ML14242A027

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2013-03-Final Outlines
ML14242A027
Person / Time
Site: Callaway Ameren icon.png
Issue date: 03/18/2013
From: Vincent Gaddy
Operations Branch IV
To:
Ameren Corp, Union Electric Co
References
50-483/13-003, ES-401, ES-401-2 50-483/OL-13
Download: ML14242A027 (37)
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Text

ES-401 PWR Examination Outline Form ES-401-2 Facility: Callaway Date of Exam: March 25, 2013 Rev 1 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 3 3 3 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 3 2 3 2 2 2 2 3 3 3 3 28 3 2 5 2.

Plant 2 1 1 1 1 1 1 0 1 1 1 1 10 1 1 1 3 Systems Tier Totals 4 3 4 3 3 3 2 4 4 4 4 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.

CW-2013-03-Written Exam Outline Rev 0

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 000008 Pressurizer Vapor Space AK3.04 - Knowledge of the reasons for the following responses as they X 4.2 1 Accident / 3 apply to the Pressurizer Vapor Space Accident: RCP tripping requirements.

EK1.02 - Knowledge of the operational implications of the following concepts 000009 Small Break LOCA / 3 X 3.5 2 as they apply to the small break LOCA: Use of steam tables.

EA1.11 - Ability to operate and monitor the following as they apply to a 000011 Large Break LOCA / 3 X 4.2 3 Large Break LOCA: Long-term cooling of core.

AK1.01 - Knowledge of the operational implications of the following concepts 000015/17 RCP Malfunctions / 4 X as they apply to Reactor Coolant Pump Malfunctions (Loss of RC Flow): 4.4 4 Natural circulation in a nuclear reactor power plant.

000025 Loss of RHR System / 4 X 2.1.32 - Ability to explain and apply system limits and precautions. 3.8 5 000026 Loss of Component Cooling AA2.01 - Ability to determine and interpret the following as they apply to the X 2.9 6 Water / 8 Loss of Component Cooling Water: Location of a leak in the CCWS.

000027 Pressurizer Pressure Control AK2.03 - Knowledge of the interrelations between the Pressurizer Pressure X 2.6 7 System Malfunction / 3 Control Malfunctions and the following: Controllers and positioners.

EK3.11 - Knowledge of the reasons for the following responses as they 000029 ATWS / 1 X 4.2 8 apply to the ATWS: Initiating emergency boration.

2.2.42 - Ability to recognize system parameters that are entry-level 000038 Steam Gen. Tube Rupture / 3 X 3.9 9 conditions for Technical Specifications.

CW-2013-03-Written Exam Outline 2 Rev 0

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

EA1.1 - Ability to operate and / or monitor the following as they apply to the 000040 (BW/E05; CE/E05; W/E12)

Steam Line Rupture - Excessive Heat (Uncontrolled Depressurization of all Steam Generators): Components, and X 3.8 10 Transfer / 4 functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

EA2.06 - Ability to determine or interpret the following as they apply to a 000055 Station Blackout / 6 X Station Blackout: Faults and lockouts that must be cleared prior to re- 3.7 11 energizing buses.

AA1.21 - Ability to operate and / or monitor the following as they apply to the 000056 Loss of Off-site Power / 6 X 3.3 12 Loss of Offsite Power: Reset of the ESF load sequencers.

AK3.01 - Knowledge of the reasons for the following responses as they 000057 Loss of Vital AC Inst. Bus / 6 X apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for 4.1 13 loss of vital ac electrical instrument bus.

AK1.01 - Knowledge of the operational implications of the following concepts 000058 Loss of DC Power / 6 X as they apply to Loss of DC Power: Battery charger equipment and 2.8 14 instrumentation.

000062 Loss of Nuclear Svc Water / 4 X 2.4.6 - Knowledge of EOP mitigation strategies. 3.7 15 EK2.1 - Knowledge of the interrelations between the (Loss of Emergency W/E11 Loss of Emergency Coolant Recirc. / 4 Coolant Recirculation) and the following: Components, and functions of X 3.6 16 control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

EK2.2 - Knowledge of the interrelations between the (Loss of Secondary BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 Heat Sink) and the following: Facilitys heat removal systems, including X primary coolant, emergency coolant, the decay heat removal systems, and 3.9 17 relations between the proper operation of these systems to the operation of the facility.

CW-2013-03-Written Exam Outline 3 Rev 0

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

AA2.10 - Ability to determine and interpret the following as they apply to 000077 Generator Voltage and Electric Grid Disturbances / 6 X Generator Voltage and Electric Grid Disturbances: Generator overheating 3.6 18 and the required actions.

K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18 CW-2013-03-Written Exam Outline 4 Rev 0

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 AK1.21 - Knowledge of the operational implications of the following 2.9 19 X concepts as they apply to Continuous Rod Withdrawal: Integral rod worth.

000024 Emergency Boration / 1 AA1.26 - Ability to operate and / or monitor the following as they 3.3 20 X

apply to Emergency Boration: Boric acid storage tank.

000036 (BW/A08) Fuel Handling Accident / 8 AA2.02 - Ability to determine and interpret the following as they 3.4 21 X apply to the Fuel Handling Incidents: Occurrence of a fuel handling incident.

000037 Steam Generator Tube Leak / 3 AA2.16 - Ability to determine and interpret the following as they 4.1 22 X apply to the Steam Generator Tube Leak: Pressure at which to maintain RCS during S/G cooldown.

000067 Plant Fire On-site / 8 2.4.46 - Ability to verify that the alarms are consistent with the plant 4.2 23 X

conditions.

000068 (BW/A06) Control Room Evac. / 8 AK3.12 - Knowledge of the reasons for the following responses as 4.1 24 X they apply to the Control Room Evacuation: Required sequence of actions for emergency evacuation of control room.

000069 (W/E14) Loss of CTMT Integrity / 5 EK2.1 - Knowledge of the interrelations between the (High Containment Pressure) and the following: Components, and X functions of control and safety systems, including instrumentation, 3.4 25 signals, interlocks, failure modes, and automatic and manual features.

