Text

2016-06 Final Outlines
	ML16158A469
Person / Time
Site:	Callaway
Issue date:	06/01/2016
From:	Vincent Gaddy; Operations Branch IV
To:	;
References
	Download: ML16158A469 (40)
	v • d • e

ES-401 PWR Examination Outline Form ES-401-2 Facility: Callaway Plant (RO, Rev. 2)

Date of Exam: 2016 Tier Group RO K/A Category Points SRO-Only Points 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.

Emergency &

Abnormal Plant Evolutions 1

2 2

4 N/A 3

18 6

2 1

1 1

2 2

2 9

4 Tier Totals 3

3 5

5 6

5 27 10

2.

Plant Systems 1

2 2

2 3

3 3

3 2

3 28 5

2 1

1 0

1 1

10 3

Tier Totals 3

3 2

4 4

3 4

38 8

3. Generic Knowledge and Abilities Categories 1

3 2

2 3

2 4

3 10 1

2 3

4 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). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category).

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 with justification; 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 a category 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.

G*

Generic K/As

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

EK2.02 - Knowledge of the interrelations between a reactor trip and the following: Breakers, relays and disconnects (CFR 41.7/45.7) 2.6 1

000008 Pressurizer Vapor Space Accident / 3 X

2.4.11 - Knowledge of abnormal condition procedures. (CFR:

41.10/43.5/45.13) 4.0 2

000009 Small Break LOCA / 3 X

EK1.02 - Knowledge of the operational implications of the following concepts as they apply to the small break LOCA: Use of steam tables (CFR 41.8/41.10/45.3) 3.5 3

000011 Large Break LOCA / 3 X

EK3.02 - Knowledge of the reasons for the following responses as the apply to the Large Break LOCA: Feedwater isolation (CFR 41.5/41.10/45.6/45.13) 3.5 4

000015/17 RCP Malfunctions / 4 000022 Loss of Rx Coolant Makeup / 2 000025 Loss of RHR System / 4 X

AK3.01 - Knowledge of the reasons for the following responses as they apply to the Loss of Residual Heat Removal System: Shift to alternate flowpath (CFR 41.5,41.10/45.6/45.13) 3.1 5

000026 Loss of Component Cooling Water / 8 X

AA2.06 - Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: The length of time after the loss of CCW flow to a component before that component may be damaged (CFR: 43.5/45.13) 2.8 6

000027 Pressurizer Pressure Control System Malfunction / 3 X

A2.10 - Ability to determine and interpret the following as they apply to the Pressurizer Pressure Control Malfunction: PZR Heater energized/ de energized condition (CFR 43.5/45.13) 3.3 7

000029 ATWS / 1 X

EK3.12 - Knowledge of the reasons for the following responses as the apply to the ATWS: Actions contained in EOP for ATWS (CFR 41.5 / 41.10 /45.6 /

45.13) 4.4 8

000038 Steam Gen. Tube Rupture / 3 X

EK3.01 - Knowledge of the reasons for the following responses as the apply to the SGTR: Equalizing pressure on primary and secondary sides of ruptured S/G (CFR 41.5/41.10/45.6/45.13) 4.1 9

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

Steam Line Rupture - Excessive Heat Transfer / 4 X

W/E12, EA1.3 - Ability to operate and

/ or monitor the following as they apply to the (Uncontrolled Depressurization of all Steam Generators): Desired operating results during abnormal and emergency situations. (CFR: 41.7 / 45.5 /

45.6) 3.4 10 000054 (CE/E06) Loss of Main Feedwater / 4 X

AA2.02 - Ability to determine and interpret the following as they apply to the Loss of Main Feedwater (MFW):

Differentiation between loss of all MFW and trip of one MFW pump (CFR:

43.5 / 45.13) 4.1 11

000055 Station Blackout / 6 X

EA1.02 Ability to operate and monitor the following as they apply to a Station Blackout: Manual ED/G start (CFR 41.7 / 45.5 / 45.6) 4.3 13 000056 Loss of Off-site Power / 6 X

AA1.08 - Ability to operate and/or monitor the following as they apply to the Loss of Offsite Power: HVAC chill water pump and unit (CFR 41.7/45.5/45.6) 2.5 12 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 X

2.1.28 - Knowledge of the purpose and function of major system components and controls. (CFR: 41.7) 4.1 14 W/E04 LOCA Outside Containment / 3 X

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

41.7 / 45.7) 3.5 15 W/E11 Loss of Emergency Coolant Recirc. / 4 X

EK1.3 - Knowledge of the operational implications of the following concepts as they apply to the (Loss of Emergency Coolant Recirculation):

Annunciators and conditions indicating signals, and remedial actions associated with the (Loss of Emergency Coolant Recirculation).

(CFR: 41.8 / 41.10 / 45.3) 3.6 16 BW/E04; W/E05 Inadequate Heat Transfer - Loss of Secondary Heat Sink / 4 X

W/E05, EA2.1 - Ability to determine and interpret the following as they apply to the (Loss of Secondary Heat Sink): Facility conditions and selection of appropriate procedures during abnormal and emergency operations. (CFR: 43.5 / 45.13) 3.4 17 000077 Generator Voltage and Electric Grid Disturbances / 6 X

2.1.19 - Ability to use plant computers to evaluate system or component status. (CFR: 41.10 /

45.12) 3.9 18 K/A Category Totals:

2 2 4 3 4 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 000003 Dropped Control Rod / 1 000005 Inoperable/Stuck Control Rod / 1 X

AK1.03 - Knowledge of the operational implications of the following concepts as they apply to Inoperable / Stuck Control Rod: Xenon transient (CFR 41.8 / 41.10 / 45.3) 3.2 19 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 X

