Date of Exam: 11/4/2013 Operating Test No.:

A E Scenarios P V 1 2 3 4 T M P E O I L N CREW POSITION CREW POSITION CREW POSITION CREW T N I T POSITION I

C S A B S A B S A B S A B A M

A T R T O R T O R T O R T O L U N Y O C P O C P O C P O C P M(*)

T P E R I U SRO-I RX 0 1 1 0 I1 NOR 1 1 1 1 1 I/C 2, 3, 8 2, 3, 4, 10 4 4 2 5, 7, 8, 10 MAJ 6, 7 6, 9 4 2 2 1 TS 3, 5 2 0 2 2 SRO-I RX 5 1 1 1 0 I2 NOR 1 1 1 1 1 I/C 2, 3, 8 2, 3, 4, 8 4 4 2 7, 8 MAJ 6, 7 6 3 2 2 1 TS 4, 5 2 0 2 2 SRO-I RX 0 1 1 0 I3, I4 NOR 1 1 2 1 1 1 I/C 2, 3, 4, 2, 4, 5, 3, 5 13 4 4 2 5, 8, 9 8, 10 MAJ 6, 7 6, 9 6 5 2 2 1 TS 3, 5 2 0 2 2 SRO-I RX 5 1 1 1 0 I5, I6 NOR 1 1 2 1 1 1 I/C 3, 4, 2, 4, 5, 2, 3, 4, 14 4 4 2 5, 9 8, 10 7, 8 MAJ 6, 7 6, 9 6 5 2 2 1 TS 4, 5 2 0 2 2 SRO-I RX 5 1 1 1 0 I7 NOR 1 1 2 1 1 1 I/C 2, 3, 8 3, 5, 7, 2, 3, 4, 12 4 4 2 10 7, 8 MAJ 6, 7 6, 9 6 5 2 2 1 TS 4, 5 2 0 2 2 7 Evaluator Schedule Revision 0

ES-301 Transient and Event Checklist Form ES-301-5 Facility: PVNGS Date of Exam: 11/4/2013 Operating Test No.:

A E Scenarios P V 1 2 3 4 T M P E O I L N CREW POSITION CREW POSITION CREW POSITION CREW T N I T POSITION I

C S A B S A B S A B S A B A M

A T R T O R T O R T O R T O L U N Y O C P O C P O C P O C P M(*)

T P E R I U SRO-I RX 5 1 1 1 0 I8 NOR 1 1 1 1 1 I/C 2, 3, 4, 2, 4, 11 4 4 2 5, 7, 8, 7, 8 10 MAJ 6, 9 6 3 2 2 1 TS 3, 5 2 0 2 2 SRO-U RX 0 1 1 0 U1, U2, NOR 1 1 2 1 1 1 U3, U4, I/C 2, 3, 4, 2, 3, 4, 13 4 4 2 U5, U6 5, 8, 9 5, 7, 8, 10 MAJ 6, 7 6, 9 4 2 2 1 TS 3, 5 3, 5 4 0 2 2 Instructions:

1. Check the applicant level and enter the operating test number and Form ES-D-1 event numbers for each event type; TS are not applicable for RO applicants. ROs must serve in both the at-the-controls (ATC) and balance-of-plant (BOP) positions; Instant SROs must serve in both the SRO and the ATC positions, including at least two instrument or component (I/C) malfunctions and one major transient, in the ATC position. If an Instant SRO additionally serves in the BOP position, one I/C malfunction can be credited toward the two I/C malfunctions required for the ATC position.

2. Reactivity manipulations may be conducted under normal or controlled abnormal conditions (refer to Section D.5.d) but must be significant per Section C.2.a of Appendix D. (*) Reactivity and normal evolutions may be replaced with additional instrument or component malfunctions on a 1-for-1 basis.

3. Whenever practical, both instrument and component malfunctions should be included; only those that require verifiable actions that provide insight to the applicants competence count toward the minimum requirements specified for the applicants license level in the right-hand columns.

7 Evaluator Schedule Revision 0

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: __1 Op-Test No: 2013 Examiners: Operators:

Initial Conditions: (100% power, MOC).

Turnover: Unit 1 is at 100% power (250 EFPD). HPSI A Pump is tagged out.

Event Malf. No. Event Event Description No. Type*

1 N/A N Shift Condenser AR Pumps to ARN-P01D running with ARN-BOP/SRO P01B shutdown for preventative maintenance in accordance with 40OP-9AR01, Condenser Air Removal, Section 6.2.