CW-2013-03-Written Exam Outline 5 Rev 0

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

W/E01 & E02 Rediagnosis & SI Termination / 3 EA1.1 (E01) - Ability of operate and / or monitor the following as they apply to the (Reactor Trip or Safety Injection/Rediagnosis):

X Components, and functions of control and safety systems, 3.7 26 including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 EK3.3 (E09) - Knowledge of the reasons for the following responses as they apply to the (Natural Circulation Operations): Manipulations X

of controls required to obtain desired operating results during 3.5 27 abnormal, and emergency situations.

K/A Category Point Totals: 1 1 2 2 2 1 Group Point Total: 9 CW-2013-03-Written Exam Outline 6 Rev 0

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 K3.03 - Knowledge of the effect that a loss or malfunction of the X RCPS will have on the following: Feedwater and emergency 2.8 28 feedwater.

004 Chemical and Volume K6.17 - Knowledge of the effect of a loss or malfunction on the X 4.4 29 Control following CVCS components: Flow paths for emergency boration.

004 Chemical and Volume A1.04 - Ability to predict and/or monitor changes in parameters (to Control X prevent exceeding design limits) associated with operating the 3.9 30 CVCS controls including: PZR pressure and level.

005 Residual Heat Removal K2.03 - Knowledge of bus power supplies to the following: RCS X 2.7 31 pressure boundary motor-operated valves.

006 Emergency Core Cooling K5.06 - Knowledge of the operational implications of the following X concepts as they apply to ECCS: Relationship between ECCS 3.5 32 flow and RCS pressure.

007 Pressurizer Relief/Quench A4.10 - Ability to manually operate and/or monitor in the control X 3.6 33 Tank room: Recognition of leaking PORV/code safety.

008 Component Cooling Water K1.01 - Knowledge of the physical connections and/or cause-X effect relationships between the CCWS and the following 3.1 34 systems: SWS.

008 Component Cooling Water A3.02 - Ability to monitor automatic operation of the CCWS, X including: Operation of the CCW pumps, including interlocks and 3.2 35 the CCW booster pump.

CW-2013-03-Written Exam Outline 7 Rev 0

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO) 010 Pressurizer Pressure Control K6.01 - Knowledge of the effect of a loss or malfunction of the X 2.7 36 following will have on the PZR PCS: pressure detection systems.

012 Reactor Protection K2.01 (JAN2011) - Knowledge of bus power supplies to the X 3.3 37 following: RPS channels, components, and interconnections.

012 Reactor Protection A2.06 - Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those X predictions, use procedures to correct, control, or mitigate the 4.4 38 consequences of those malfunctions or operations: Failure of RPS signal to trip the reactor.

013 Engineered Safety Features K1.12 - Knowledge of the physical connections and/or cause Actuation X effect relationships between the ESFAS and the following 4.1 39 systems: ED/G.

022 Containment Cooling A4.05 - Ability to manually operate and/or monitor in the control X room: Containment readings of temperature, pressure, and 3.8 40 humidity system.

026 Containment Spray A3.01 - Ability to monitor automatic operation of the CSS, X 4.3 41 including: Pump starts and correct MOV positioning.

026 Containment Spray 2.4.49 - Ability to perform without reference to procedures those X actions that require immediate operation of system components 4.6 42 and controls.

039 Main and Reheat Steam K4.04 - Knowledge of MRSS design feature(s) and/or interlock(s) which provide for the following: Utilization of steam pressure X 2.9 43 program control when steam dumping through atmospheric relief/dump valve, including T-ave. limits.

059 Main Feedwater K3.04 - Knowledge of the effect that a loss or malfunction of the 3.6 44 X

MFW will have on the following: RCS.

CW-2013-03-Written Exam Outline 8 Rev 0

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO) 061 Auxiliary/Emergency K3.02- Knowledge of the effect that a loss or malfunction of the Feedwater X 4.2 45 AFW will have on the following: S/G.

061 Auxiliary/Emergency K5.02 - Knowledge of the operational implications of the following Feedwater X concepts as they apply to the AFW: Decay heat sources and 3.2 46 magnitude.

062 AC Electrical Distribution K4.01 - Knowledge of ac distribution system design feature(s)

X 2.6 47 and/or interlocks(s) which provide for the following: Bus lockouts.

062 AC Electrical Distribution A1.01 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the ac X 3.4 48 distribution system control including: Significance of D/G load limits.

063 DC Electrical Distribution A4.03 - Ability to manually operate and/or monitor in the control X 3.0 49 room: Battery discharge rate.

064 Emergency Diesel Generator A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or X 2.7 50 mitigate the consequences of those malfunctions or operations:

Load, VARS, pressure on air compressor, speed droop, frequency, voltage, fuel oil level, temperatures.

064 Emergency Diesel Generator 2.4.45 - Ability to prioritize and interpret the significance of each X 4.1 51 annunciator or alarm.

073 Process Radiation 2.1.18 - Ability to make accurate, clear, and concise logs, records, Monitoring X 3.6 52 status boards, and reports.

076 Service Water K1.01 - Knowledge of the physical connections and/or cause-X effect relationships between the SWS and the following systems: 3.4 53 CCW system.

CW-2013-03-Written Exam Outline 9 Rev 0

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO) 078 Instrument Air A3.01 - Ability to monitor automatic operation of the IAS, X 3.1 54 including: Air pressure.

103 Containment A2.05 - Ability to (a) predict the impacts of the following malfunctions or operations on the containment system and (b)

X based on those predictions, use procedure to correct, control, or 2.9 55 mitigate the consequences of those malfunctions or operations:

Emergency containment entry.

K/A Category Point Totals: 3 2 3 2 2 2 2 3 3 3 3 Group Point Total: 28 CW-2013-03-Written Exam Outline 10 Rev 0

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 4 002 Reactor Coolant X 2.4.11 - Knowledge of abnormal condition procedures. 4.0 56 K2.01 - Knowledge of bus power supplies to the following: Charging 011 Pressurizer Level Control X 3.1 57 pumps.

K5.01 - Knowledge of the operational implications of the following 014 Rod Position Indication X concepts as they apply to the RPIS: Reasons for differences 2.7 58 between RPIS and step counter.

K3.12 - 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: S/G.