2.4.11 Knowledge of abnormal condition procedures (CFR:

41.10 / 43.5 / 45.13) 4.0 20 000059 Accidental Liquid Radwaste Rel. / 9 000060 Accidental Gaseous Radwaste Rel. / 9 X

AA1.02 - Ability to operate and

/ or monitor the following as they apply to the Accidental Gaseous Radwaste: Ventilation System (CFR 41.7 / 45.5 / 45.6) 2.9 21 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 X

AK2.01 - Knowledge of the interrelations between the High Reactor Coolant Activity and the following: Process radiation monitors (CFR 41.7 /

45.7) 2.6 22 W/EO1 & E02 Rediagnosis & SI Termination / 3 X

W/E02, EA2.2 - Ability to determine and interpret the following as they apply to the (SI Termination): Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments. (CFR:

43.5 / 45.13) 3.5 23 W/E13 Steam Generator Over-pressure / 4 W/E15 Containment Flooding / 5 X

EA1.2 - Ability to operate and

/ or monitor the following as they apply to Containment Flooding: Operating behavior characteristics of the facility (CFR: 41.7 / 45.5 / 45.6) 2.7 24 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 X

EK3.2 - Knowledge of the reasons for the following responses as they apply to the (LOCA Cooldown and Depressurization): Normal, abnormal and emergency operating procedures associated with (LOCA Cooldown and Depressurization). (CFR: 41.5 /

41.10, 45.6 / 45.13) 3.4 25 BW/E09; CE/A13; W/E09&E10 Natural Circ. / 4 X

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

(CFR: 41.10 / 43.5 / 45.3 /

45.12) 4.1 26 BW/E13&E14 EOP Rules and Enclosures CE/A11; W/E08 RCS Overcooling - PTS / 4 X

EA2.1 - Ability to determine and interpret the following as they apply to the (Pressurized Thermal Shock): Facility conditions and selection of appropriate procedures during abnormal and emergency operations. (CFR: 43.5 / 45.13) 3.1 27 CE/A16 Excess RCS Leakage / 2 CE/E09 Functional Recovery K/A Category Point Totals:

1 1 1 2 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 X

K6.04 - Knowledge of the effect of a loss or malfunction on the following will have on the RCPS:

Containment isolation valves affecting RCP operation (CFR: 41.7 / 45/5) 2.8 28 004 Chemical and Volume Control X

K3.04 - Knowledge of the effect that a loss or malfunction of the CVCS will have on the following: RCPS (CFR: 41.7/45/6) 3.7 29 005 Residual Heat Removal X

K3.01 - Knowledge of the effect that a loss or malfunction of the RHRS will have on the following: RCS (CFR: 41.7 / 45.6) 3.9 30 005 Residual Heat Removal X

A4.03 - Ability to manually operate and/or monitor in the control room: RHR temperature, PZR heaters and flow, and nitrogen (CFR:

41.7 / 45.5 to 45.8) 2.8 31 006 Emergency Core Cooling X

K5.08 - Knowledge of the operational implications of the following concepts as they apply to ECCS:

Operation of pumps in parallel (CFR: 41.5 / 45.7) 2.9 32 007 Pressurizer Relief/Quench Tank X

A1.03 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the PRTS controls including:

Monitoring quench tank temperature (CFR: 41.5 /

45.5) 2.6 33 008 Component Cooling Water X

A3.04 - Ability to monitor automatic operation of the CCWS, including:

Requirements on and for the CCWS for different conditions of the power plant (CFR: 41.7 / 45.5) 2.9 34 010 Pressurizer Pressure Control X

A2.02 - 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: Spray valve failures (CFR: 41.5 / 43.5 /

45.3 / 45.13) 3.9 36 012 Reactor Protection X

G2.2.22 Knowledge of limiting conditions for operations and safety limits. (CFR: 41.5 / 43.2 /

45.2) 4.0 37

013 Engineered Safety Features Actuation X

K2.01 - Knowledge of bus power supplies to the following: ESFAS/safeguards equipment control (CFR:

41.7) 3.6 38 013 Engineered Safety Features Actuation X

K6.01 - Knowledge of the effect of a loss or malfunction on the following will have on the ESFAS:

Sensors and detectors (CFR:

41.7 / 45.5 to 45.8) 2.7 39 022 Containment Cooling X

K4.04 - Knowledge of CCS design feature(s) and/or interlock(s) which provide for the following: Cooling of control rod drive motors (CFR: 41.7) 2.8 40 025 Ice Condenser Not part of the plant design 026 Containment Spray X

K1.01 - Knowledge of the physical connections and/or cause/effect relationships between the CSS and the following systems: ECCS (CFR: 41.2 to 41.9 / 45.7 to 45.8) 4.2 41 026 Containment Spray X

K2.01 - Knowledge of the bus power supplies to the following: Containment Spray Pumps (CFR: 41.7) 3.4 42 039 Main and Reheat Steam X

K5.08 - Knowledge of the operational implications of the following concepts as the apply to the MRSS:

Effect of steam removal on reactivity (CFR: 41.5 /

45.7) 3.6 43 059 Main Feedwater X

A1.07 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the MFW controls including:

Feed Pump speed, including normal control speed for ICS (CFR: 41.5 / 45.5) 2.5 44 059 Main Feedwater X

A3.06 - Ability to monitor automatic operation of the MFW, including: Feedwater isolation (CFR: 41.7 / 45.5) 3.2 45 061 Auxiliary/Emergency Feedwater X

K5.02 - Knowledge of the operational implications of the following concept as the apply to the AFW: Decay Heat Sources and Magnitude.