2 cmTRRC03RCNPT100X_4 I PT-100X fails low. Crew will select Y on Pressurizer Pressure ATC/SRO Control selector switch and will reset the proportional heaters in accordance with alarm response.

40AL-9RK4A, Panel B04A Alarm Responses 3 mfTH06A f:0.6 C Small Steam Generator tube leak requires entry into 40AO-ALL 9ZZ02, Excessive RCS Leakrate.

(AOP/TS) Tube leak is on Steam Generator 1 with a leakrate of ~8.1 gpm.

4 cmCPTP04TCNP01B_5 C Running Turbine Cooling Water pump will trip due to rapid cmCPTP04TCNP01A_2 BOP/SRO seizure of the impeller and the standby pump will fail to automatically start requiring crew to start manually. Crew will (TCA trips, TCB fails to start) (AOP) enter 40AO-9ZZ03, Loss of Cooling Water.

5 cmTRRX12SGBLT1123B_4 I CH B Steam Generator #2 WR Level Transmitter will fail low.

BOP/SRO Crew will address Technical Specifications and bypass affected channel and bistables in accordance with alarm response.

(TS) 40AL-9RK5B, Panel B05B Alarm Responses 6 modify mfTH06A f:12 M Steam Generator Tube Leak will degrade to beyond charging ALL pump capacity. Crew will trip perform a Reactor Trip due to meeting criteria. 40EP-9EO01, SPTAs 7 mfMS03A f:30 r:5:00 M On the Reactor Trip, an ESD will develop on the affected Steam ALL Generator (#1). This will require entry into 40EP-9EO09, Functional Recovery Procedure.

CRITICAL TASK - Once SPTAs completed and FRP is entered, establish 1360-1600 gpm feed to ruptured Steam Generator prior to exiting HR-2 of FRP.

8 cmCPCC08SPAP01_5 C Spray Pond pump A will fail to auto start. Crew will manually ATC/SRO start pump to supply cooling water to a running (unloaded) Diesel Generator.

9 cmBSRP01BSPZRPRLOAT_ C SIAS/CIAS will fail to automatically initiate on low pressurizer 1 BOP/SRO pressure.

cmBSRP01BSPZRPRLOBT_1 CRITICAL TASK - When the SIAS/CIAS setpoint is cmBSRP01BSPZRPRLOCT_1 exceeded, manually initiate SIAS and CIAS prior to cmBSRP01BSPZRPRLODT_ completion of SPTAs.

1 End Scenario may be ended once SIAS and CIAS have been manually point initiated and Steam Generator #1 is being fed at 1360-1600 gpm.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 1 of 3 REV 0

Appendix D Scenario Outline Form ES-D-1 Crew Handout Plant conditions:

Unit 1 is at 100% power.

The core is presently at 250 EFPD.

Risk Management Action Level is GREEN HPSI B Pump is protected in accordance with 40DP-9AP21, Protected Equipment Train B is protected.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header.

Equipment out of service:

HPSI A Pump is under clearance for bearing inspection. LCO 3.5.3 Condition B has been entered. The pump is expected to return to service in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Planned shift activities:

Shift Condenser Air Removal Pumps to ARN-P01D running with ARN-P01B shutdown in preparation for preventative maintenance in accordance with 40OP-9AR01, Condenser Air Removal, Section 6.2.

Sections 6.2.1 and 6.2.2 have been completed. An area operator has been briefed and is standing by.

NUREG-1021, Revision 9 2 of 3 REV 0

Appendix D Scenario Outline Form ES-D-1 Turnover Plant conditions:

Unit 1 is at 100% power.

The core is presently at 250 EFPD.

Risk Management Action Level is GREEN HPSI B Pump is protected in accordance with 40DP-9AP21, Protected Equipment Train B is protected.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header.

Equipment out of service:

HPSI A Pump is under clearance for bearing inspection. LCO 3.5.3 Condition B has been entered. The pump is expected to return to service in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Planned shift activities:

Shift Condenser Air Removal Pumps to ARN-P01D running with ARN-P01B shutdown in preparation for preventative maintenance in accordance with 40OP-9AR01, Condenser Air Removal, Section 6.2.

Sections 6.2.1 and 6.2.2 have been completed.

NUREG-1021, Revision 9 3 of 3 REV 0

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: __2 Op-Test No: 2013 Examiners: Operators:

Initial Conditions: (2% power, MOC).

Turnover: Unit 1 is at 2% power (200 EFPD). AFA-P01 and Containment Spray A are tagged out.

Event Malf. No. Event Type* Event Description No.