K4.05 - Knowledge of design feature(s) and/or interlock(s) which 033 Spent Fuel Pool Cooling X 3.1 60 provide for the following: Adequate SDM (boron concentration).

A4.02 - Ability to manually operate and/or monitor in the control 034 Fuel Handling Equipment X 3.5 61 room: Neutron levels.

035 Steam Generator K6.01 - Knowledge of the effect of a loss or malfunction on the X 3.2 62 following will have on the S/Gs: MSIVs.

041 Steam Dump/Turbine A3.05 - Ability to monitor automatic operation of the SDS, including:

X 2.9 63 Bypass Control Main steam pressure.

045 Main Turbine Generator K1.18 - Knowledge of the physical connections and/or cause-effect X relationships between the MT/G system and the following systems: 3.6 64 RPS.

CW-2013-03-Written Exam Outline 11 Rev 0

ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO) 001 Control Rod Drive A2.14 - Ability to (a) predict the impacts of the following malfunction or operations on the CRDS and (b) based on those predictions, X use procedures to correct, control, or mitigate the consequences of 3.7 65 those malfunctions or operations: Urgent failure alarm, including rod-out-of-sequence and motion-inhibit alarms.

K/A Category Point Totals: 1 1 1 1 1 1 0 1 1 1 1 Group Point Total: 10 CW-2013-03-Written Exam Outline 12 Rev 0

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 000008 Pressurizer Vapor Space AA2.30 - Ability to determine and interpret the following as they apply to the Accident / 3 X Pressurizer Vapor Space Accident: Inadequate core cooling. 4.3 76 000029 ATWS / 1 X 2.4.18 - Knowledge of the specific bases for EOPs. 4.0 77 000055 Station Blackout / 6 EA2.03 - Ability to determine or interpret the following as they apply to a X 3.9 78 Station Blackout: Actions necessary to restore power.

000057 Loss of Vital AC Inst. Bus / 6 X 2.2.37 - Ability to determine operability and/or availability of safety related 4.6 79 equipment.

W/E11 Loss of Emergency Coolant X EA2.2 - Ability to determine and interpret the following as they apply to the Recirc. / 4 (Loss of Emergency Coolant Recirculation): Adherence to appropriate 4.2 80 procedures and operation within the limitations in the facilitys license and amendments.

000077 Generator Voltage and Electric 2.2.36 - Ability to analyze the effect of maintenance activities, such as X 4.2 81 Grid Disturbances / 6 degraded power sources, on the status of limiting conditions for operations.

K/A Category Totals: 3 3 Group Point Total: 6 CW-2013-03-Written Exam Outline 13 Rev 0

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 X AA2.03 - Ability to determine and interpret the following as they apply to the Continuous Rod Withdrawal: Proper actions to be 4.5 82 taken if automatic safety functions have not taken place.

000067 Plant Fire On-site / 8 X 2.1.6 - Ability to manage the control room crew during plant 4.8 83 transients.

000069 (W/E14) Loss of CTMT Integrity / 5 X 2.4.41 - Knowledge of the emergency action level thresholds and 4.6 84 classifications.

W/E01 & E02 Rediagnosis & SI Termination / 3 X EA2.1 (E01) - Ability to determine and interpret the following as they apply to the (Reactor Trip or Safety Injection Rediagnosis): Facility 4.0 85 conditions and selection of appropriate procedures during abnormal and emergency operations.

K/A Category Point Totals: 2 2 Group Point Total: 4 CW-2013-03-Written Exam Outline 14 Rev 0

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 4 012 Reactor Protection A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those X predictions, use procedures to correct, control, or mitigate the 3.7 86 consequences of those malfunctions or operations: Incorrect channel bypassing.

061 Auxiliary/Emergency 2.2.22 - Knowledge of limiting conditions for operations and safety Feedwater X 4.7 87 limits.

063 DC Electrical Distribution X 2.1.20 - Ability to interpret and execute procedure steps. 4.6 88 064 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 X on those predictions, use procedures to correct, control, or 3.3 89 mitigate the consequences of those malfunctions or operations:

Operating unloaded, lightly loaded, and highly loaded time limit.

103 Containment A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the containment system; and (b)

X based on those predictions, use procedures to correct, control, or 3.8 90 mitigate the consequences of those malfunctions or operations:

Phase A and B isolation.

K/A Category Point Totals: 3 2 Group Point Total: 5 CW-2013-03-Written Exam Outline 15 Rev 0

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 4 034 Fuel Handling Equipment K4.02 - Knowledge of design feature(s) and/or interlocks(s) which X 3.3 91 provide for the following: Fuel movement.

041 Steam Dump/Turbine 2.1.23 - Ability to perform specific system and integrated plant Bypass Control X 4.4 92 procedures during all modes of plant operation.

045 Main Turbine Generator X A2.17- Ability to (a) predict the impacts of the following malfunctions or operation on the MT/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the 2.9 93 consequences of those malfunctions or operations: Malfunction of electrohydraulic control.

K/A Category Point Totals: 1 1 1 Group Point Total: 3 CW-2013-03-Written Exam Outline 16 Rev 0

ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-3 Facility: Callaway Date of Exam: March 25, 2013 RO SRO-Only Category K/A # Topic IR # IR #

2.1.14 Knowledge of criteria or conditions that require plant-wide announcements, such as 3.1 66 pump starts, reactor trips, mode changes, etc.

1.

Conduct 2.1.26 Knowledge of industrial safety procedures (such as rotating equipment, electrical, high 3.4 67 of Operations temperature, high pressure, caustic, chlorine, oxygen and hydrogen).

2.1.44 Knowledge of RO duties in the control room during fuel handling, such as responding 3.9 68 to alarms from the fuel handling area, communication with the fuel storage facility, systems operated from the control room in support of fueling operations, and supporting instrumentation.

2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, 3.9 94 overtime limitations, etc.

2.1.23 Ability to perform specific system and integrated plant procedures during all modes of 4.4 95 plant operation.

Subtotal 3 2 2.2.12 (JAN2011) - Knowledge of surveillance procedures. 3.7 69 2.2.13 Knowledge of tagging and clearance procedures. 4.1 70 2.

