ML15293A561

2015-10 Final Outlines

ML15293A561
Person / Time
Site:	South Texas
Issue date:	10/02/2015
From:	Vincent Gaddy Operations Branch IV
To:	South Texas
References
Download: ML15293A561 (51)

Text

ES-401 PWR RO Examination Outline FORM ES-401-2 Facility: STP Date of Exam:

RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total

1. 1 3 3 3 3 3 3 18 6 Emergency &

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

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

3. Generic Knowledge and Abilities Categories 1 2 3 4 10 1 2 3 4 7 3 2 2 3 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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery / 1 000008 Pressurizer Vapor Space Accident / 3 Knowledge of the operational implications of the 000009 Small Break LOCA / 3 X following concepts as 3.5 1 they apply to the small break LOCA:

(CFR 41.8 / 41.10 / 45.3)

EK1.02 Use of steam tables RO 3.5/SRO 4.2 000011 Large Break LOCA / 3 000015/17 RCP Malfunctions / 4 X Ability to operate and / or monitor the following 4.0 2 as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow)

(CFR 41.7 / 45.5 / 45.6)

AA1.22 RCP seal failure/malfunction RO 4.0/SRO4.2 000022 Loss of Rx Coolant Makeup / 2 Ability to determine and interpret the following 000025 Loss of RHR System / 4 X as they apply to the Loss of Residual Heat 3.4 3 Removal System:

(CFR: 43.5 / 45.13)

AA2.07 Pump cavitation RO 3.4/SRO 3.7 G 2.4.4 Ability to recognize abnormal indications 000026 Loss of Component Cooling X for systems operating parameters that are entry 3.9 4 Water / 8 level conditions for emergency and abnormal operating procedures.

(CFR: 45.2 / 45.6)

RO 3.9/SRO 4.0 Knowledge of the operational implications of the 000027 Pressurizer Pressure Control X following concepts as they apply to Pressurizer 2.8 5 System Malfunction / 3 Pressure Control Malfunctions:

(CFR 41.8 / 41.10 / 45.3)

AK1.02 Expansion of liquids as temperature increases RO2.8/SRO 3.1

ES-401 3 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO)

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

1 2 3 1 2 Knowledge of the interrelations between the and 000029 ATWS / 1 X the following an ATWS: 2.9 6 (CFR 41.7 / 45.7)

EK2.06 Breakers, relays, and disconnects RO 2.9*/SRO 3.1*

Knowledge of the reasons for the following 000038 Steam Gen. Tube Rupture / 3 X responses as the apply to the SGTR: 4.4 7 (CFR 41.5 / 41.10 / 45.6 / 45.13)

EK3.02 Prevention of secondary PORV cycling RO 4.4/SRO 4.5 Ability to operate and / or monitor the following 000040 (BW/E05; CE/E05; W/E12) X as they apply to the Steam Line Rupture: 3.9 8 Steam Line Rupture - Excessive Heat Transfer / 4 (CFR 41.7 / 45.5 / 45.6)

AA1.15 T-ave. protection indicators RO 3.9*/SRO 3.8*

Ability to determine and interpret the following 000054 (CE/E06) Loss of Main X as they apply to the Loss of Main Feedwater 4.1 9 Feedwater / 4 (MFW):

(CFR: 43.5 / 45.13)

AA2.03 Conditions and reasons for AFW pump startup RO 4.1/SRO 4.2 000055 Station Blackout / 6 X 2.4.1 Knowledge of EOP entry conditions and 4.6 10 immediate action steps (CFR: 41.10 / 43.5 / 45.13)

RO 4.6 / SRO 4.8 Ability to operate and / or monitor the following 000056 Loss of Off-site Power / 6 X as they apply to 3.6 11 the Loss of Offsite Power:

(CFR 41.7 / 45.5 / 45.6)

AA1.06 Safety injection pump RO 3.6*/SRO 3.6*

Knowledge of the reasons for the following 000057 Loss of Vital AC Inst. Bus / 6 X responses as they apply to 4.1 12 the Loss of Vital AC Instrument Bus:

(CFR 41.5,41.10 / 45.6 / 45.13)

AK3.01 Actions contained in EOP for loss of vital ac electrical instrument bus RO 4.1/SRO 4.4

ES-401 4 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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 Knowledge of the reasons for the following 000058 Loss of DC Power / 6 X responses as they apply to 4.0 13 the Loss of DC Power:

(CFR 41.5,41.10 / 45.6 / 45.1)

AK3.02 Actions contained in EOP for loss of dc power RO 4.0/SRO 4.2 000062 Loss of Nuclear Svc Water / 4 X Ability to determine and interpet the following as 2.9 they apply to the Loss of Nuclear Service Water (SWS):

CFR 43.5 / 45.13) 14 AA2.01 Location of leak in the SWS RO 2.9/SRO3.6 000065 Loss of Instrument Air / 8 2.1.28 Knowledge of the purpose and function of W/E04 LOCA Outside Containment / 3 X major system components and controls. 3.2 15 (CFR: 41.7)

RO 3.2/SRO 3.3 Knowledge of the operational implications of the W/E11 Loss of Emergency Coolant X following concepts as they apply to the (Loss of 16 Recirc. / 4 Emergency Coolant Recirculation)

(CFR: 41.8 / 41.10 / 45.3)

EK1.1 Components, capacity, and function of 3.7 emergency systems.

