Text

04- Draft Outlines
	ML14140A111
Person / Time
Site:	Waterford
Issue date:	04/02/2014
From:	Chris Steely; Operations Branch IV
To:	;
	laura hurley
References
	Download: ML14140A111 (64)
	v • d • e

2014 NRC Revision 1 ES-401 PWR Examination Outline Form ES-401-2 Facility: Waterford 3 (RO Exam Outline) Date of Exam:

April 2, 2014 RO K/A Category Points SRO-Only Points Tier Group K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total A2 G*

Total 1

3 3

18 6

2 1

2 2

1 9

4

1.

Emergency &

Abnormal Plant Evolutions Tier Totals 4

5 4

N/A 5

5 N/A 4

27 10 1

3 2

3 3

2 2

3 2

3 3

2 28 5

2 1

1 1

1 0

10 3

2.

Plant Systems Tier Totals 4

3 4

4 3

3 4

4 2

38 8

1 2

3 4

1 2

3 4

3. Generic Knowledge and Abilities Categories 3

2 2

3 10 7

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.

2014 NRC Revision 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 / SRO)

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery / 1 X

EK2.1 - Knowledge of the interrelations between the (Reactor Trip Recovery) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features.

3.3 1

000008 Pressurizer Vapor Space Accident / 3 X

AA2.01 - Ability to determine and interpret the following as they apply to the Pressurizer Vapor Space Accident:

RCS pressure and temperature indicators and alarms 3.9 1

000009 Small Break LOCA / 3 X

EK2.03 - Knowledge of the interrelations between the small break LOCA and the following: S/Gs 3.0 1

000011 Large Break LOCA / 3 X

2.4.11 -Knowledge of abnormal condition procedures.

4.0 1

000015/17 RCP Malfunctions / 4 X

AK3.04 - Knowledge of the reasons for the following responses as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow): Reduction of power to below the steady state power-to-flow limit 3.1 1

000022 Loss of Rx Coolant Makeup / 2 X

AA1.01 -Ability to operate and / or monitor the following as they apply to l the Loss of Reactor Coolant Makeup:

CVCS letdown and charging 3.4 1

000025 Loss of RHR System / 4 X

AK1.01 - Knowledge of the operational implications of the following concepts as they apply to Loss of Residual Heat Removal System: Loss of RHRS during all modes of operation 3.9 1

000026 Loss of Component Cooling Water / 8 000027 Pressurizer Pressure Control System Malfunction / 3 X

AA2.15 - Ability to determine and interpret the following as they apply to the Pressurizer Pressure Control Malfunctions: Actions to be taken if PZR pressure instrument fails high 3.7 1

000029 ATWS / 1 X

EA1.06 - Ability to operate and monitor the following as they apply to a ATWS: Operating switches for normal charging header isolation valves 3.2 1

000038 Steam Gen. Tube Rupture / 3 X

EK1.02 - Knowledge of the operational implications of the following concepts as they apply to the SGTR: Leak rate vs. pressure drop 3.2 1

000040 (BW/E05; CE/E05; W/E12)

Steam Line Rupture - Excessive Heat Transfer / 4 X

2.1.27 - Knowledge of system purpose and/or function.

3.9 1

000054 (CE/E06) Loss of Main Feedwater / 4 X

EK2.1 - Knowledge of the interrelations between the (Loss of Feedwater) and the following: Components, and functions of control and safety systems, including instrumentation, signals, interlocks, failure modes, and automatic and manual features 3.3 1

000055 Station Blackout / 6 X

EK1.01 - Knowledge of the operational implications of the following concepts as they apply to the Station Blackout : Effect of battery discharge rates on capacity 3.3 1

000056 Loss of Off-site Power / 6 X

AA2.40 - Ability to determine and interpret the following as they apply to the Loss of Offsite Power: Service water pump ammeter and flowmeter 3.3 1

000057 Loss of Vital AC Inst. Bus / 6 X

AK3.01 - Knowledge of the reasons for the following responses as they apply to the Loss of Vital AC Instrument Bus: Actions contained in EOP for loss of vital ac electrical instrument bus 4.1 1

2014 NRC Revision 1 000058 Loss of DC Power / 6 X

AK3.02 - Knowledge of the reasons for the following responses as they apply to the Loss of DC Power: Actions contained in EOP for loss of dc power 4.0 1

000062 Loss of Nuclear Svc Water / 4 X

2.2.36 - Ability to analyze the effect of maintenance activities, such as degraded power sources, on the status of limiting conditions for operations.

3.1 1

000065 Loss of Instrument Air / 8 X

AA1.01 - Ability to operate and / or monitor the following as they apply to the Loss of Instrument Air:

Remote manual loaders 2.7 1

W/E04 LOCA Outside Containment / 3 W/E11 Loss of Emergency Coolant Recirc. / 4 BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 000077 Generator Voltage and Electric Grid Disturbances / 6 K/A Category Totals:

3 3

Group Point Total:

18/6

2014 NRC Revision 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 / SRO)

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 000001 Continuous Rod Withdrawal / 1 000003 Dropped Control Rod / 1 X

AA1.06 - Ability to operate and / or monitor the following as they apply to the Dropped Control Rod: RCS pressure and temperature 4.0 1

000005 Inoperable/Stuck Control Rod / 1 X

AA2.03 - Ability to determine and interpret the following as they apply to the Inoperable / Stuck Control Rod: Required actions if more than one rod is stuck or inoperable 3.5 1

000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 X 2.1.25 - Ability to interpret reference materials, such as graphs, curves, tables, etc.