Equipment Control 2.2.35 Ability to determine Technical Specification Mode of Operation. 3.6 71 CW-2013-03-Written Exam Outline 17 Rev 0

Facility: Callaway Date of Exam: March 25, 2013 RO SRO-Only Category K/A # Topic IR # IR #

2.2.7 (JUN2011) - Knowledge of the process for conducting special or infrequent tests. 3.6 96 2.2.17 Knowledge of the process for managing maintenance activities during power 3.8 97 operations, such as risk assessments, work prioritization, and coordination with the transmission system operator.

Subtotal 3 2 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. 3.2 72 2.3.13 (JAN2011) - Knowledge of radiological safety procedures pertaining to licensed 3.4 73 3.

Radiation operator duties, such as response to radiation monitor alarms, containment entry Control requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, 3.8 98 abnormal, or emergency conditions or activities.

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

4.

Emergency 2.4.14 Knowledge of general guidelines for EOP usage. 3.8 75 Procedures /

Plan 2.4.9 Knowledge of low power/shutdown implications in accident (e.g, loss of coolant 4.2 99 accident or loss of residual heat removal) mitigation strategies.

CW-2013-03-Written Exam Outline 18 Rev 0

Facility: Callaway Date of Exam: March 25, 2013 RO SRO-Only Category K/A # Topic IR # IR #

2.4.28 Knowledge of procedures relating to a security event (non-safeguards information). 4.1 100 Subtotal 2 2 Tier 3 Point Total 10 7 CW-2013-03-Written Exam Outline 19 Rev 0

ES-401 Record of Rejected K/As Form ES-401-4 Tier/

Randomly Group/ Reason for Rejection Selected K/A Question 1/1 Could not develop a psychometrically sound question for selected 015/017 AK1.01 K/A, AK1.05. Randomly reselected new system in Tier Group Q#4 under same K/A section (AK1).

2/1 Could not develop a psychometrically sound question for selected 026G2.4.49 K/A, G2.4.9. Randomly reselected from within same Generic Q#42 Section, 2.4.

There are no local controls associated with the Process Radiation 2/1 Monitoring System that licensed personnel are responsible for.

073G2.1.18 Q#52 Randomly reselected from within same Generic Section, 2.1.

Original K/A was G2.1.30.

Oversampling of Fire Protection subject - there were 3 questions related to this subject. Randomly reselected new system in Tier 2/2 Group under same K/A section (A2). Original K/A was 086 Fire 001A2.14 Q#65 Protection), A2.02. Other questions related to Fire Protection are:

Q#23, K/A 067, Plant Fire On-site, G2.4.46, and Q#83, K/A 067, Plant Fire On-site, G2.1.6.

Could not develop a discriminatory RO only question from selected 3/2 2.2.35 topic, K/A G2.2.36. Randomly reselected from within same Q#71 Generic Section, 2.2.

Could not develop a discriminatory SRO only question from 1/2 067G2.1.6 selected topic, K/A G2.1.28. Randomly reselected from within Q#83 same Generic Section, 2.1.

Could not develop a discriminatory SRO only question from 2/1 103A2.03 original K/A, A2.05. Randomly reselected from within same topic Q#90 area (A2).

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Callaway Date of Examination: 3/18/2013 Examination Level: RO Operating Test Number: 2013301, Rev 2 Administrative Topic Type Describe activity to be performed (see Note) Code*

Calculate a Shutdown Margin (A1) Conduct of Operations R, N 2.1.37 (4.3) Knowledge of procedures, guidelines, or limitations associated with reactivity management.

Calculate Volume of Water to Transfer Between RWST and Spent Fuel Pool.

(A2) Conduct of Operations R, N 2.1.25 (3.9) Ability to interpret reference materials, such as graphs, curves, tables, etc.

Determine Amperage Limits for 480 VAC Safety Related busses.

(A3) Equipment Control R, N 2.2.37 (3.6) Ability to determine operability and/or availability of safety related equipment.

Radiation Control N/A Determine Correct Functional Restoration Guideline (FRG) Procedure Implementation.

(A4) Emergency R, N 2.4.14 (3.8) Knowledge of general guidelines for EOP Procedures/Plan usage.

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)

RO ADMIN JPM

SUMMARY

A1 This is a new JPM. The applicant will calculate an at power Shutdown Margin.

The plant computer is not available and the calculation must be manually performed.

A2 This is a new JPM. The applicant will calculate the amount of water required to test the Spent Fuel Pool (SFP) high level alarm. The water will come from the RWST and the candidate must determine if there is sufficient volume in the RWST to perform the SFP test without lowering below the Technical Specification low level limit.

A3 This is a new JPM. The applicant will review planned maintenance which requires load centers NG01 and NG03 to be cross-connected. The applicant will be required to determine what equipment can be started on the cross-connected load centers without overloading the buses.

A4 This is a new JPM. The applicant will review the Critical Safety Functions (CSFs) following a plant event. Upon completion of this review, the applicant will report to the CRS that the highest priority CSF that needs to be addressed is Core Cooling and that FR-C.2, Response to Degraded Core Cooling should be implemented.

Rev 2

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Callaway Date of Examination: 3/18/2013 Examination Level: SRO Operating Test Number: 2013301 Rev. 2 Administrative Topic Type Describe activity to be performed (see Note) Code*

Evaluate Conditions for Restart of Refueling Preshuffle.

(A5) Conduct of Operations R, M 2.1.35 (3.9) Knowledge of the fuel-handling responsibilities of SROs.

Review Shiftly Logs (A6) Conduct of Operations R, N 2.1.18 (3.8) Ability to make accurate, clear, and concise logs, records, status boards, and reports.

Perform a Risk Assessment during Shutdown Conditions.

(A7) Equipment Control R, N 2.2.18 (3.9) Knowledge of the process for managing maintenance activities during shutdown operations, such as risk assessments, work prioritization, etc.

Determine Estimated Dose and Make Shielding Recommendation.

(A8) Radiation Control R, D 2.3.12 (3.7) Knowledge of radiological safety principles pertaining to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

Initiate RERP Implementation to Include Event Classification and Initial Offsite Notification.

(A9) Emergency R, D 2.4.41 (4.6) Knowledge of the emergency action level Procedures/Plan thresholds and classification.