(CFR: 41.5 / 45.7) 3.2 46 061 Auxiliary/Emergency Feedwater X

A1.01 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the AFW controls including:

S/G level (CFR: 41.5 / 45.5) 3.9 47 062 AC Electrical Distribution X

K4.10 - Knowledge of ac distribution system design feature(s) and/or interlock(s) which provide for the following:

Uninterruptable ac power sources (CFR: 41.7) 3.1 48

063 DC Electrical Distribution X

A3.01 - Ability to monitor automatic operation of the DC electrical system, including: Meters, annunciators, dials, recorders, and indicating lights (CFR: 41.7 / 45.5) 2.7 49 063 DC Electrical Distribution X

A4.03 Ability to manually operate and / or monitor in the control room: Battery Discharge Rate (CFR: 41.7 /

45.5 to 45.8) 3.0 35 064 Emergency Diesel Generator X

K6.08 - Knowledge of the effect of a loss or malfunction of the following will have on the ED/G system: Fuel oil storage tanks (CFR: 41.7 / 45.7) 3.2 50 073 Process Radiation Monitoring X

2.4.31 - Knowledge of annunciator alarms, indications, or response procedures. (CFR: 41.10 /

45.3) 4.2 51 076 Service Water X

K1.21 - Knowledge of the physical connections and/or cause-effect relationships between the SWS and the following systems: Auxiliary backup SWS (CFR: 41.2 to 41.9 / 45.7 to 45.8) 2.7 52 076 Service Water X

K4.02 - Knowledge of SWS design feature(s) and/or interlock(s) which provide for the following:

Automatic start features associated with SWS pump controls (CFR: 41/7) 2.9 53 078 Instrument Air X

2.4.18 - Knowledge of the specific bases for EOPs.

(CFR: 41.10 / 43.1 / 45.13) 3.3 54 103 Containment X

A2.03 - Ability to (a) predict the impacts of the following malfunctions or operations on the containment system and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Phase A and B isolation (CFR: 41.5 / 43.5 / 45.3 /

45.13) 3.5 55 K/A Category Point Totals:

2 2 2 3 3 3 3 2 3 2 3

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 X

A2.14 Ability to (a) predict the impacts of the following malfunction or operations on the CRDS and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Urgent failure alarm, including rod-out-of-sequence and motion-inhibit alarms.

(CFR: 41.5 / 43.5 / 45.3 /

45.13) 3.7 56 002 Reactor Coolant X

K5.07 Knowledge of the operational implications of the following concepts as they apply to the RCS: Reactivity effects of RCS boron, pressure and temperature (CFR: 41.5 /

45.7) 3.3 65 011 Pressurizer Level Control 014 Rod Position Indication X

A1.02 - Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the RPIS controls, including:

Control rod position indication on control room panels. (CFR: 41.5 / 45.5) 3.2 57 015 Nuclear Instrumentation X

K1.01 - Knowledge of the physical connections and/or cause/effect relationships between the NIS and the following systems: RPS (CFR:

41.2 to 41.9 / 45.7 to 45.8) 4.1 58 016 Non-Nuclear Instrumentation 017 In-Core Temperature Monitor 027 Containment Iodine Removal X

K2.01 - Knowledge of bus power supplies to the following:

Fans (CFR: 41.7) 3.1 59 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator X

K6.01 - Knowledge of the effect of a loss or malfunction on the following will have on the S/GS: MSIVs (CFR: 41.7 / 45.7) 3.2 62 041 Steam Dump/Turbine Bypass Control X

A4.05 Ability to manually operate and/or monitor in the control room: Main steam header pressure (CFR: 41.7 / 45.5 to 45.8) 3.1 63

045 Main Turbine Generator X

K4.02 Knowledge of MT/G system design feature(s) and/or interlock( s) which provide for the following: Automatic shut of reheat stop valves as well as main control valves when tripping turbine (CFR:

41.7) 2.5 60 055 Condenser Air Removal X

G2.1.28 Knowledge of the purpose and function of major system components and controls. (CFR 41.7) 4.1 61 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air 086 Fire Protection X

A3.01 Ability to monitor automatic operation of the Fire Protection System including: Starting mechanisms of the fire water pumps (CFR 41.7 / 45.5) 2.9 64 K/A Category Point Totals:

1 1 0 1 1 1 1 1 1 1 1 Group Point Total:

10/3

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

Form ES-401-3 Facility: Callaway Plant (RO, Rev. 2)

Date of Exam: 2016 Category K/A #

Topic RO SRO-Only IR IR

1.

Conduct of Operations 2.1.13 (CFR: 41.10 / 43.5 / 45.9 / 45.10 )

2.5 66 2.1.36 Knowledge of procedures and limitations involved in core alterations. (CFR: 41.10 / 43.6 / 45.7) 3.0 67 2.1.3 Knowledge of shift or short-term relief turnover practices (CFR: 41.10 / 45.13) 3.7 68 Subtotal 3

2.

Equipment Control 2.2.14 Knowledge of the process for controlling equipment configuration or status. (CFR: 41.10 / 43.3 / 45.13) 3.9 69 2.2.23 Ability to track Technical Specification limiting conditions for operations. (CFR: 41.10 / 43.2 / 45.13) 3.1 70 Subtotal 2

3.

Radiation Control 2.3.11 Ability to control radiation releases. (CFR: 41.11 / 43.4 /

45.10) 3.8 71 2.3.14 Knowledge of radiation or contamination hazards that may arise during normal, abnormal, or emergency conditions or activities. (CFR: 41.12 / 43.4 / 45.10) 3.4 72 Subtotal 2

4.