3.9 1

000033 Loss of Intermediate Range NI / 7 000036 (BW/A08) Fuel Handling Accident / 8 000037 Steam Generator Tube Leak / 3 X

AA2.15 - Ability to determine and interpret the following as they apply to the Steam Generator Tube Leak: Magnitude of atmospheric radioactive release if cool-down must be completed using steam dump or atmospheric reliefs 3.4 1

000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 000061 ARM System Alarms / 7 X

AK1.01 - Knowledge of the operational implications of the following concepts as they apply to Area Radiation Monitoring (ARM)

System Alarms: Detector limitations 2.5 1

000067 Plant Fire On-site / 8 000068 (BW/A06) Control Room Evac. / 8 000069 (W/E14) Loss of CTMT Integrity / 5 000074 (W/E06&E07) Inad. Core Cooling / 4 X

EK2.09 - Knowledge of the interrelations between the and the following Inadequate Core Cooling: Controllers and positioners 2.6 1

000076 High Reactor Coolant Activity / 9 X

AK3.06 - Knowledge of the reasons for the following responses as they apply to the High Reactor Coolant Activity : Actions contained in EOP for high reactor coolant activity 3.2 1

W/EO1 & E02 Rediagnosis & SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5 W/E16 High Containment Radiation / 9 BW/A01 Plant Runback / 1 BW/A02&A03 Loss of NNI-X/Y / 7 BW/A04 Turbine Trip / 4 BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8

2014 NRC Revision 1 BW/E03 Inadequate Subcooling Margin / 4 BW/E08; W/E03 LOCA Cooldown - Depress. / 4 BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 BW/E13&E14 EOP Rules and Enclosures CE/A11; W/E08 RCS Overcooling - PTS / 4 CE/A16 Excess RCS Leakage / 2 X

AK2.2 - Knowledge of the interrelations between the (Excess RCS Leakage) and the following:

Facilitys heat removal systems, including primary coolant, emergency coolant, the decay heat removal systems, and relations between the proper operation of these systems to the operation of the facility.

3.0 1

CE/E09 Functional Recovery X

EA1.3 -Ability to operate and / or monitor the following as they apply to the (Functional Recovery): Desired operating results during abnormal and emergency situations.

3.6 1

K/A Category Point Totals:

1 2

2 1

Group Point Total:

9/4

2014 NRC Revision 1 ES-401 4

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

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 003 Reactor Coolant Pump X

K6.02 - Knowledge of the effect of a loss or malfunction on the following will have on the RCPS: RCP seals and seal water supply 2.7 1

004 Chemical and Volume Control X

A2.18 - Ability to (a) predict the impacts of the following malfunctions or operations on the CVCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: High VCT level 3.1 1

005 Residual Heat Removal X

K6.03 - Knowledge of the effect of a loss or malfunction on the following will have on the RHRS: RHR heat exchanger 2.5 1

006 Emergency Core Cooling X X K3.02 - Knowledge of the effect that a loss or malfunction of the ECCS will have on the following: Fuel K4.25 - Knowledge of ECCS design feature(s) and/or interlock(s) which provide for the following: Concentrated boric acid supply to RWST 4.3 2.8 1

1 007 Pressurizer Relief/Quench Tank X

X K1.03 - Knowledge of the physical connections and/or cause-effect relationships between the PRTS and the following systems: RCS K4.01 - Knowledge of PRTS design feature(s) and/or interlock(s) which provide for the following: Quench tank cooling 3.0 2.6 1

1 008 Component Cooling Water X

X K3.02 - Knowledge of the effect that a loss or malfunction of the CCWS will have on the following: CRDS A1.02 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CCWS controls including: CCW temperature 2.9 2.9 1

1 010 Pressurizer Pressure Control X

A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the PZR PCS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Heater failures 3.3 1

012 Reactor Protection X

K5.01 - Knowledge of the operational implications of the following concepts as the apply to the RPS: DNB 3.3 1

013 Engineered Safety Features Actuation X

A4.03 - Ability to manually operate and/or monitor in the control room: ESFAS initiation 4.5 1

022 Containment Cooling X

X K2.01 - Knowledge of power supplies to the following: Containment cooling fans A3.01 - Ability to monitor automatic operation of the CCS, including: Initiation of safeguards mode of operation 3.0 4.1 1

1

2014 NRC Revision 1 025 Ice Condenser This system is not part of plant design, but included in random selection process.

026 Containment Spray X

A1.03 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the CSS controls including: Containment sump level 3.5 1

039 Main and Reheat Steam X

K4.04 - Knowledge of MRSS design feature(s) and/or interlock(s) which provide for the following: Utilization of steam pressure program control when steam dumping through atmospheric relief/dump valves, including T-ave. limits 2.9 1

059 Main Feedwater X

X A3.03 - Ability to monitor automatic operation of the MFW, including: Feedwater pump suction flow pressure 2.1.28 - Knowledge of the purpose and function of major system components and controls.

2.5 4.1 1

1 061 Auxiliary/Emergency Feedwater X

A1.05 -Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the AFW controls including: AFW flow/motor amps 3.6 1

062 AC Electrical Distribution X

A4.01 - Ability to manually operate and/or monitor in the control room: All breakers (including available switchyard) 3.3 1

063 DC Electrical Distribution X

2.4.8 - Knowledge of how abnormal operating procedures are used in conjunction with EOPs.