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)

SRO ADMIN JPM

SUMMARY

A5 This is a bank JPM modified from the 2011 Turkey Point Exam. The applicant will be given a set of plant conditions and OOS equipment associated with recommencing shuffling of irradiated fuel assemblies in the Spent Fuel Pool. The applicant will evaluate the given conditions as to whether irradiated fuel can be moved. Of the conditions provided to the applicant, four items would prevent the movement of irradiated fuel assemblies in the Spent Fuel Pool.

A6 This is a new JPM. The applicant will be given 10 pages of a set of manual Control Room logs that have been taken due to the unavailability of Auto Tour.

The applicant will review the logs and inform the RO of any changes or plant issues that need to be addressed based on this review. There are seven issues to be identified on the logs; the applicant must identify at least six of the seven issues to successfully complete this JPM.

A7 This is a new JPM. The applicant will perform a Shutdown Safety Assessment for Power Availability IAW EDP-ZZ-01129 based on a set of given conditions.

After this review, the applicant will have determined that there are 5 credit points available for Power Availability and the Risk Assessment condition color is Green.

A8 This is a bank JPM from the 2012 Ft. Calhoun Exam. The applicant will calculate the total dose for a maintenance job in the Auxiliary Building, with and without temporary shielding installed. The applicant will make a recommendation of whether to request temporary shielding for the job or to perform the job without temporary shielding installed. The addition of shielding reduces the total dose for the job; therefore the applicant should recommend temporary shielding be installed.

A9 This is a Callaway Bank JPM [SRO-RER-02-A119J (TC)]. The applicant will be given a set of plant conditions and will implement the Radiological Emergency Response Plan (RERP) to classify the event within 15 minutes (Time Critical) and then make the initial notifications to offsite agencies within 15 minutes (Time Critical).

Rev 2

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Callaway Date of Examination: 3/18/2013 Exam Level: RO (only) / SRO-I / SRO-U Operating Test No.: 2013301, Rev.3 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 004 Chemical and Volume Control System N, S, A, E 1 Borate Reactor Coolant System for Power Change S2 010 Reactor Coolant System (BB)

D, S 3 Perform System Surveillance - BBHV8000A Stroke Test S3 013 Engineered Safety Features Actuation System (ESFAS) M, S, A, E, 2

EN, L Perform Attachment A of E-0 S4 007 Pressurizer Relief Tank (PRTS)

N, S 5 Drain PRT to Containment Normal Sump (RO ONLY)

S5 059 Main Feedwater System D, S, A 4S Transfer A MFP Speed Control / Pump Trip S6 062 A.C. Electrical Distribution Perform Operational Testing of the Alternate Emergency N, S 6 Power Source S7 005 Residual Heat Removal System N, S, L, 4P Transfer to Cold Leg Recirculation A, E S8 029 Containment Purge System N, S 8 Remove Containment Mini-Purge System From Service In-Plant Systems (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P1 055 Station Blackout D, A 6 Locally Start (NE01) Emergency Diesel P2 059 Main Feedwater (MFW) System D 4S Locally Operate A Main Feedwater Regulating Valve P3 033 Spent Fuel Pool Cooling System M, R 8 Place RWST in Recirculation

@ 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 (5) / 4-6 (5) / 2-3 (3)

(C)ontrol room (0) / (0) / (0)

(D)irect from bank 9 (4) 8 (4) / 4 (2)

(E)mergency or abnormal in-plant 1 (3) / 1 (3) / 1 (2)

(EN)gineered safety feature - (1) / - (1) / 1 (1) (control room system)

(L)ow-Power / Shutdown 1 (2) / 1 (2) / 1 (1)

(N)ew or (M)odified from bank including 1(A) 2 (7) / 2 (6) / 1 (3)

(P)revious 2 exams 3 (0) / 3 (0) / 2 (0) (randomly selected)

(R)CA 1 (1) / 1 (1) / 1 (1)

(S)imulator (8) (7) (2)

Rev 3

JPM Summary S1 This is a NEW JPM. The applicant will be assigned the task of borating the RCS for a plant shutdown due to a S/G tube leak IAW OTO-MA-00008, Rapid Load Reduction. Both normal boration to the VCT and emergency boration from the Boric Acid Storage Tank will not be successful due to equipment malfunctions. The applicant will have to use the RNO option of borating from the RWST, which will be successful (ALTERNATE PATH).

S2 This is a BANK JPM [URO-SBB05C77J (A)]. The applicant will perform the stroke time test for BBHV8000A, Reactor Coolant System Pressurizer PORV Block Valve, per OSP-BB-V00001, RCS Valve Inservice Test. When the valve is stroked, its closing and opening times exceed the allowable times. The acceptance criterion is not met and the valve fails its surveillance with notification provided to the CRS.

S3 This JPM is MODIFIED from BANK JPM URO-AEO01C184J (A). The applicant will be assigned Attachment A of E-0, Reactor Trip or Safety Injection.

When verifying equipment status the applicant will find equipment that failed to properly actuate on the SI signal. This JPM was modified from the bank JPM in that it includes different equipment that must be manually started (ALTERNATE PATH).

S4 This is a NEW JPM. The Pressurizer Relief Tank (PRT) has a high level due to valve testing with its associated high level alarm activated. The applicant will be required to drain the PRT to the containment normal sump sufficiently to clear the tank high level alarm and not actuate the low level alarm.

S5 This is a BANK JPM repeated from the 2007 License Exam. The applicant will be directed to transfer MFP control from Auto to Manual on the GE Controller.

During the process of completing the transfer the pump will develop bearing problems resulting in high thrust bearing oil temperature. ALTERNATE PATH action will be required by the applicant to trip the pump in accordance with OTA-RK-00026 annunciator response.

S6 This is a NEW JPM. The applicant will be assigned the task of performing an online test of Alternate Emergency Power Source Diesel Generator #4 from the Control Room. The diesel will be started, readings taken and then secured from the Control Room.

S7 This is a NEW JPM. The simulator will be set up following a large Loss of Coolant Accident. The applicant will be directed to transfer the Emergency Core Cooling System to the recirculation mode in accordance with ES-1.3, Transfer to Cold Leg Recirculation. During performance, the applicant finds valves out of position and must use the Response Not Obtained column to complete the task (ALTERNATE PATH).