Emergency Procedures /

Plan 2.4.8 Knowledge of how abnormal operating procedures are used in conjunction with EOPs. (CFR: 41.10 / 43.5 /

45.13) 3.8 73 2.4.29 Knowledge of the emergency plan. (CFR: 41.10 / 43.5 /

45.11) 3.1 74 2.4.42 Knowledge of emergency response facilities. (CFR: 41.10

/ 45.11) 2.6 75 Subtotal 3

Tier 3 Point Total 10 7

ES-401 PWR Examination Outline Form ES-401-2 Facility: Callaway Plant (SRO, Rev. 2)

Date of Exam: 2016 Tier Group RO K/A Category Points SRO-Only Points 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.

Emergency &

Abnormal Plant Evolutions 1

N/A N/A 18 2

4 6

2 9

2 2

4 Tier Totals 27 5

5 10

2.

Plant Systems 1

28 3

2 5

2 10 1

2 3

Tier Totals 38 4

4 8

3. Generic Knowledge and Abilities Categories 1

2 3

4 10 1

1 2

2 3

2 4

2 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). (One Tier 3 Radiation Control K/A is allowed if the K/A is replaced by a K/A from another Tier 3 Category).

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 with justification; 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 a category 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.

G*

Generic K/As

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

EA2.36 Ability to determine or interpret the following as they apply to a small break LOCA:

Difference between overcooling and LOCA indications (CFR 43.5 / 45.13) 4.6 79 000011 Large Break LOCA / 3 000015/17 RCP Malfunctions / 4 000022 Loss of Rx Coolant Makeup / 2 X

AA2.01 Ability to determine and interpret the following as they apply to the Loss of Reactor Coolant Makeup: Whether charging line leak exists (CFR 43.5/ 45.13) 3.8 76 000025 Loss of RHR System / 4 000026 Loss of Component Cooling Water / 8 X

AA2.01 - Ability to determine and interpret the following as they apply to the Loss of Component Cooling Water: Location of a leak in the CCWS (CFR: 43.5 / 45.13) 3.5 77 000027 Pressurizer Pressure Control System Malfunction / 3 000029 ATWS / 1 000038 Steam Gen. Tube Rupture / 3 X

2.4.41 Knowledge of the emergency action level thresholds and classifications. (CFR: 41.10 / 43.5

/ 45.11) 4.6 78 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 X

2.2.44 - Ability to interpret control room indications to verify the status and operation of a system, and understand how operator actions and directives affect plant and system conditions. (CFR: 41.5 /

43.5 / 45.12) 4.4 80 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 X

2.4.6 - Knowledge of EOP mitigation strategies. (CFR: 41.10 / 43.5 /

45.13) 4.7 81 000077 Generator Voltage and Electric Grid Disturbances / 6 K/A Category Totals:

2 4

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 000003 Dropped Control Rod / 1 000005 Inoperable/Stuck Control Rod / 1 X

2.1.20 - Ability to interpret and execute procedure steps.

(CFR: 41.10 / 43.5 / 45.12) 4.6 82 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 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 X

2.2.40 - Ability to apply Technical Specifications for a system. (CFR: 41.10 / 43.2 /

43.5 / 45.3) 4.7 84 W/EO1 & E02 Rediagnosis & SI Termination / 3 W/E13 Steam Generator Over-pressure / 4 X

EA2.2 - Ability to determine and interpret the following as they apply to the (Steam Generator Overpressure):

Adherence to appropriate procedures and operation within the limitations in the facility*s license and amendments. (CFR: 43.5 / 45.13) 3.4 83 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

EA2.2 - Ability to determine and interpret the following as they apply to the (Natural Circulation with Steam Void in Vessel with/without RVLIS):

Adherence to appropriate procedures and operation within the limitations in the facilitys license and amendments. (CFR: 43.5 / 45.13) 3.9 85 BW/E13&E14 EOP Rules and Enclosures CE/A11; W/E08 RCS Overcooling - PTS / 4 CE/A16 Excess RCS Leakage / 2 CE/E09 Functional Recovery K/A Category Point Totals:

2 2 Group Point Total:

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 X

A2.02 Ability to (a) predict the impacts of the following malfunctions or operations on the RCPS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Conditions which exist for an abnormal shutdown of an RCP in comparison to a normal shutdown of an RCP. (CFR:

41.5 / 43.5/ 45.3 / 45/13) 3.9 89 004 Chemical and Volume Control 005 Residual Heat Removal X

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. (CFR:

41.10 / 43.5 / 45.13) 4.2 86 006 Emergency Core Cooling X

2.1.32 Ability to explain and apply system limits and precautions. (CFR: 41.10 /

43.2 / 45.12) 4.0 88 007 Pressurizer Relief/Quench Tank X

A2.04 - Ability to (a) predict the impacts of the following malfunctions or operations on the PRTS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Overpressurization of the waste gas vent header (CFR:

41.5 / 43.5 / 45.3 / 45.13) 2.9 87 008 Component Cooling Water 010 Pressurizer Pressure Control 012 Reactor Protection 013 Engineered Safety Features Actuation 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 063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Monitoring 076 Service Water 078 Instrument Air X

A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the IAS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations: Air dryer and filter malfunctions (CFR:

41.5 / 43.5 / 45.3 / 45.13) 2.9 90 103 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 X

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

(CFR: 41.10 / 43.5 / 45.2 /

45.6) 4.4 91 017 In-Core Temperature Monitor X

2.4.30 - Knowledge of events related to system operation/status that must be reported to internal organizations or external agencies, such as the State, the NRC, or the transmission system operator. (CFR: 41.10 /

43.5 / 45.11) 4.1 92 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling X

A2.01 - Ability to (a) predict the impacts of the following malfunctions or operations on the Spent Fuel Pool Cooling System ; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

Inadequate SDM (CFR: 41.5 /

43.5 / 45.3 / 45.13) 3.5 93 034 Fuel Handling Equipment 035 Steam Generator 041 Steam Dump/Turbine Bypass Control 045 Main Turbine Generator 055 Condenser Air Removal 056 Condensate 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring 075 Circulating Water 079 Station Air

086 Fire Protection K/A Category Point Totals:

1 2

Group Point Total:

10/3

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

Form ES-401-3 Facility: Callaway Plant (SRO, Rev. 2)

Date of Exam: 2016 Category K/A #

Topic RO SRO-Only IR IR

1.