3.8 1

064 Emergency Diesel Generator X

K2.03 - Knowledge of bus power supplies to the following: Control power 3.2 1

073 Process Radiation Monitoring X

K5.03 - Knowledge of the operational implications as they apply to concepts as they apply to the PRM system: Relationship between radiation intensity and exposure limits 2.9 1

076 Service Water X

X K1.20 - Knowledge of the physical connections and/or cause-effect relationships between the SWS and the following systems: AFW K3.07 - Knowledge of the effect that a loss or malfunction of the SWS will have on the following: ESF loads 3.4 3.7 1

1 078 Instrument Air X

X K1.02 - Knowledge of the physical connections and/or cause-effect relationships between the IAS and the following systems:

Service air A4.01 - Ability to manually operate and/or monitor in the control room: Pressure gauges 2.7 3.1 1

1 103 Containment X

A3.01 - Ability to monitor automatic operation of the containment system, including: Containment isolation 3.9 1

K/A Category Point Totals:

3 2

3 3

2 2

3 2

3 3

2 Group Point Total:

28/5

2014 NRC Revision 1 ES-401 5

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

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 001 Control Rod Drive X

K4.05 - Knowledge of CRDS design feature(s) and/or interlock(s) which provide for the following: Boration and dilution.

3.9 1

002 Reactor Coolant 011 Pressurizer Level Control X

A3.02 - Ability to monitor automatic operation of the PZR LCS, including: Reactor power 2.6 1

014 Rod Position Indication 015 Nuclear Instrumentation X

K6.03 - Knowledge of the effect of a loss or malfunction on the following will have on the NIS: Component interconnections 2.6 1

016 Non-nuclear Instrumentation X

K5.01 - Knowledge of the operational implication of the following concepts as they apply to the NNIS: Separation of control and protection circuits 2.7 1

017 In-core Temperature Monitor X

K1.02 - Knowledge of the physical connections and/or cause-effect relationships between the ITM system and the following systems: RCS 3.3 1

027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control X

A1.02 - Ability to predict and/or monitor changes in parameter (to prevent exceeding design limits) associated with operating the HRPS controls including: Containment pressure 3.4 1

029 Containment Purge X

K3.01 - Knowledge of the effect that a loss or malfunction of the Containment Purge System will have on the following: Containment parameters 2.9 1

033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment Randomly selected this system for a RO question. Accounted for in SRO exam per ES-401-2 instructions.

035 Steam Generator 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal X

A2.02 - Ability to (a) predict the impacts of the following malfunctions or operations on the Waste Gas Disposal System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Use of waste gas release monitors, radiation, gas flow rate, and totalizer 3.3 1

072 Area Radiation Monitoring

2014 NRC Revision 1 075 Circulating Water X

K2.03 - Knowledge of bus power supplies to the following: Emergency/essential SWS pumps 2.6 1

079 Station Air 086 Fire Protection X

A4.02 - Ability to manually operate and/or monitor in the control room: Fire Detection Panels 3.5 1

K/A Category Point Totals:

1 1

0 Group Point Total:

10/3

2014 NRC Revision 1 ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility: Waterford 3 (RO Exam Outline) Date of Exam: April 2, 2014 RO SRO-Only Category K/A #

Topic IR IR 2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, no-solo operation, maintenance of active license status, 10CFR55, etc.

3.3 1

2.1.8 Ability to coordinate personnel activities outside the control room.

3.4 1

2.1.44 Knowledge of RO duties in the control room during fuel handling, such as responding 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.

3.9 1

2.1.

1.

Conduct of Operations Subtotal 3

2.2.1 Ability to perform pre-startup procedures for the facility, including operating those controls associated with plant equipment that could affect reactivity.

4.5 1

2.2.21 Knowledge of pre-and post-maintenance operability requirements.

2.9 1

2.2.

2.

Equipment Control Subtotal 2

2.3.5 Ability to use radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

2.9 1

2.3.15 Knowledge of radiation monitoring systems, such as fixed radiation monitors and alarms, portable survey instruments, personnel monitoring equipment, etc.

2.9 1

2.3.

3.

Radiation Control Subtotal 2

2.4.5 Knowledge of the organization of the operating procedures network for normal, abnormal, and emergency evolutions.

3.7 1

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

3.8 1

2.4.16 Knowledge of EOP implementation hierarchy and coordination with other support procedures or guidelines such as, operating procedures, abnormal operating procedures, and severe accident management guidelines.

3.5 1

2.4.

4.

Emergency Procedures /

Plan Subtotal 3

Tier 3 Point Total 10 7

2014 NRC Revision 1 ES-401 Record of Rejected K/As Form ES-401-4 Tier /

Group Randomly Selected K/A Reason for Rejection 2/1 025 Ice Condenser This system was selected for a question in the RO exam. Since this system is not part of the Waterford 3 design, another system was randomly selected for the question.

1/1 022 Loss of Reactor Coolant Makeup Originally selected AK2 area for a question. None of the K/A statements had an Importance Rating above 2.5. Reselected 026 Loss of Component Cooling Water in the AK2 area. Reselected an AA1 area question for 022 Loss of Reactor Coolant Makeup.

1/1 026 Loss of Component Cooling Water (CCW)

Reselected an AK2 area for a question (see previous item). There are no specific KA statements provided. Reselected AK2 question under 009 Small Break LOCA.

1/1 065 Loss of Instrument Air Originally selected an AK2 area for the question. There are no KA statements that are above a 2.5 Importance Rating. Reselected an EK2 KA statement under E06 Loss of Main Feedwater. Reselected an AA1 KA statement for 065 Loss of Instrument Air.

2/1 073 Process Radiation Monitoring Originally selected an A3 area for the question. There are no KA statements available. Reselected an A3 KA statement under 103 Containment. Reselected a K5 statement under 073 Process Radiation Monitoring.

2/2 055 Condenser Air Removal Originally selected an A2 area for the question. There are no KA statements that are above a 2.5 Importance Rating. Reselected the A2 area under 071 Waste Gas Disposal.

2/2 086 Fire Protection Originally selected a K2 area for the question. There are no KA statements available. Reselected the K2 KA statement under 075 Circulating Water. Reselected the A4 KA statement under 086 Fire Protection.