1 N/A N Shift MFP Lube Oil Pumps per 40OP-9FT02, Feedwater Pump BOP/SRO Turbine B, Section 6.13.

2 cmAVRC03RCEPV100F_1 C Pressurizer spray valve fails open. Crew will respond by selecting cmAVRC03RCEPV100F_2 ATC/SRO unaffected valve using RCN-HS-100-10 in accordance with alarm response procedure.

40AL-9RK4A, Panel B04A Alarm Responses 3 mfRP06L1 C Inadvertent AFAS, B train AFW pumps and valves align to initiate mfRP06L2 BOP/SRO AFW flow to the SGs. Crew takes actions to terminate flow and resulting power increase.

(TS) 40AO-9ZZ17, Inadvertent PPS-ESFAS Actuations 4 cmCNCV04CHNFIC243_2 f:100 I A seal injection controller will fail closed in automatic requiring the ATC/SRO crew to take manual control of the controller.

40AL-9RK3A, Panel B03A Alarm Responses 5 mfED10B C NBN-X04 faults and subsequently the DG will trip on low lube oil rfEG36 f:CLOSE ALL pressure causing a LOP of class 4160 bus, PBB-S04.

(TS) 40AO-9ZZ12, Degraded Electrical; 40AO-9ZZ05, Loss of Letdown 6 mfMS07 f:30 M ESD on common Main Steam header outside containment.

ALL 40EP-9EO05, Excessive Steam Demand.

7 Scenario File noMSIS C MSIS will fail to automatically initiate.

BOP/SRO CRITICAL TASK - Crew manually initiates MSIS after initiation setpoints are exceeded prior to completion of the SPTAs.

8 mfRD03G C Multiple CEAs stick out on the reactor trip. CHE-HV-536 fails to mfRD03L ATC/SRO AUTO-Open.

mfRD03M CRITICAL TASK - Crew establishes > 44 gpm boration prior to cmMVCV08CHEHV536_4 completion of the SPTAs.

40EP-9EO02, Reactor Trip 9 mfED02 M Loss of Grid on Reactor Trip.

ALL 10 mfFW21A C Trip of AFN-P01:

ALL CRITICAL TASK - Implement the FRP to restore power to PBB-S04 and establish AFW flow to the SGs prior to completion of MVAC-2.

40EP-9EO09, Functional Recovery Procedure End Crew has restored AFW flow to the point SGs

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 1 of 3 REV 0

Appendix D Scenario Outline Form ES-D-1 Crew Handout Plant conditions:

Unit 1 is at 2% power.

The plant has been at 2% power for 2 days awaiting repair of AFA-P01.

The core is presently at 250 EFPD.

Risk Management Action Level is ORANGE.

Train B is protected equipment.

AF B, AF N, and CS B are protected in accordance with 40DP-9AP21, Protected Equipment.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header.

CEDMCS is in Manual Sequential Steam Bypass Master Controller SGN-PIC-1010 is in Local Setpoint with SBCV 1004 and 1006 in manual Pressurizer is in Boron Equalization AFN-P01 is in service feeding the SGs thru the Feedwater Isolation bypasses (SGN-HS-1143/1145)

Maintenance on the breaker was completed on Main Lube Oil pump LON-P07B at the end of last shift and it is ready to be tested.

Equipment out of service:

Auxiliary Feedpump A (AFA-P01) is tagged out due to a noisy bearing. LCO 3.7.5 conditions A and C were entered. It is expected to return to service in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

CS A is tagged out for scheduled maintenance. LCO 3.6.6 condition A has been entered. It is expected to return to service in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Planned shift activities:

Shift MFP Lube Oil Pumps per 40OP-9FT02, Feedwater Pump Turbine B, Section 6.13.

NUREG-1021, Revision 9 2 of 3 REV 0

Appendix D Scenario Outline Form ES-D-1 Turnover Plant conditions:

Unit 1 is at 2% power.

The plant has been at 2% power for 2 days awaiting repair of AFA-P01.

The core is presently at 250 EFPD.

Risk Management Action Level is ORANGE.

Train B is protected equipment.

AF B, AF N, and CS B are protected in accordance with 40DP-9AP21, Protected Equipment.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header.

CEDMCS is in Manual Sequential Steam Bypass Master Controller SGN-PIC-1010 is in Local Setpoint with SBCV 1004 and 1006 in manual Pressurizer is in Boron Equalization AFN-P01 is in service feeding the SGs thru the Feedwater Isolation bypasses (SGN-HS-1143/1145)

Maintenance on the breaker was completed on Main Lube Oil pump LON-P07B at the end of last shift and it is ready to be tested.