Conduct of Operations 2.1.5 Ability to use procedures related to shift staffing, such as minimum crew complement, overtime limitations, etc.

(CFR: 41.10 / 43.5 / 45.12) 3.9 94 Subtotal 1

2.

Equipment Control 2.2.7 Knowledge of the process for conducting special or infrequent tests. (CFR: 41.10 / 43.3 / 45.13) 3.6 95 2.2.5 Knowledge of the process for making design or operating changes to the facility. (CFR: 41.10 / 43.3 / 45.13) 3.2 96 Subtotal 2

3.

Radiation Control 2.3.4 Knowledge of radiation exposure limits under normal or emergency conditions. (CFR: 41.12 / 43.4 / 45.10) 3.7 97 2.3.13 Knowledge of radiological safety procedures pertaining to licensed operatorl duties, such as response to radiation monitor alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc. (CFR: 41.12 / 43.4 / 45.9 /

45.10) 3.8 98 Subtotal 2

4.

Emergency Procedures /

Plan 2.4.28 Knowledge of procedures relating to a security event (non-safeguards information). (CFR: 41.10 / 43.5 / 45.13) 4.1 99 2.4.25 Knowledge of fire protection procedures. (CFR: 41.10 /

43.5 / 45.13) 3.7 100 Subtotal 2

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 RO 1/1 00027 AA2.10 Question #7 - 00027 AK1.01 was replaced using random selection process within the same safety function. Unable to write question to meet K/A with plausible distractors.

RO 1/1 00029 EK3.12 Question #8 - EK2.06 was replaced using random selection process within the same safety function. Unable to write question to meet K/A with plausible distractors.

RO 1/1 000055 EA1.02 Question #13 - 00058 AA1.02 was replaced due to overlap with questions #48 and #49 and their associated K/As. Random selection from same tier and group on topic not yet selected.

RO 1/2 00051 G2.4.11 Question #20 - 00059 G2.4.21 was replaced due to overlap with question

71. Selected previous topic and random selection of generic K/A within the emergency procedure/plan area.

RO 1/2 000060 AA1.02 Question #21 - 000060 AA1.01 was replaced as PRMs not ARMs are associated with isolation logic etc. To maintain category spread, the A1 category was retained and AA1.02 is the only other K/A in this area.

RO 1/2 W/E 15 EA1.2 Question #24 - W/E 15 EK3.1 was randomly replaced within same topic due to inability to write operationally valid question to k/a.

RO 2/1 00063 A4.03 Question #35 - 00010 K1.01 was replaced due to overlap with the operating test and the inability to write question to meet K/A with plausible distractors.

RO 2/1 00012 G2.2.22 Question #37 - 012 A4.03 was replaced due to the inability to write question to meet K/A with plausible distractors.

RO 2/1 026 K1.01 Question #41 026 K1.02 was randomly reselected due to the fact that there is No physical connection. Maintained same topic and K1 area while maintaining >2.5 importance.

RO 2/1 00026 K2.01 Question #42 - 00026 K3.01 was replaced due to difficulty writing a RO level question on the malfunction of CSS effects on CCS. Random selection from same topic, 00026.

RO 2/1 00061 K5.02 Question #46 - 00061 K2.01 Audit Overlap. Unable to write another question to K/A and maintain separation from NRC and Audit exams.

Random selection from within same safety function.

RO 2/1 103 A2.03 Question #55 - 103 A2.05 - was randomly replaced within same topic and ability due to overlap with SRO question #98.

RO 2/2 001 A2.14 Question #56 - 001 A3.04 was randomly replaced within the topic due to the inability to write question to meet K/A with plausible distractors.

RO 2/2 014 A1.02 Question #57 - 014 A4.02 - was randomly replaced within same topic due to overlap with the operating exam and inability to develop plausible distractors RO 2/2 045 K4.02 Question #60 - 033 A1.01 was randomly replaced due to inability to write a question with 3 plausible distractors and overlap with SRO question and to maintain an even K&A spread among tier 2 group 2.

RO 2/2 055 G2.1.28 Question #61 - 034 K4.03 was randomly replaced due to inability to write a question with 3 plausible distractors and to maintain an even K&A spread among tier 2 group 2.

RO 2/2 035 K6.01 Question #62 - 035 K6.03 was randomly replaced due to inability to write a question with 3 plausible distractors but maintained within the same K6 area to maintain an even K&A spread among tier 2 group 2.

RO 2/2 041 A4.05 Question #63 - 068 A2.03 was randomly replaced due to operational validity while maintain spread of question between K &A's..

RO 2/2 086 A3.01 Question #64 - 072 K3.01 was randomly reselected as a malfunction of an ARM did not impact Containment ventilation. PRM failures would have an effect but not ARMs.

RO 2/2 002 K5.07 Question #65 - 086 K5.03 was randomly reselected due to the inability to write a question to this topic that has 3 plausible distractors.

Randomly reselected system and knowledge in the K5 category in order to maintain an even K&A spread among tier 2 group 2 RO 3 G2.1.13 Question #66 - G2.1.7 was replaced due to the inability to write a generic question about topic. Selected next generic from same category.

RO 3 G2.1.3 Question #68 - G2.1.44 was replaced due to the inability to write question to meet K/A with plausible distractors.

RO 3 G2.4.8 Question #73 - G2.4.6 was replaced due to the inability to write a generic question about specific EOP mitigation strategy. Selected next generic from same category.