2/1 076 Service Water System Originally selected K1.15 for Service Water. There is no relationship at Waterford 3 between TCCW/ACC and the FPS.

Randomly selected another system for the K1 Statement for 076 Service Water. The system selected was K1.20, AFW.

2/2 086 Fire Protection System.

Originally selected A4.06 for the Halon System. There is no Halon Systems at Waterford 3. Randomly selected another K/A for the A4 Statement for 086, Fire Protection System. The K/A selected was A4.02, Fire Detection Panels.

1/1 029 Anticipated Transient Without Scram (ATWS)

Originally selected EA1.06 for Operating switches for normal charging header isolation valves. Waterford 3 does not operate charging isolation valves for an ATWS event. Randomly selected another K/A for the EA1 Statement for 029 Anticipated Transient Without Scram (ATWS). The K/A selected was EA1.12, M/G set power supply and Reactor Trip Breakers

2014 NRC Revision 1

ES-401 PWR Examination Outline Form ES-401-2 Facility: Waterford 3 (SRO Exam Outline) Date of Exam:

April 2, 2014 RO K/A Category Points SRO-Only Points Tier Group K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

Total A2 G*

Total 1

18 3

3 6

2 9

2 2

4

1.

Emergency &

Abnormal Plant Evolutions Tier Totals N/A N/A 27 5

5 10 1

28 3

2 5

2 10 1

1 1

3

2.

Plant Systems Tier Totals 38 5

3 8

1 2

3 4

1 2

3 4

3. Generic Knowledge and Abilities Categories 10 2

2 2

1 7

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.

ES-401 2

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

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery / 1 X

2.4.4 - Ability to recognize abnormal indications for system operating parameters that are entry-level conditions for emergency and abnormal operating procedures.

4.7 1

000008 Pressurizer Vapor Space Accident / 3 000009 Small Break LOCA / 3 X

2.2.40 - Ability to apply Technical Specifications for a system.

4.7 1

000011 Large Break LOCA / 3 X

EA2.04 - Ability to determine or interpret the following as they apply to a Large Break LOCA: Significance of PZR readings 3.9 1

000015/17 RCP Malfunctions / 4 000022 Loss of Rx Coolant Makeup / 2 000025 Loss of RHR System / 4 000026 Loss of Component Cooling Water / 8 X

AA2.03 - Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water:

The valve lineups necessary to restart the CCWS while bypassing the portion of the system causing the abnormal condition 2.9 1

000027 Pressurizer Pressure Control System Malfunction / 3 000029 ATWS / 1 000038 Steam Gen. Tube Rupture / 3 X

2.2.38 - Knowledge of conditions and limitations in the facility license.

4.5 1

000040 (BW/E05; CE/E05; W/E12)

Steam Line Rupture - Excessive Heat Transfer / 4 000054 (CE/E06) Loss of Main Feedwater / 4 000055 Station Blackout / 6 000056 Loss of Off-site Power / 6 000057 Loss of Vital AC Inst. Bus / 6 000058 Loss of DC Power / 6 000062 Loss of Nuclear Svc Water / 4 000065 Loss of Instrument Air / 8 W/E04 LOCA Outside Containment / 3 W/E11 Loss of Emergency Coolant Recirc. / 4 BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 000077 Generator Voltage and Electric Grid Disturbances / 6 X

AA2.08 - Ability to determine and interpret the following as they apply to Generator Voltage and Electric Grid Disturbances: Criteria to trip the turbine or reactor 4.4 1

K/A Category Totals:

3 3

Group Point Total:

18/6

ES-401 3

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

E/APE # / Name / Safety Function K

1 K

2 K

3 A

1 A

2 G

K/A Topic(s)

IR 000001 Continuous Rod Withdrawal / 1 X

AA2.01 - Ability to determine and interpret the following as they apply to the Continuous Rod Withdrawal : Reactor tripped breaker indicator 4.2 1

000003 Dropped Control Rod / 1 000005 Inoperable/Stuck Control Rod / 1 000024 Emergency Boration / 1 000028 Pressurizer Level Malfunction / 2 000032 Loss of Source Range NI / 7 000033 Loss of Intermediate Range NI / 7 000036 (BW/A08) Fuel Handling Accident / 8 000037 Steam Generator Tube Leak / 3 000051 Loss of Condenser Vacuum / 4 000059 Accidental Liquid RadWaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 X 2.4.6 - Knowledge of EOP mitigation strategies.

4.7 1

000061 ARM System Alarms / 7 000067 Plant Fire On-site / 8 000068 (BW/A06) Control Room Evac. / 8 000069 (W/E14) Loss of CTMT Integrity / 5 000074 (W/E06&E07) Inad. Core Cooling / 4 000076 High Reactor Coolant Activity / 9 W/EO1 & E02 Rediagnosis & SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5 W/E16 High Containment Radiation / 9 BW/A01 Plant Runback / 1 BW/A02&A03 Loss of NNI-X/Y / 7 BW/A04 Turbine Trip / 4 BW/A05 Emergency Diesel Actuation / 6 BW/A07 Flooding / 8 BW/E03 Inadequate Subcooling Margin / 4 BW/E08; W/E03 LOCA Cooldown - Depress. / 4 BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 X 2.4.35 - Knowledge of local auxiliary operator tasks during an emergency and the resultant operational effects.

4.0 1

BW/E13&E14 EOP Rules and Enclosures CE/A11; W/E08 RCS Overcooling - PTS / 4 X

AA2.2 - Ability to determine and interpret the following as they apply to the (RCS Overcooling) Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments.

3.4 1

CE/A16 Excess RCS Leakage / 2 CE/E09 Functional Recovery

K/A Category Point Totals:

2 2

Group Point Total:

9/4

ES-401 4

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

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 003 Reactor Coolant Pump 004 Chemical and Volume Control X

2.4.1 - Knowledge of EOP entry conditions and immediate action steps.