RO 3.7/SRO 4.0 Knowledge of the interrelations between the BW/E04; W/E05 Inadequate Heat X (Loss of Secondary Heat Sink) and the following: 3.9 17 Transfer - Loss of Secondary Heat Sink / 4 (CFR: 41.7 / 45.7)

EK2.2 Facility*s 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.

RO 3.9/SRO 4.2 Knowledge of the interrelations between 000077 Generator Voltage and Electric X Generator Voltage and Electric Grid Disturbances 3.1 18 Grid Disturbances / 6 and the following:

(CFR: 41.4, 41.5, 41.7, 41.10/ 45.8)

AK 2.0 1 Motors RO 3.1/SRO 3.2 K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18/6

ES-401 5 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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 000001 Continuous Rod Withdrawal / 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 Knowledge of the reasons for the 000033 Loss of Intermediate Range NI / 7 X 3.6 19 following responses as they apply to the Loss of Intermediate Range Nuclear Instrumentation:

(CFR 41.5,41.10 / 45.6 / 45.13)

AK3.02 Guidance contained in EOP for loss of intermediate range instrumentation.

RO 3.6/SRO 3.9 Ability to operate and / or monitor the 000036 (BW/A08) Fuel Handling Accident / 8 X 3.5 20 following as they apply to the Fuel Handling Incidents:

(CFR 41.7 / 45.5 / 45.6)

AA1.03 Reactor building containment evacuation alarm enable switch.

RO 3.5/SRO 3.9 Ability to operate and / or monitor the 000037 Steam Generator Tube Leak / 3 X 3.8 21 following as they apply to the Steam Generator Tube Leak:

(CFR 41.7 / 45.5 / 45.6)

AA1.06 Main steam line rad monitor meters RO 3.8*/SRO 3.9*

Ability to determine and interpret the 000051 Loss of Condenser Vacuum / 4 X 3.9 22 following as they apply to the Loss of Condenser Vacuum:

(CFR: 43.5 / 45.13)

AA2.02 Conditions requiring reactor and/or turbine trip.

RO 3.9/SRO 4.1 2.1.32 Ability to explain and apply all 000059 Accidental Liquid RadWaste Rel. / 9 X 3.4 23 system limits and precautions.

(CFR: 41.10 / 43.2 / 45.12)

RO 3.4/ SRO 3.8

ES-401 6 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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 Knowledge of the operational 000060 Accidental Gaseous Radwaste Rel. / 9 X 2.5 24 implications of the following concepts as they apply to Accidental Gaseous Radwaste Release:

(CFR 41.8 / 41.10 / 45.3)

AK1.02 Biological effects on humans of the various types of radiation, exposure levels that are acceptable for personnel in a nuclear reactor power plant; the units used for radiation intensity measurements and for radiation exposure levels.

RO 2.5/SRO 3.1*

Knowledge of the interrelations between 000061 ARM System Alarms / 7 X 2.5 25 the Area Radiation Monitoring (ARM)

System Alarms and the following:

(CFR 41.7 / 45.7)

AK2.01 Detectors at each ARM system location.

RO 2.5*/SRO 2.6*

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 X Knowledge of the operational 3.4 26 implications of the following concepts as they apply to the (SI Termination)

(CFR: 41.8 / 41.10, 45.3)

EK1.2 Normal, abnormal and emergency operating procedures associated with (SI Termination).

RO 3.4/SRO 3.9 W/E13 Steam Generator Over-pressure / 4 X Knowledge of the interrelations between 3.0 27 the (Steam Generator Overpressure) and the following:

(CFR: 41.7 / 45.7)

EK2.2 Facility*s 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.