RO 3 G2.4.42 Question #75 - G2.4.46 was replaced due to the inability to write a generic question that would "verify that alarms are consistent with the plant conditions" Random selection from same category.

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

Group Randomly Selected K/A Reason for Rejection SRO 1/1 00022 AA2.01 Question #76 - 00008 AA2.19 was randomly replaced due to the inability to write a SRO level question on the topic.

SRO 1/1 00038 G4.4.41 Question #78 - 00038 G2.1.25 was randomly replaced due to the inability to write a SRO level question on the topic.

SRO 1/1 00009 EA2.36 Question #79 - 00054 AA2.07 was randomly replaced due to the inability to write a SRO level question on the topic.

SRO 1/1 W/E 05 G2.4.6 Question #81-W/E 05 G2.4.9 was randomly reselected within the same generic tier due to no different procedural actions at low power versus full power.

SRO 1/2 00076 G2.2.40 Question #84 -W/E 16 G2.2.40 - topic was randomly replaced as technical specification during original topic; same generic maintained.

SRO 2/1 005 G2.4.9 Question #86 - 005 G2.4.35 was randomly reselected within the same generic tier due to inability to write a SRO level question on the topic.

SRO 2/1 006 G2.1.32 Question #88 - 008 G2.4.41 was randomly replaced due to the inability to write a SRO level question on the topic.

SRO 2/1 003 A2.02 Question #89 - 039 A2.02 was randomly replaced because the system does not response the way the K/A assumes it does.

Randomly reselected the system while maintaining the same A2.02.

SRO 3 G2.2.5 Question #96 - G2.2.35 replaced due to the inability to write a SRO level question on the topic. Randomly reselected generic from same category.

SRO 3 G2.3.4 Question #97 - G2.3.5 replaced due to the inability to write a SRO level question on the topic. Randomly reselected generic from same category.

SRO 3 G2.4.25 Question #100 - G2.4.47 replaced due to inability to write a generic question on the selected k/a. Randomly reselected generic from same category.

ES-301 Administrative Topics Outline Form ES-301-1 Rev 2 NUREG-1021, Revision 10 Page 1 of 2 Facility:

Callaway Date of Examination:

5/23/2016 Examination Level:

RO Operating Test Number:

2016-1 Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations A1 R, D 2.1.37 (4.3)

Knowledge of procedures, guidelines, or limitations associated with reactivity management JPM:

Perform a QPTR Calculation Conduct of Operations A2 R, M 2.1.25 (3.9)

Ability to interpret reference materials such as graphs, curves, tables, etc.

JPM:

Determine RV Venting Time (EOP ADD 33)

Equipment Control A3 R, D, P 2.2.37 (3.6)

Ability to determine operability and/or availability of safety related equipment.

JPM:

Determine Amperage Limits for 480 VAC Safety Related busses.

Radiation Control A4 R, M 2.3.7 (3.5)

Ability to comply with radiation work permit requirements during normal or abnormal conditions.

JPM:

Determine entry requirements for the RCA.

NOTE:

All items (five total) are required for SROs. RO applicants require only four items unless they are retaking only the administrative topics (which would require all five items).

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)

The JPMs from the 2013 exam were randomly selected by placing 4 slips of paper labeled A1.a 2013 through A4 2013 in a hardhat. A2 2013was drawn from the hardhat.

ES-301 Administrative Topics Outline Form ES-301-1 Rev 2 NUREG-1021, Revision 10 Page 2 of 2 A1 This is a BANK JPM. The parent JPM (URO-SSE-04-A100J) was last used on an ILT NRC Exam administered at Callaway in 2009. Upon completion of this JPM, the applicant will have performed a manual QPTR calculation with a final QPTR tolerance of

+/- 0.01.

A2 This is a MODIFIED JPM. The parent JPM was used on the 2009 ILT NRC exam. The candidate is to determine the maximum RV Venting time using EOP Addendum 33.

Upon completion of this JPM, the applicant will have determined RV Venting time to be between 1.72 and 1.84 minutes.

A3 This BANK JPM was used on the 2013 ILT NRC Exam. 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. Upon completion of this JPM, the applicant reported that the following equipment could be started: CGM01A, DG Vent Sply Fan A, SGK04A, Ctrl Rm A/C Unit A, PEC01A, Fuel Pool Clg Pmp A.

A4 This is a MODIFIED JPM from the 2013 Palo Verde ILT NRC Exam. This JPM requires the RO to review given conditions and determine RWP to be used, required dosimetry.

Dose and dose rate alarm, protective clothing required, and required RP briefing or authorization for the task will be performed; in accordance with APA-ZZ-01004, Radiological Work standards, and HDP-ZZ-01500, Radiological Postings. Upon completion of the JPM the applicant will have identified the following:

RWP to be used 160501ROUTINE Required Dosimetry OSLD and Electronic Dosimeter Dose Alarm 11 mRem Dose Rate Alarm 100 mRem Protective Clothing Requirements Full set of Protective Clothing in Contaminated Areas.

OR Partial PC's allowed for tours, inspections, and work below grating as allowed by RP.