4.8 1

005 Residual Heat Removal X

2.4.45 - Ability to prioritize and interpret the significance of each annunciator or alarm.

4.3 1

006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 010 Pressurizer Pressure Control 012 Reactor Protection X

A2.06 - Ability to (a) predict the impacts of the following malfunctions or operations on the RPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Failure of RPS signal to trip the reactor 4.7 1

013 Engineered Safety Features Actuation X

A2.05 - Ability to (a) predict the impacts of the following malfunctions or operations on the ESFAS; and (b) based Ability on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Loss of dc control power 4.2 1

022 Containment Cooling 025 Ice Condenser 026 Containment Spray 039 Main and Reheat Steam 059 Main Feedwater 061 Auxiliary/Emergency Feedwater 062 AC Electrical Distribution X

A2.12 - Ability to (a) predict the impacts of the following malfunctions or operations on the ac distribution system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Restoration of power to a system with a fault on it 3.6 1

063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Monitoring 076 Service Water

078 Instrument Air 103 Containment K/A Category Point Totals:

3 2

Group Point Total:

28/5

ES-401 5

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

System # / Name K

1 K

2 K

3 K

4 K

5 K

6 A

1 A

2 A

3 A

4 G

K/A Topic(s)

IR 001 Control Rod Drive 002 Reactor Coolant 011 Pressurizer Level Control 014 Rod Position Indication 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment X

A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the Fuel Handling System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Mispositioned fuel element 4.0 1

035 Steam Generator 041 Steam Dump/Turbine Bypass Control X

2.2.12 - Knowledge of surveillance procedures.

4.1 1

045 Main Turbine Generator X

A2.15 - Ability to (a) predict the impacts of the following malfunctions or operation on the MT/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Turbine overspeed 2.6 1

055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air 086 Fire Protection K/A Category Point Totals:

2 1

Group Point Total:

10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3)

Form ES-401-3 Facility: Waterford 3 (SRO Exam Outline) Date of Exam: April 2, 2014 RO SRO-Only Category K/A #

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

3.9 1

2.1.45 Ability to identify and interpret diverse indications to validate the response of another indication.

4.3 1

2.1.

1.

Conduct of Operations Subtotal 2

2.2.6 Knowledge of the process for making changes to procedures.

3.6 1

2.2.35 Ability to determine Technical Specification Mode of Operation.

4.5 1

2.2.

2.

Equipment Control Subtotal 2

2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions.

3.7 1

2.3.6 Ability to approve release permits.

3.8 1

2.3.

3.

Radiation Control Subtotal 2

2.4.42 Knowledge of emergency response facilities.

3.8 1

2.4.

4.

Emergency Procedures /

Plan Subtotal 1

Tier 3 Point Total 10 7

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

Group Randomly Selected K/A Reason for Rejection

ES-301 Administrative Topics Outline Form ES-301-1 2014 NRC Revision 0 Facility:

Waterford 3 Date of Examination:

4/07/2014 Examination Level:

RO SRO Operating Test Number:

1 Administrative Topic (see Note)

Type Code*

Describe activity to be performed A1 Conduct of Operations K/A Importance:

3.9 M,R 2.1.25, Ability to interpret reference materials, such as graphs, curves, tables, etc.

Calculate required and available Feedwater to place the plant on Shutdown Cooling and determine the time requirement to be on Shutdown Cooling.

A2 Conduct of Operations K/A Importance:

4.3 D,P,R 2.1.23, Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Complete a calculation for determining the amount of pure water that may be added to the Refuel Cavity without dilution to below shutdown margin requirements in accordance with OP-010-006, Outage Operations, section 9.24, Refueling Cavity Boron Concentration.

(Used on 2012 NRC Exam)

A3 Equipment Control K/A Importance:

3.7 N,R 2.2.12, Knowledge of surveillance procedures Complete surveillance OP-903-008, Reactor Coolant System Isolation Leakage Test, Attachment 10.9 RC Loop 2 Hot Leg Injection Inside Containment Check SI-510B Leak Rate Data.

A4 Radiation Control K/A Importance:

3.2 D,R 2.3.4, Knowledge of radiation exposure limits under normal or emergency conditions.

Calculate stay time to perform a tagout verification in the Regen Heat Exchanger Room. Room dose rate &

operators yearly dose provided.

Emergency Plan Not Selected NOTE:

All items (5 total are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 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 Administrative Topics Outline Form ES-301-1 2014 NRC Revision 0 Facility:

Waterford 3 Date of Examination:

4/07/2014 Examination Level:

RO SRO Operating Test Number:

1 Administrative Topic (see Note)

Type Code*

Describe activity to be performed A5 Conduct of Operations K/A Importance:

4.2 N,R 2.1.25, Ability to interpret reference materials, such as graphs, curves, tables, etc.

Review and approve a completed calculation for required and available Feedwater to place the plant on Shutdown Cooling and review recommendation for the maximum time requirement to be on Shutdown Cooling.

A6 Conduct of Operations K/A Importance:

4.4 D,P,R 2.1.23, Ability to perform specific system and integrated plant procedures during all modes of plant operation.

Review and approve a completed calculation for determining the amount of pure water that may be added to the Refuel Cavity without dilution to below shutdown margin requirements in accordance with OP-010-006, Outage Operations, section 9.24, Refueling Cavity Boron Concentration.

(Used on 2012 NRC Exam)

A7 Equipment Control K/A Importance:

4.7 N,R 2.2.40, Ability to apply Technical Specifications for a system.

Review and approve surveillance OP-903-008, Reactor Coolant System Isolation Leakage Test, Attachment 10.9 RC Loop 2 Hot Leg Injection Inside Containment Check SI-510B Leak Rate Data.