Equipment out of service:

Auxiliary Feedpump A (AFA-P01) is tagged out due to a noisy bearing. LCO 3.7.5 conditions A and C were entered. It is expected to return to service in 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.

CS A is tagged out for scheduled maintenance. LCO 3.6.6 condition A has been entered. It is expected to return to service in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Planned shift activities:

Shift MFP Lube Oil Pumps per 40OP-9FT02, Feedwater Pump Turbine B, Section 6.13.

NUREG-1021, Revision 9 3 of 3 REV 0

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: __3 Op-Test No: 2013 Examiners: Operators:

Initial Conditions: (100% power, MOC).

Turnover: Unit 1 is at 100% power (250 EFPD). HPSI A Pump is tagged out.

Event Malf. No. Event Type* Event Description No.

1 N/A N Shift CEDM HVAC fans in accordance with 40OP-9HC01, BOP/SRO Containment HVAC, Section 4.4.

2 cmCNCV01CHEPDIC240_2 C Charging Header D/P controller will fail in the AUTO mode f:100 ATC/SRO requiring the crew to take manual control of PDIC-240 in accordance with associated alarm response procedure.

40AL-9RK3A, Panel B03A Alarm Responses 3 cmTRMS17SGNFT1011_4 I Steam Generator flow transmitter FT-1011 will fail requiring BOP/SRO the crew to place it in maintenance mode and remove the three-element lockout on the DFWCS in accordance with associated alarm response procedure.

40AL-9RK6A, Panel B06A Alarm Responses 4 mfTH07 f:6 C A small non-isolable RCS instrument leak inside containment.

ATC/SRO The crew will enter 40AO-9ZZ02, Excessive RCS Leakrate and perform a leakrate calculation. The CRS will address (TS/AOP) Technical Specifications.

5 mfRD02B R - SRO, CEA 15 will drop requiring entry into 40AO-9ZZ11, CEA ATC Malfunctions. The crew will begin a power reduction. The C - BOP CRS will address Technical Specifications.

(TS/AOP) CRITICAL TASK - Crew begins power reduction within 10 minutes of dropped CEA.

6 mfTH01 f:1 (2 minute ramp) M RCS leak will degrade to the point of exceeding the capacity of ALL the charging pumps requiring a Reactor Trip.

40EP-9EO01, SPTAs 7 mfED10B (NBN-X04 fault) C A phase-to-phase fault will occur on NBN-X04 causing PBB-cmBKEG03PBBS04B_2 ATC/SRO S04 to lose power. The DG supply breaker will fail to automatically close requiring the Reactor Operator to manually close it onto PBB-S04.

CRITICAL TASK - Crew will close DG supply breaker to energize PBB-S04 prior to completion of SPTAs.

8 cmCPSI01SIBP02_5 C HPSI Pump B will fail to auto start.

ATC/SRO CRITICAL TASK - Crew will manually start HPSI B prior to exiting LOCA EOP.

End Crew establishes adequate HPSI point flow to RCS per Standard Appendix 2.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 1 of 3 REV 0

Appendix D Scenario Outline Form ES-D-1 Crew Handout Plant conditions:

Unit 1 is at 100% power.

The core is presently at 250 EFPD.

Risk Management Action Level is GREEN HPSI B Pump is protected in accordance with 40DP-9AP21, Protected Equipment Train B is protected.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header.

Equipment out of service:

HPSI A Pump is under clearance for bearing inspection. LCO 3.5.3 Condition B has been entered. The pump is expected to return to service in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Planned shift activities:

Shift CEDM HVAC fans for upcoming engineering evaluation of the system.

NUREG-1021, Revision 9 2 of 3 REV 0

Appendix D Scenario Outline Form ES-D-1 Turnover Plant conditions:

Unit 1 is at 100% power.

The core is presently at 250 EFPD.

Risk Management Action Level is GREEN HPSI B Pump is protected in accordance with 40DP-9AP21, Protected Equipment Train B is protected.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header.

Equipment out of service:

HPSI A Pump is under clearance for bearing inspection. LCO 3.5.3 Condition B has been entered. The pump is expected to return to service in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Planned shift activities:

Shift CEDM HVAC fans for upcoming engineering evaluation of the system.

NUREG-1021, Revision 9 3 of 3 REV 0

Appendix D Scenario Outline Form ES-D-1 Facility: PVNGS Scenario No.: __4 Op-Test No: 2013 Examiners: Operators:

Initial Conditions: (100% power, MOC).

Turnover: Unit 1 is at 100% power (250 EFPD). HPSI A Pump is tagged out.