Rev 3

S8 This is a NEW JPM. The containment mini-purge system is in service. The applicant will be directed to remove the containment mini-purge system from service in accordance with OTN-GT-00001, Containment Purge System.

P1 This is a BANK JPM (URO-AEO05059J(A)). In the plant, the applicant will simulate locally starting an emergency diesel generator (EDG) which fails to start following a loss of all AC Power. The applicant will first try to reset the Engine Shutdown Relay to start the EDG. When this fails to start the EDG, the emergency start pop-out button will be actuated, which also fails to start the EDG. The applicant will then take local control of the EDG and will start the EDG with the local start button (ALTERNATE PATH).

P2 This is a BANK JPM (URO-SAE02P055J). In the plant, the applicant will simulate taking local control of A Main Feedwater Regulating Valve.

P3 This JPM is MODIFIED from BANK JPM URO-SEC01053J. In the plant, the applicant will simulate placing the Refueling Water Storage Tank (RWST) in recirculation for Chemistry. This will be an ALTERNATE PATH JPM in that several valves will not be in their required position for recirculation and will have to be repositioned by the applicant. Also flow will have to be adjusted following the lineup. The bank JPM was not alternate path.

Rev 3

Appendix D Scenario Outline Form ES-D-1 Facility: Callaway Scenario No.: 1, Rev 2 Op-Test No.: 2013301 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: 100% Power, Steady State Conditions Turnover: B SI Pump is tagged out of service for a breaker inspection. The B Emergency Diesel Generator is running fully loaded. After the completion of Shift Turnover, Unload and Shutdown the B Emergency Diesel Generator.

Eve Malf. No. Event Event nt Type* Description No.

BOP (N) 1 N/A Unload and shutdown the B Diesel Generator SRO (I) Pressurizer Level Transmitter BB LT-459 Fails Low / Restore 2 BBLT459 RO (I) Letdown (Tech Spec)

SRO (C) Main Seal Oil Pump Trips / Emergency Seal Oil Pump fails to start 3 PCD01_Trip BOP (C) in Automatic PBG04 SRO (C) Normal Charging Pump Trips, must start a Centrifugal Charging 4

RO (C) Pump EBB01B SRO (C) Steam Generator B Tube Leak (25 gpm) Requiring Rapid Load 5

RO (R) Reduction (Tech Spec)

BOP (C)

EBB01B SRO (M) Steam Generator B Tube Rupture (400 gpm) after downpower 6

RO (M) started which results in a Reactor Trip / Safety Injection (PRA)

BOP (M)

SAS10XX_2 BOP (C) Feedwater Isolation Valve Fails to close on Ruptured SG 7

CPIS BLOCK RO (C) Containment Purge Isolation Signal fails to Actuate (Both Trains) 8

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
1. Total malfunctions (5-8) 6
2. Malfunctions after EOP entry (1-2) 2
3. Abnormal events (2-4) 4
4. Major transients (1-2) 1
5. EOPs entered/requiring substantive actions (1-2) 1
6. EOP contingencies requiring substantive actions (0-2) 0
7. Critical tasks (2-3) 2

Scenario Event Description Callaway 2013 NRC Scenario #1, rev. 2 The plant is operating at 100%, steady state power. Diesel Generator NE02 has been running fully loaded for one hour. During turnover, the crew is directed to unload and secure NE02 IAW OSP-NE-0001B, Standby Diesel Generator B Periodic Tests. B Safety Injection Pump is tagged out of service for a breaker inspection.

After NE02 has been unloaded, Pressurizer Level Channel BB LT-459 fails low, resulting in a loss of letdown. The crew will respond IAW OTO-BG-00001, Pressurizer Level Control Malfunction, select an operable pressurizer level channel and restore letdown to service. Tech Spec 3.3.1 for Reactor Trip System Instrumentation applies.

After Tech Specs have been addressed for BB LT-459, the Main Seal Oil Pump for the Main Generator trips and the Emergency Seal Oil Pump fails to start. The crew will enter OTO-MA-00002, Generator Seal Oil System Malfunction and restore generator seal oil by manually starting the Emergency Seal Oil Pump.

Once seal oil has been restored, the Normal Charging Pump will trip. The crew will re-enter OTO-BG-00001, Pressurizer Level Control Malfunction, and start a Centrifugal Charging Pump (CCP) to restore RCS charging flow.

Once the CCP has been started and pressurizer level is stable a 25 gpm tube leak develops on B Steam Generator. The crew should enter OTO-BB-00001, Steam Generator Tube Leak. OTO-BB-00001 will direct the crew to commence a rapid load decrease IAW OTO-MA-00008, Rapid Load Reduction, to have the unit off-line within the next 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />. Tech spec 3.4.13 for RCS Operational Leakage applies.

Once the rapid load reduction has been commenced and a CUE has been received from the Lead Examiner, Steam Generator B tube ruptures and results in a 400 gpm primary to secondary leak. The crew should initiate a manual reactor trip and safety injection due to the loss of primary inventory.

The Main Feedwater Isolation Valve to Steam Generator B fails to close on the Feedwater Isolation Signal following the reactor trip and SI and must be manually closed by the crew.

Also post trip, the Containment Purge Isolation Signal fails to actuate. The crew will actuate a Containment Purge Isolation Signal when completing Attachment A in E-0, Reactor Trip or Safety Injection.

The scenario can be terminated after the crew completes the initial RCS cooldown IAW E-3, Steam Generator Tube Rupture, or at the discretion of the lead evaluator.