A8 Radiation Control K/A Importance:

3.7 D,R 2.3.4, Knowledge of radiation exposure limits under normal or emergency conditions.

Calculate dose and assign non-licensed operators to vent Safety Injection piping in Safeguards Room A. Given dose rate with and without shielding installed, time to install shielding, and job completion time using 1 operator or using 2 operators, determine proper job assignment.

A9 Emergency Plan K/A Importance:

4.6 M,R 2.4.41, Knowledge of the emergency action level thresholds and classifications.

Determine appropriate Emergency Plan EAL.

NOTE:

All items (5 total are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 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 Administrative Topics Outline Form ES-301-1 2014 NRC Revision 0

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 1

2014 NRC Revision 0 Facility:

Waterford 3 Date of Examination:

4/07/14 Exam Level RO SRO-I SRO-U Operating Test No.:

NRC 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 004 Chemical and Volume Control System Secure Emergency Boration in accordance with OP-901-103, Emergency Boration. (Used on 2012 NRC Exam)

S1 A4.07 Boration/Dilution RO - 3.9, SRO - 3.7 D,L,P,S 1

006 Emergency Core Cooling System Mitigate the release of radioactivity through RWSP following RAS Actuation in accordance with OP-902-002, Loss of Coolant accident Recovery.

Fault: LPSI pump continues to run after RAS actuates, requiring the applicant to manually stop the running LPSI pump after additional valve manipulations.

S2 011 EA1.12 Long term containment of radioactivity RO - 4.1, SRO - 4.4 A,D,EN,L,S 2

003 Reactor Coolant Pump System Perform a Reactor Coolant Pump Shutdown in accordance with OP-001-002, Reactor Coolant Pump Operation.

Fault: Reactor Coolant pump reverse rotates requiring stopping of remaining Reactor Coolant Pumps.

S3 A2.02 Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP RO - 3.7, SRO - 3.9 A,D,L,S 4P 076 Service Water System Perform a manual start of the Auxiliary Component Cooling water System in accordance with OP-002-001, Auxiliary Component Cooling Water.

S4 A4.01 SWS pumps RO - 2.9, SRO - 2.9 D,L,S 4S 026 Containment Spray System Realign Containment Spray for auto initiation following a Containment Spray actuation signal in accordance with OP-902-009, Standard Appendices (Appendix 5-E).

S5 A4.01 CSS Controls RO - 4.5, SRO - 4.3 D,EN,L,S 5

064 Emergency Diesel Generators Restore Power to Safety Bus 3A in accordance with OP-902-000, Standard Post Trip Actions.

Fault: Tie breaker fails to open automatically. (WF3 OE)

S6 A3.03 Indicating lights, meters, and recorders RO - 3.4, SRO - 3.3 A,EN,N,S 6

008 Component Cooling Water System Start Component Cooling Water Pump in accordance with OP-901-311, Loss of Train B Safety Bus.

S7 A4.01 CCW indications and Controls RO - 3.3, SRO - 3.1 D,S 8

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 2

2014 NRC Revision 0 068 Liquid Radwaste System Discharge Waste Condensate Tank A to the Circulating water System in accordance with OP-007-004, Liquid Waste Management System.

Fault: Upon initiation of flow, CW pump will trip reducing the required CW flow to below what is permitted by the release permit.

S8 A4.03 Stoppage of releases if limits exceeded RO - 3.9, SRO - 3.8 A,D,L,S 9

In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) 061 Auxiliary/Emergency Feedwater (AFW) System Establish Local Manual Control of EFW Flow in accordance with OP-009-003, Emergency Feedwater. (PRA Top Operator Action List)

P1 K1.01 S/G System RO - 4.1, SRO - 4.1 D,E,L 4S 062 A.C. Electrical Distribution Transfer SUPS 014AB from Alternate to Normal AC Power in accordance with OP-006-005, Inverters and Distribution.

Fault: After alignment, voltage will not be indicated on SUPS 014 AB inverter. (Used on 2012 NRC Exam)

P2 A3.04 Operation of inverter RO - 2.7, SRO - 2.9 A,D,P 6

033 Spent Fuel pool Cooling System Restore Spent Fuel Cooling Pump to Operation via the Emergency Diesel Generators in accordance with OP-901-513, Spent Fuel pool Cooling Malfunction.

P3 K3.03 Spent fuel temperature RO - 3.0, SRO - 3.3 E,N,R 8

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 5

(C)ontrol room (D)irect from bank d 9 / d 8 / d 4 9

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

(EN)gineered safety feature

- / - / 1 (control room system)

(L)ow-Power / Shutdown t 1 / t 1 / t 1 7

(N)ew or (M)odified from bank including 1(A) t 2 / t 2 / t 1 2

(P)revious 2 exams d 3 / d 3 / d 2 (randomly selected) 2 (R)CA t 1 / t 1 / t 1 1

(S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 3

2014 NRC Revision 0 Facility:

Waterford 3 Date of Examination:

4/07/14 Exam Level RO SRO-I SRO-U Operating Test No.:

NRC 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 004 Chemical and Volume Control System Secure Emergency Boration in accordance with OP-901-103, Emergency Boration. (Used on 2012 NRC Exam)

S1 A4.07 Boration/Dilution RO - 3.9, SRO - 3.7 D,L,P,S 1

006 Emergency Core Cooling System Mitigate the release of radioactivity through RWSP following RAS Actuation in accordance with OP-902-002, Loss of Coolant accident Recovery.

Fault: LPSI pump continues to run after RAS actuates, requiring the applicant to manually stop the running LPSI pump after additional valve manipulations.