Event Malf. No. Event Type* Event Description No.

1 N/A N Remove Reactor Power Cutback System from service in accordance BOP/SRO with40OP-9SF05, Operation of the Steam Bypass Control System, Section 4.4.

2 cmTRCV19RCALT110X_1f:0 I Pressurizer Level Transmitter LT-110X will fail low. Crew will take ATC/SRO actions per alarm response procedures and take the Pressurizer Level (TS) Control Selector Switch to CH Y. Technical Specifications will be addressed for PAM Instrumentation.

40AL-9RK4A, Panel B04A Alarm Responses 3 cmCPHV12HJNA02_2 C Control Room Normal AHU Fan A02 will trip on electrical ATC/SRO protection. The alarm response procedure will direct the Reactor Operator to start a Control Room Essential AHU per 40OP-9HJ01, Control Building HVAC.

41AL-1RK2A, Panel B02A Alarm Responses 4 cmTRMS03MTNPT11A_1 f:0 I The 1st Stage Pressure Transmitter to Reactor Regulating System BOP/SRO (TLI) will fail low. Crew will respond by taking actions per alarm (AOP) response procedures and 40AO-9ZZ16, RRS Malfunctions.

5 mfCW01A f:200 R - SRO, ATC A Circulating Water leak will develop in the Main Condenser C - BOP requiring entry into 40AO-9ZZ10, Condenser Tube Rupture. The (AOP) crew will perform a downpower in order to isolate the affected loop.

6 mfRP06G1 C An inadvertent Containment Spray Actuation will occur which will mfRP06G2 BOP/SRO require entry into 40AO-9ZZ17, Inadvertent PPS-ESFAS (TS/AOP) Actuations.

CRITICAL TASK - Restore NCW flow to RCPs within 10 minutes of RCP Low NCW Flow alarms.

7 cmCPRC02RCEP01B_1 M RCP 1B pump will experience a shaft shear creating a loop low flow ALL condition requiring a Reactor Trip. Crew enters Standard Post Trip Actions procedure.

40EP-9EO01, SPTAs 8 mfRD12A C Due to a failure of the RPS system, an ATWS will occur. The crew mfRP04A ATC/SRO will be required to open NGN-L03B2 and NGN-L10B2 breakers in mfRP04C order to trip the reactor.

CRITICAL TASK - After RPS trip setpoint has been exceeded, ensure the contingency actions of Reactivity Control are taken prior to completion of SPTAs.

9 cmTRMS02SGNPT1024_1 I Steam Generator Pressure Transmitter PT-1024 will fail low. This f:900 BOP/SRO will result in the SBCS not receiving a modulate demand to control SG pressure. The crew will take manual control of SBCS or SG ADVs in order to control SG pressure.

CRITICAL TASK - Take manual control of SG pressure using SBCS or ADVs to control SG pressure below SG safety valve setpoints prior to completion of SPTAs.

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 9 1 of 3 REV 0

Appendix D Scenario Outline Form ES-D-1 Crew Handout Plant conditions:

Unit 1 is at 100% power.

The core is presently at 250 EFPD.

Risk Management Action Level is GREEN HPSI B Pump is protected in accordance with 40DP-9AP21, Protected Equipment Train B is protected.

SBCS Master Controller was placed in MANUAL for I&C testing. Testing has been completed.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header.

Equipment out of service:

HPSI A Pump is under clearance for bearing inspection. LCO 3.5.3 Condition B has been entered. The pump is expected to return to service in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Planned shift activities:

Remove Reactor Power Cutback System from service in accordance with 40OP-9SF05, Operation of the Steam Bypass Control System, Section 4.4 due to overheating components.

NUREG-1021, Revision 9 2 of 3 REV 0

Appendix D Scenario Outline Form ES-D-1 Turnover Plant conditions:

Unit 1 is at 100% power.

The core is presently at 250 EFPD.

Risk Management Action Level is GREEN HPSI B Pump is protected in accordance with 40DP-9AP21, Protected Equipment Train B is protected.

SBCS Master Controller was placed in MANUAL for I&C testing. Testing has been completed.

PC is NOT recircing the RWT.

Unit 2 is supplying the Aux Steam cross-tie header.

Equipment out of service:

HPSI A Pump is under clearance for bearing inspection. LCO 3.5.3 Condition B has been entered. The pump is expected to return to service in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Planned shift activities:

Remove Reactor Power Cutback System from service in accordance with 40OP-9SF05, Operation of the Steam Bypass Control System, Section 4.4 due to overheating components.

NUREG-1021, Revision 9 3 of 3 REV 0