Callaway 2013 NRC Scenario #1, rev. 2 Critical Tasks:

Event #7 CT - Isolate "B" Seam Generator by closing FWIV B prior to transitioning from E-0, Reactor Trip or Safety Injection Event #8 CT - Manually initiate a Containment Purge Isolation Signal (CPIS) prior to completing Attachment A, Automatic Action Verification, in E-0, Reactor Trip or Safety Injection References OSP-NE-0001B, Standby Diesel Generator B Periodic Tests OTO-BG-00001, Pressurizer Level Control Malfunction OTO-MA-00002, Generator Seal Oil System Malfunction OTO-BB-00001, Steam Generator Tube Leak OTO-MA-00008, Rapid Load Reduction E-0, Reactor Trip or Safety Injection E-3, Steam Generator Tube Rupture Tech Spec 3.3.1 for Reactor Trip System Instrumentation Tech spec 3.4.13 for RCS Operational Leakage ODP-ZZ-00025, EOP/OTO User's Guide

Appendix D Scenario Outline Form ES-D-1 Facility: Callaway Scenario No.: 3, Rev 5 Op-Test No.: 2013301 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: 80% Power, Steady State Conditions Turnover: The B Motor Driven Auxiliary Feedwater Pump is out of service for scheduled maintenance and will not be returned to service until next shift. The NCP is vibrating excessively, so after the completion of Shift Turnover, shift to the "A" CCP Event Malf. No. Event Event No. Type* Description 1 N/A RO (N) Swap Charging Pumps (High Vibration on NCP)

SRO (I) 2 BBTE0411 RTD Fails High (Tech Spec)

A1 RO (I)

SRO (C) MFW Reg Valve (FRV) C Controller Fails Closed - Manual 3 AEFC0530 BOP (C) Control Available

_1 SRO Refueling Water Storage Tank (RWST) Level Channel Fails Low 4 BNLT0932 (Tech Spec)

SRO (M) 5 PB03 RO (M) Loss of Power Supply PB03 / Reactor Trip BOP (M)

SRO (C) Running CCP Trips (A) / Non Running CCP (B) must be 6 PBG05A RO (C) manually started SA036D_

MDAFAS SRO (I) Auxiliary Feedwater Actuation Signal (MD AFAS) fails to actuate on 7 SA036E_ BOP (I) both trains MDAFAS SRO (C) Turbine Driven Auxiliary Feedwater Pump trips 60 seconds 8

PAL02_1 BOP (C) following the Reactor Trip (contributes to Loss of Secondary Heat Sink)

SRO (C) "A" Motor Driven Auxiliary Feedwater Pump Discharge Flow 9

BOP (C) Degraded. Discharge Valve cannot be opened (which contributes ALV0043 to Loss of Secondary Heat Sink)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
1. Total malfunctions (5-8) 6
2. Malfunctions after EOP entry (1-2) 3
3. Abnormal events (2-4) 3
4. Major transients (1-2) 1
5. EOPs entered/requiring substantive actions (1-2) 1
6. EOP contingencies requiring substantive actions (0-2) 1
7. Critical tasks (2-3) 3

Scenario Event Description Callaway 2013 NRC Scenario #3, rev. 5 The plant is operating at 80%, steady state power. Motor Driven Auxiliary Feedwater (MDAFW) Pump B is out of service for scheduled maintenance and will not be returned to service until next shift. The crew is directed to shift charging to Centrifugal Charging Pump (CCP) A after shift turnover due to excessive vibration reported on the Normal Charging Pump (NCP).

After the NCP is secured and pressurizer level has been stabilized, the Loop 1 Hot Leg RTD will fail high causing the control rods to drive in. The Reactor Operator will take manual control of the control rods and respond in accordance with OTO-BB-00004, RCS RTD Channel Failures. Tech Spec 3.3.1 applies.

After Tech Specs have been addressed for the RTD, MFW Reg Valve (FRV) C fails closed. This causes a feedwater flow reduction and a lowering SG level. The crew should respond per OTO-AE-00001, Feedwater System Malfunction, and take manual control of the failed valve to prevent a reactor trip.

After Steam Generator C level has been stabilized, a Refueling Water Storage Tank (RWST) level channel fails low. The crew will respond IAW OTO-BN-00001, RWST Level Channel Malfunction, Tech Spec 3.3.2 applies After Tech Specs have been reviewed for the RWST level channel a loss of Bus PB03 occurs. This results in a loss Heater Drain Pump A and Condensate Pumps A and C. The crew should respond by manually tripping the reactor and entering E-0, Reactor Trip or Safety Injection. If the reactor is not tripped manually, it will trip automatically on SG low level.

When the reactor trips, CCP A will trip. CCP B will have to be manually started to provide RCS charging and seal injection to the Reactor Coolant Pumps. This could be on prudent operation action in accordance with ODP-ZZ-00025, EOP/OTO User's Guide, or from direction in ES-0.1, Reactor Trip Response, or from FR-H.1, Response to Loss of Secondary Heat Sink.

The Auxiliary Feedwater Actuation Signal-Motor Driven (AFAS-MD) fails to actuate on both trains from the SG low level. The crew should respond to the failed AFAS-MD signal by starting MDAFW Pump A (B pump is OOS for maintenance). The manual discharge valve for MDAFW Pump A is failed at 10% open and cannot be opened locally.

Once the crew has entered ES-0.1, Reactor Trip Response, and completed the first 4 steps, the Turbine Driven Aux Feedwater Pump will be tripped.

Due to the status of the AFW system, the crew should transition to FR-H.1. The crew should use EOP Addendum 38, Non Safety Auxiliary Feedwater Pump, as directed in FR-H.1, to restore Aux Feedwater flow.

The scenario can be terminated once the crew restores Aux Feedwater flow IAW EOP Addendum 38 or at the discretion of the lead evaluator.

Callaway 2013 NRC Scenario #3, rev. 5 Critical Tasks:

Event #3 CT - Take manual control of FRV C prior to a reactor trip occurring on low steam generator water level Event #5 CT - Manually start CCP B prior to initiating a RCS bleed and feed due to having no CCPs in service Event #8 CT - Manually start the Non Safety Auxiliary Feedwater Pump IAW FR-H.1, Response to Loss of Secondary Heat Sink, prior to initiating a RCS bleed and feed due to Steam Generator low level NOTE:

RCS bleed and feed criteria:

WR level in any 3 S/Gs < 27% [42%]

OR PZR Pressure > 2335 psig OR NO CCPs available References OTN-BG-00001, Addendum 1, Shifting From The NCP to One Of The CCPs OTO-BB-00004, RCS RTD Channel Failures OTO-AE-000001, Feedwater System Malfunction OTO-BN-00001, RWST Level Channel Malfunction E-0, Reactor Trip or Safety Injection ES-0.1, Reactor Trip Response FR-H.1, Response To Loss Of Secondary Heat Sink EOP Addendum 38, Non Safety Auxiliary Feedwater Pump Tech Spec 3.3.1 for Reactor Trip System Instrumentation ODP-ZZ-00025, EOP/OTO User's Guide

Appendix D Scenario Outline Form ES-D-1 Facility: Callaway Scenario No.: 4, Rev. 6 Op-Test No.: 2013301 Examiners: ____________________________ Operators: _____________________________

Initial Conditions: A Reactor Startup has just been completed with Reactor power just above the Point of Adding Heat (POAH). A Train CCW in Service.