S2 011 EA1.12 Long term containment of radioactivity RO - 4.1, SRO - 4.4 A,D,EN,L,S 2

003 Reactor Coolant Pump System Perform a Reactor Coolant Pump Shutdown in accordance with OP-001-002, Reactor Coolant Pump Operation.

Fault: Reactor Coolant pump reverse rotates requiring stopping of remaining Reactor Coolant Pumps.

S3 A2.02 Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP RO - 3.7, SRO - 3.9 A,D,L,S 4P 076 Service Water System Perform a manual start of the Auxiliary Component Cooling water System in accordance with OP-002-001, Auxiliary Component Cooling Water.

S4 A4.01 SWS pumps RO - 2.9, SRO - 2.9 D,L,S 4S S5 064 Emergency Diesel Generators Restore Power to Safety Bus 3A in accordance with OP-902-000, Standard Post Trip Actions.

Fault: Tie breaker fails to open automatically. (WF3 OE)

S6 A3.03 Indicating lights, meters, and recorders RO - 3.4, SRO - 3.3 A,EN,N,S 6

008 Component Cooling Water System Start Component Cooling Water Pump in accordance with OP-901-311, Loss of Train B Safety Bus.

S7 A4.01 CCW indications and Controls RO - 3.3, SRO - 3.1 D,S 8

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 4

2014 NRC Revision 0 068 Liquid Radwaste System Discharge Waste Condensate Tank A to the Circulating water System in accordance with OP-007-004, Liquid Waste Management System.

Fault: Upon initiation of flow, CW pump will trip reducing the required CW flow to below what is permitted by the release permit.

S8 A4.03 Stoppage of releases if limits exceeded RO - 3.9, SRO - 3.8 A,D,L,S 9

In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) 061 Auxiliary/Emergency Feedwater (AFW) System Establish Local Manual Control of EFW Flow in accordance with OP-009-003, Emergency Feedwater. (PRA Top Operator Action List)

P1 K1.01 S/G System RO - 4.1, SRO - 4.1 D,E,L 4S 062 A.C. Electrical Distribution Transfer SUPS 014AB from Alternate to Normal AC Power in accordance with OP-006-005, Inverters and Distribution.

Fault: After alignment, voltage will not be indicated on SUPS 014 AB inverter. (Used on 2012 NRC Exam)

P2 A3.04 Operation of inverter RO - 2.7, SRO - 2.9 A,D,P 6

033 Spent Fuel pool Cooling System Restore Spent Fuel Cooling Pump to Operation via the Emergency Diesel Generators in accordance with OP-901-513, Spent Fuel pool Cooling Malfunction.

P3 K3.03 Spent fuel temperature RO - 3.0, SRO - 3.3 E,N,R 8

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 5

(C)ontrol room (D)irect from bank d 9 / d 8 / d 4 8

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

(EN)gineered safety feature

- / - / 1 (control room system)

(L)ow-Power / Shutdown t 1 / t 1 / t 1 6

(N)ew or (M)odified from bank including 1(A) t 2 / t 2 / t 1 2

(P)revious 2 exams d 3 / d 3 / d 2 (randomly selected) 2 (R)CA t 1 / t 1 / t 1 1

(S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 5

2014 NRC Revision 0 Facility:

Waterford 3 Date of Examination:

4/07/14 Exam Level RO SRO-I SRO-U Operating Test No.:

NRC 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 006 Emergency Core Cooling System Mitigate the release of radioactivity through RWSP following RAS Actuation in accordance with OP-902-002, Loss of Coolant accident Recovery.

Fault: LPSI pump continues to run after RAS actuates, requiring the applicant to manually stop the running LPSI pump after additional valve manipulations.

S2 011 EA1.12 Long term containment of radioactivity RO - 4.1, SRO - 4.4 A,D,EN,L,S 2

003 Reactor Coolant Pump System Perform a Reactor Coolant Pump Shutdown in accordance with OP-001-002, Reactor Coolant Pump Operation.

Fault: Reactor Coolant pump reverse rotates requiring stopping of remaining Reactor Coolant Pumps.

S3 A2.02 Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP RO - 3.7, SRO - 3.9 A,D,L,S 4P S4 S5 064 Emergency Diesel Generators Restore Power to Safety Bus 3A in accordance with OP-902-000, Standard Post Trip Actions.

Fault: Tie breaker fails to open automatically. (WF3 OE)

S6 A3.03 Indicating lights, meters, and recorders RO - 3.4, SRO - 3.3 A,EN,N,S 6

S7 S8

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 6

2014 NRC Revision 0 In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) 061 Auxiliary/Emergency Feedwater (AFW) System Establish Local Manual Control of EFW Flow in accordance with OP-009-003, Emergency Feedwater. (PRA Top Operator Action List)

P1 K1.01 S/G System RO - 4.1, SRO - 4.1 D,E,L 4S P2 033 Spent Fuel pool Cooling System Restore Spent Fuel Cooling Pump to Operation via the Emergency Diesel Generators in accordance with OP-901-513, Spent Fuel pool Cooling Malfunction.

P3 K3.03 Spent fuel temperature RO - 3.0, SRO - 3.3 E,N,R 8

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 3

(C)ontrol room (D)irect from bank d 9 / d 8 / d 4 3

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

(EN)gineered safety feature

- / - / 1 (control room system) 2 (L)ow-Power / Shutdown t 1 / t 1 / t 1 3

(N)ew or (M)odified from bank including 1(A) t 2 / t 2 / t 1 2

(P)revious 2 exams d 3 / d 3 / d 2 (randomly selected) 0 (R)CA t 1 / t 1 / t 1 1

(S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 1

2014 NRC Revision 1 Facility:

Waterford 3 Date of Examination:

4/07/14 Exam Level RO SRO-I SRO-U Operating Test No.:

NRC 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 004 Chemical and Volume Control System Secure Emergency Boration in accordance with OP-901-103, Emergency Boration. (Used on 2012 NRC Exam)

S1 A4.07 Boration/Dilution RO - 3.9, SRO - 3.7 D,L,P,S 1

006 Emergency Core Cooling System Mitigate the release of radioactivity through RWSP following RAS Actuation in accordance with OP-902-002, Loss of Coolant accident Recovery.