Required RP briefing and/or authorization Contact RP for Survey Prior to Entry (CRP)

ES-301 Administrative Topics Outline Form ES-301-1 Rev 2 NUREG-1021, Revision 10 Page 1 of 2 Facility:

Callaway Date of Examination:

5/23/2016 Examination Level:

SRO Operating Test Number:

2016 - 1 Administrative Topic (see Note)

Type Code*

Describe activity to be performed Conduct of Operations A5 R, M 2.1.37 (4.6)

Knowledge of procedures, guidelines, or limitations associated with reactivity management JPM:

Review a QPTR Calculation Conduct of Operations A6 R, M 2.1.25 (4.2)

Ability to interpret reference materials such as graphs, curves, tables, etc JPM:

Determine RV Venting Time (EOP ADD 33)

Equipment Control A7 R, D, P 2.2.37 (4.6)

Ability to determine operability and/or availability of safety related equipment JPM:

Determine Amperage Limits for 480 VAC Safety Related busses Radiation Control A8 R, M 2.3.4 (3.7)

Knowledge of radiation exposure limits under normal or emergency conditions JPM:

Select Volunteer for Emergency Exposure Emergency Procedures/Plan A9 R, M 2.4.44 (4.4)

Make a Protective Action Recommendation JPM:

Determine the Protective Action Recommendation (PAR)

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)

No JPMs from the last 2 SRO exams (including the 2013 re-exam) were selected for this exam. JPM A7 was on the 2013 RO exam. This JPMs was randomly selected by placing 4 slips of paper labeled A1.a 2013 through A4 2013 in a hardhat. A2 2013was drawn from the hardhat.

ES-301 Administrative Topics Outline Form ES-301-1 Rev 2 NUREG-1021, Revision 10 Page 2 of 2 A5 This is a MODIFIED JPM. The parent JPM (SRO-MAS-04-A006J) has not been used on an NRC Exam administered at Callaway between 2004 and 2014. Upon completion of this JPM, the applicant will have reviewed a manual QPTR calculation with a final QPTR tolerance of +/- 0.01 and determined that N44 Lower detector is greater than 1.02 and entered T/S 3.2.4.A, and entered the data on Attachment 2.

A6 This is a MODIFIED JPM. The parent JPM (RA2) was used on the 2009 ILT NRC exam.

The candidate is to determine the maximum RV Venting time using EOP Addendum 33.

Upon completion of this JPM, the applicant will have determined RV Venting time to be between 1.72 and 1.84 minutes.

A7 This BANK JPM was used on the 2013 ILT NRC Exam. 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. Upon completion of this JPM, the Applicant reported that the following equipment could be started: CGM01A, DG Vent Sply Fan A, SGK04A, Ctrl Rm A/C Unit A, PEC01A, Fuel Pool Clg Pmp A A8 This is a MODIFIED JPM. The parent JPM (SRO-RER-03-A203J) was used on the 2009 ILT NRC exam. The applicant will be given a set of conditions and the appropriate procedures in an emergency radiological situation need to determine which volunteer may receive and emergency exposure. Upon completion of this JPM, Candidate selected Volunteer #5 to attempt the rescue of the injured operator in accordance with HDP-ZZ-01450 and completed Section 1 of CA0276 correctly in accordance with the KEY.

A9 This is a MODIFIED JPM. The parent JPM (SRO-RER-02-A031J(TC)) was used on the 2011 ILT NRC exam. The applicant will be assigned the task of determining the Protective Action Recommendation (PAR) within the allotted amount of time. Upon completion of this JPM the applicant will have identified the PAR as Evacuate 2 Mile Radius and 10 miles downwind (Sectors G, H, J).

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Rev 2 Page 1 of 4 Facility: __Callaway___________________________

Date of Examination: _5/23/2016___

Exam Level: RO SRO-I SRO-U Operating Test No.: __2016-1_______

Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code*

Safety Function S1 001 Control Rod Drive System (SF) / Perform Control Rod Partial Movement Test D, S 1

S2 004 CVCS (BG) / Swap From the NCP to 'B' CCP A, D, S 2

S3 010 Pressurizer Pressure Control System (BB) / Respond to a Master Pressure Controller Failure A, D, S 3

S4 059 Main Feedwater System (AE) / Transfer Steam Generator Water Level Control A, N, S 4S S5 005 Residual Heat Removal System (EJ) / Transfer to Hot Leg Recirculation A, D, L, EN, S 4P S6 062 A.C. Electrical Distribution (PA) / Perform Operational Testing of the Alternate Emergency Power Source D, P1, S 6

S7 015 Nuclear Instrumentation System (SE) / Respond to a Failed Power Range Instrument D, S 7

S8 Containment Purge System (GT) / Remove Shutdown Purge System From Service N, L, S 8

In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P1 006 Emergency Core Cooling System (EP) / Secure Safety Injection Accumulators D, L 2

P2 035 Main and Reheat Steam System (AB) / Isolate a Failed Open Atmospheric Steam Dump A, M, E, R 4S P3 062 AC Electrical Distribution System (NN) / Transfer NN01 from Manual Bypass to Normal M

6 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Rev 2 Page 2 of 4 A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)

(P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 9 / 8 / 4 1 / 1 / 1 1 / 1 / 1 (control room system) 1 / 1 / 1 2 / 2 / 1 3 / 3 / 2 (randomly selected) 1 / 1 / 1 Note 1.

The JPMs from the 2013 exam were randomly selected by placing 11 slips of paper labeled S1 through P3 in a hardhat. S6 was drawn from the hardhat.

S1 This is a BANK JPM. The JPM (URO-SSF-01-C005J) was used on the 2009 ILT NRC Exam. The applicant will be assigned the task of performing control rod partial movement for all shutdown banks, per OSP-SF-00002, Control Rod Partial Movement, beginning at step 6.1 Upon completion of this JPM, the applicant will have inserted all shutdown bank A control rods at least 12 steps into the core and restored them to their pretest position per procedural requirements.

S2 This is an ALTERNATE PATH, BANK JPM. The JPM (URO-SBG-02-C160J (A))

has not been used on an NRC ILT Exam administered at Callaway between 2004 and 2014.The applicant will perform the actions of OTN-BG-00001, Addendum 1 to shift from the NCP to the B CCP. After the B CCP is started and during the transition from the NCP flow controller to the B CCP flow controller, the B CCP will Trip, requiring the applicant to restore charging flow. Upon completion of this JPM the applicant will have restored charging flow to normal.