Turnover: The plant is in Mode 2. Reactor Startup has just been completed on the previous shift.

Conditions are being held steady while the on-coming crew is performing Just In Time Training for the

-6 -6 power increase and directed to maintain power between 1.0 X 10 to 2.0 X 10 amps. Callaway County is under a severe thunderstorm watch. The crew is directed to shift CCW train Service Loops from the "A" to the "B" Train for normal equipment rotation.

Event Malf. No. Event Event Type* Description RO (N) 1 N/A Swap CCW Train Service Loops from A to B Train SRO (N)

SRO (I) 2 BBPT0455 Pressurizer pressure channel 455 fails high (Tech Spec)

RO (I)

BOP (C) 3 ABPV0002A Atmospheric Steam Dump Failure on B SG (Tech Spec)

SRO (C)

SRO (C) 4 XMR01_1 Loss of ESF transformer XNB02 causing a Loss of NB02/

BOP (C)

EDG B starts, ESW Pump B trips (Tech Spec)

PEF01B_1 RO (C)

MD SRO (M) Loss of Offsite Power, A EDG fails to start Automatically, Loss 5

RO (M) of All AC Power, Manual Reactor Trip BOP (M)

BBPCV0455A RO (C) 6 Pressurizer PORV Fails Partially Open SRO (C)

SRO (C) 7 PEF01A_2 ESW Pump A Auto Start Failure BOP (C)

  • (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes
1. Total malfunctions (5-8) 6
2. Malfunctions after EOP entry (1-2) 2
3. Abnormal events (2-4) 3
4. Major transients (1-2) 1
5. EOPs entered/requiring substantive actions (1-2) 2
6. EOP contingencies requiring substantive actions (0-2) 0
7. Critical tasks (2-3) 3

Scenario Event Description Callaway 2013 NRC Scenario #4, rev. 6 The plant is in Mode 2. Reactor Startup has just been completed on the previous shift. Conditions are being held steady while the on-coming crew is performing Just In Time Training prior to the startup. Callaway County is under a severe thunderstorm watch.

The crew starts the scenario by having the ATC Applicant shift CCW Service Loops from the A to the B Train for normal equipment rotation.

Once the Pumps have been shifted, Pressurizer Pressure Channel, PT-455 fails high. The crew should respond IAW OTO-BB-00006, Pressurizer Pressure Control Malfunction, and selects away from the failed channel prior to the reactor tripping on low pressurizer pressure. T.S. 3.3.1, 3.3.2, and 3.3.4 apply.

Once Tech Specs are addressed, SG B Atmospheric Steam Dump fails Open. The crew should respond per OTO-AB-00001, Steam Dump Malfunction, close the failed valve and initiate action to make repairs. T.S.

3.7.4 applies.

A fault on ESF Transformer XNB02 occurs, resulting in a loss of power to Bus NB02. B EDG starts, but Essential Service Water Pump B trips 3 minutes following pump start, forcing the crew to trip the affected Diesel and enter OTO-NB-00002, Loss of Power to NB02. Technical Specifications 3.8.1, 3.8.4, 3.8.7, and 3.8.9 apply. The crew will also have to shift back to A Train CCW service loop and stop Aux Feed Flow to the Steam Generators from the Turbine Driven Aux Feed Pump.

Due to the severe weather, a fault at the Montgomery substation results in a Loss of Offsite power. Upon the loss of offsite power, the crew sees that the A EDG has not started causing a loss of power to NB01. Since there is no power to NB01 or NB02, the crew will transition to ECA-0.0, Loss of All AC Power and perform the Immediate Actions. The reactor should be tripped when performing Immediate Actions.

When the crew gets to Step 5 of ECA-0.0, they will attempt to start the A Emergency Diesel Generator and it will start, however the A ESW pump fails to start automatically, but should be started manually.

Once power is restored to NB01, the crew will transition to E-0, Reactor Trip or Safety Injection and perform appropriate actions. Once the crew has completed applicable portions of E-0 and transitioned to ES-0.1, Reactor Trip Response, PZR PORV, BB PCV-455A, fails partially open. BB PCV-455A should be isolated prior to RCS pressure lowering to the Safety Injection setpoint.

The scenario will be stopped when the crew is required to Transfer Steam Dumps to the Steam Pressure Mode at Step 8 of ES-0.1 or at the discretion of the Lead Examiner.

Callaway 2013 NRC Scenario #4, rev. 6 Critical Tasks:

Event #2 CT - Select away from the failed Pressurizer Pressure Channel prior to Reactor tripping on low pressurizer pressure.

Event #6 CT - Manually close the PORV before receiving a Safety Injection.

Event #7 CT - Manually start ESW Pump A before Emergency Diesel Generator NE01 trips on high temperature.

References OTG-ZZ-00002, Reactor Startup OTN-EG-00001, Component Cooling Water System OTO-BB-00006, Pressurizer Pressure Control Malfunction OTO-AB-00001, Steam Dump Malfunction OTO-NB-00002, Loss of Power to NB02 E-0, Reactor Trip or Safety Injection ECA-0.0, Loss of All AC Power ES-0.1, Reactor Trip Response Tech Spec 3.3.1, Reactor Trip System Instrumentation Tech Spec 3.3.2, ESFAS Instrumentation Tech Spec 3.3.4, Remote Shutdown System Tech Spec 3.7.4, Atmospheric Steam Dump Valves (ASDs)

Tech Spec 3.8.1, AC Sources - Operating ODP-ZZ-00025, EOP/OTO User's Guide

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