Fault: LPSI pump continues to run after RAS actuates, requiring the applicant to manually stop the running LPSI pump after additional valve manipulations.

S2 011 EA1.12 Long term containment of radioactivity RO - 4.1, SRO - 4.4 A,D,EN,L,S 2

003 Reactor Coolant Pump System Perform a Reactor Coolant Pump Shutdown in accordance with OP-001-002, Reactor Coolant Pump Operation.

Fault: Reactor Coolant pump reverse rotates requiring stopping of remaining Reactor Coolant Pumps.

S3 A2.02 Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP RO - 3.7, SRO - 3.9 A,D,L,S 4P 076 Service Water System Perform a manual start of the Auxiliary Component Cooling water System in accordance with OP-002-001, Auxiliary Component Cooling Water.

S4 A4.01 SWS pumps RO - 2.9, SRO - 2.9 D,L,S 4S 026 Containment Spray System Realign Containment Spray for auto initiation following a Containment Spray actuation signal in accordance with OP-902-009, Standard Appendices (Appendix 5-E).

S5 A4.01 CSS Controls RO - 4.5, SRO - 4.3 D,EN,L,S 5

064 Emergency Diesel Generators Restore Power to Safety Bus 3B in accordance with OP-902-000, Standard Post Trip Actions.

Fault: Tie breaker fails to open automatically. (WF3 OE)

S6 A3.03 Indicating lights, meters, and recorders RO - 3.4, SRO - 3.3 A,EN,N,S 6

008 Component Cooling Water System Start Component Cooling Water Pump in accordance with OP-901-311, Loss of Train B Safety Bus.

S7 A4.01 CCW indications and Controls RO - 3.3, SRO - 3.1 D,S 8

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 2

2014 NRC Revision 1 068 Liquid Radwaste System Discharge Waste Condensate Tank A to the Circulating water System in accordance with OP-007-004, Liquid Waste Management System.

Fault: Upon initiation of flow, LWM flow controller output fails high, raising flow beyond what is permitted by the release permit.

S8 A4.03 Stoppage of releases if limits exceeded RO - 3.9, SRO - 3.8 A,D,L,S 9

In-Plant Systems@ (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U) 061 Auxiliary/Emergency Feedwater (AFW) System Establish Local Manual Control of EFW Flow in accordance with OP-009-003, Emergency Feedwater. (PRA Top Operator Action List)

P1 K1.01 S/G System RO - 4.1, SRO - 4.1 D,E,L 4S 062 A.C. Electrical Distribution Transfer SUPS 014AB from Alternate to Normal AC Power in accordance with OP-006-005, Inverters and Distribution.

Fault: After alignment, voltage will not be indicated on SUPS 014 AB inverter. (Used on 2012 NRC Exam)

P2 A3.04 Operation of inverter RO - 2.7, SRO - 2.9 A,D,P 6

033 Spent Fuel pool Cooling System Restore Spent Fuel Cooling Pump to Operation via the Emergency Diesel Generators in accordance with OP-901-513, Spent Fuel pool Cooling Malfunction.

P3 K3.03 Spent fuel temperature RO - 3.0, SRO - 3.3 E,N,R 8

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path 4-6 / 4-6 / 2-3 5

(C)ontrol room (D)irect from bank d 9 / d 8 / d 4 9

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

(EN)gineered safety feature

- / - / 1 (control room system) 3 (L)ow-Power / Shutdown t 1 / t 1 / t 1 7

(N)ew or (M)odified from bank including 1(A) t 2 / t 2 / t 1 2

(P)revious 2 exams d 3 / d 3 / d 2 (randomly selected) 2 (R)CA t 1 / t 1 / t 1 1

(S)imulator

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 3

2014 NRC Revision 1 Facility:

Waterford 3 Date of Examination:

4/07/14 Exam Level RO SRO-I SRO-U Operating Test No.:

NRC 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 004 Chemical and Volume Control System Secure Emergency Boration in accordance with OP-901-103, Emergency Boration. (Used on 2012 NRC Exam)

S1 A4.07 Boration/Dilution RO - 3.9, SRO - 3.7 D,L,P,S 1

006 Emergency Core Cooling System Mitigate the release of radioactivity through RWSP following RAS Actuation in accordance with OP-902-002, Loss of Coolant accident Recovery.

Fault: LPSI pump continues to run after RAS actuates, requiring the applicant to manually stop the running LPSI pump after additional valve manipulations.

S2 011 EA1.12 Long term containment of radioactivity RO - 4.1, SRO - 4.4 A,D,EN,L,S 2

003 Reactor Coolant Pump System Perform a Reactor Coolant Pump Shutdown in accordance with OP-001-002, Reactor Coolant Pump Operation.

Fault: Reactor Coolant pump reverse rotates requiring stopping of remaining Reactor Coolant Pumps.

S3 A2.02 Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP RO - 3.7, SRO - 3.9 A,D,L,S 4P 076 Service Water System Perform a manual start of the Auxiliary Component Cooling water System in accordance with OP-002-001, Auxiliary Component Cooling Water.

S4 A4.01 SWS pumps RO - 2.9, SRO - 2.9 D,L,S 4S S5 064 Emergency Diesel Generators Restore Power to Safety Bus 3B in accordance with OP-902-000, Standard Post Trip Actions.