S3 This is an ALTERNATE PATH, BANK JPM. The JPM (URO-SBB-04-C166J(A))

was used on the 2009 ILT NRC Exam. The applicant will be directed to to equalize RCS and Pressurizer Boron Concentration using OTG-ZZ-00004, Addendum 03. When the master pressure controller is taken to AUTO the PZR spray valves fail open requiring the applicant to manually close the spray valves.

Upon completion of this JPM, the master pressure controller failure has been addressed prior to a Reactor Trip being generated on low pressurizer pressure.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Rev 2 Page 3 of 4 S4 This is an ALTERNATE PATH, NEW JPM. The applicant will be assigned the task transferring Steam Generator Water Level Control from the MFRV Bypass Valves to the Main Feedwater Regulating Valves using OTN-AE-00001, Feedwater System. During the transfer the D MFRV will not open. The applicant will abort the automatic valve transfer and manually maintain SGWL. Upon completion of this JPM, the applicant will have transferred Steam Generator Water Level Control from the MFRV Bypass Valves to the MFRVs for SG A, B, and C and taken manual control of SG D water level without causing a Reactor Trip or Feedwater Isolation Signal due to high or low Steam Generator water level.

S5 This is an ALTERNATE PATH, The JPM (URO-AEO-02-C201J(A)) has not been used on an NRC ILT Exam administered at Callaway between 2004 and 2014.

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-1.4, Transfer to Hot Leg Recirculation.

During performance, the applicant determines that HV8840 will not open and must use the alternate line up to achieve hot leg recirc. Upon completion of this JPM, the applicant will have aligned SI pumps to inject into the RCS hot legs.

S6 This is a BANK JPM that was used on the 2013 ILT NRC Exam (S6 on 2013 exam). It was randomly selected using the method described above. The applicant will be assigned the task of performing an online test of Alternate Emergency Power Source Diesel Generator #4 from the Control Room. Upon completion of this JPM, the applicant will have started AEPS Diesel Generator

4, taken readings and secured the diesel.

S7 This is a BANK JPM. The JPM (URO-SSE-03-C126J) has not been used on an NRC ILT Exam administered at Callaway between 2004 and 2014. The applicant will perform the actions of OTO-SE-00001, Nuclear Instrument Malfunction, Attachment A to bypass the Power Range NIS Channel N41 current comparator and rod stop inputs. Upon Completion of this JPM, Power Range NIS channel N41 current comparator and rod stop inputs will be bypassed.

S8 This is a NEW JPM. The applicant will perform the actions of OTN-GT-00001, Containment Purge System, to remove containment shutdown purge from service. Upon completion of this JPM, the applicant will have removed containment shutdown purge from service IAW OTN-GT-00001.

P1 This is a BANK JPM. The JPM (RO-SRO Au j) has not been used on an NRC ILT Exam administered at Callaway between 2004 and 2014. The applicant will be assigned the task of locally securing Safety Injection accumulators per OTG-ZZ-00006, Addendum. Upon completion of this JPM, the applicant will have closed the SI Accumulator Outlet Isolation Valves and opened the feeder breakers to the SI accumulator outlet isolation valves.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Rev 2 Page 4 of 4 P2 This is an ALTERNATE PATH, MODIFIED JPM. The parent JPM (EOP-SAB08077J(A)) has not been used on an NRC ILT Exam administered at Callaway between 2004 and 2014. The applicant will be assigned the task of locally closing Atmospheric Steam Dumps, AB PV-3 AND AB PV-4. Upon completion of this JPM, the applicant will have closed AB PV-3 and isolated AB PV-4. AB PV-3 was closed by isolating Air/N2 from the valve. AB PV-4 was isolated by closing the manual isolation valve, ABV0007.

P3 This is a MODIFIED JPM. The parent JPM (EOS-SNN-03-P010J) has not been used on an NRC ILT Exam administered at Callaway between 2004 and 2014.

The applicant will be assigned the task of transferring NN01 to the normal power source per OTN-NN-00001. Upon completion of this JPM the applicant will have transferred NN01 to the normal power supply (inverter and NK01) without a loss of voltage.

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Rev 1 Page 1 of 4 Facility: __Callaway___________________________

Date of Examination: _5/23/2016___

Exam Level: RO SRO-I SRO-U Operating Test No.: __2016-1_______

Control Room Systems:* 8 for RO; 7 for SRO-I; 2 or 3 for SRO-U System / JPM Title Type Code*

Safety Function S1 001 Control Rod Drive System (SF) / Perform Control Rod Partial Movement Test D, S 1

S2 004 CVCS (BG) / Swap From the NCP to 'B' CCP A, D, S 2

S3 010 Pressurizer Pressure Control System (BB) / Respond to a Master Pressure Controller Failure A, D, S 3

S4 059 Main Feedwater System (AE) / Transfer Steam Generator Water Level Control A, N, S 4S S5 005 Residual Heat Removal System (EJ) / Transfer to Hot Leg Recirculation A, D, L, EN, S 4P S6 062 A.C. Electrical Distribution (PA) / Perform Operational Testing of the Alternate Emergency Power Source D, P1, S 6

S7 015 Nuclear Instrumentation System (SE) / Respond to a Failed Power Range Instrument D, S 7

In-Plant Systems* (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

P1 006 Emergency Core Cooling System (EP) / Secure Safety Injection Accumulators D, L, R 2

P2 035 Main and Reheat Steam System (AB) / Isolate a Failed Open Atmospheric Steam Dump A, M, E, R 4S P3 062 AC Electrical Distribution System (NN) / Transfer NN01 from Manual Bypass to Normal M

6 All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all five 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

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Rev 1 Page 2 of 4 A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A)