RO 3.0/SRO 3.2 W/E15 Containment Flooding / 5

ES-401 7 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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 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 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 2 1 1 1 Group Point Total: 9/4

ES-401 8 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 Ability to predict and/or monitor 003 Reactor Coolant Pump X changes in parameters (to prevent 2.6 28 exceeding design limits) associated with operating the RCPS controls including:

(CFR: 41.5 / 45.7)

A1.03 RCP motor stator winding temperatures RO 2.6 /SRO 2.6 Knowledge of the effect of a loss or 004 Chemical and Volume X malfunction on the following CVCS 4.4 29 Control components:

(CFR: 41.7 / 45.7)

K6.17 Flow paths for emergency boration RO 4.4/SRO 4.6 Ability to (a) predict the impacts of the 005 Residual Heat Removal X following malfunctions or operations 2.7 30 on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45.3 / 45.13)

A2.01 Failure modes for pressure, flow, pump motor amps, motor temperature, and tank level instrumentation RO 2.7/SRO 2.9*

Knowledge of the operational 006 Emergency Core Cooling X implications of the following concepts 2.5 31 as they apply to ECCS:

(CFR: 41.5 / 45.7)

K5.11 Basic heat transfer equation RO 2.5/SRO 2.4*

Ability to monitor automatic 007 Pressurizer Relief/Quench X operation of the PRTS, including: 2.7 32 Tank (CFR: 41.7 / 45.5)

A3.01 Components which discharge to the PRT.

RO 2.7*/SRO 2.9

ES-401 9 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 Ability to manually operate and/or 008 Component Cooling Water X monitor in the control room: 2.7 33 (CFR: 41.7 / 45.5)

A4.05 Normal CCW-header total flow rate and the flow rates to the components cooled by the CCWS.

RO 2.7*/ 2.5 Knowledge of bus power supplies to 010 Pressurizer Pressure Control X the following: 3.0 34 (CFR: 41.7)

K2.01 Pressurizer Heaters RO 3.0/SRO 3.4 Knowledge of RPS design feature(s) 012 Reactor Protection X and/or interlock(s) which provide for 3.2 35 the following:

(CFR: 41.7)

K4.06 Automatic or manual enable/disable of RPS trips RO 3.2/ SRO 3.5 Ability to monitor automatic 013 Engineered Safety Features X operation of the ESFAS including: 3.7 36 Actuation (CFR: 41.7/45.5)

A3.01 Input channels and logic RO 3.7*/SRO 3.9 Knowledge of the effect that a loss or 022 Containment Cooling X malfunction of the CCS will have on 3.0 37 the following:

(CFR: 41.7 / 45.6)

K3.02 Containment instrumentation readings.

RO 3.0/SRO 3.3 025 Ice Condenser

ES-401 10 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 Knowledge of CSS design feature(s) 026 Containment Spray X and/or interlock(s) which provide for 4.1 38 the following:

(CFR: 41.7)

K4.08 Automatic swapover to containment sump suction for recirculation phase after LOCA (RWST low-low level alarm)

RO 4.1*/SRO 4.3*

Knowledge of the operational 039 Main and Reheat Steam X implications of the following concepts 2.7 39 as the apply to the MRSS:

(CFR: 41.5 / 45.7)

K5.05 Bases for RCS cooldown limits RO 2.7/SRO 3.1*

Ability to predict and/or monitor 059 Main Feedwater X changes in parameters (to prevent 2.7 40 exceeding design limits) associated with operating the MFW controls including:

(CFR: 41.5 / 45.5)

A1.03 Power level restrictions for operation of MFW pumps and valves RO 2.7*/SRO 2.9*

Ability to (a) predict the impacts of the 061 Auxiliary/Emergency X following malfunctions or operations 3.4 41 Feedwater on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45.3 / 45.13)

A2.07 Air or MOV failure.

RO 3.4/SRO 3.5 2.4.3 Ability to identify post-accident 062 AC Electrical Distribution X instrumentation. 3.7 42 (CFR: 41.6 / 45.4)

RO 3.7/SRO 3.9 063 DC Electrical Distribution X 2.2.39 Knowledge of less than or equal 3.9 43 to one hour Technical Specification action statements for systems.

RO 3.9/SRO 4.5

ES-401 11 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 Knowledge of the effect of a loss or 064 Emergency Diesel Generator X malfunction of the following will have 3.2 44 on the ED/G system:

(CFR: 41.7 / 45.7)

K6.08 Fuel oil storage tanks RO 3.2/ SRO 3.3 Knowledge of the physical connections 073 Process Radiation X and/or cause effect relationships 3.6 45 Monitoring between the PRM system and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Those systems served by PRMs RO 3.6/SRO 3.9 Ability to predict and/or monitor 076 Service Water X changes in parameters (to prevent 2.6 46 exceeding design limits) associated with operating the SWS controls including:

(CFR: 41.5 / 45.5)

A1.02 Reactor and turbine building closed cooling water temperatures RO 2.6*/SRO 2.6*

K3 Knowledge of the effect that a loss 078 Instrument Air X or malfunction of the IAS will have on 3.4 47 the following:

(CFR: 41.7 / 45.6)

K3.02 Systems having pneumatic valves and controls.

RO 3.4/SRO 3.6 Knowledge of containment system 103 Containment X design feature(s) and/or interlock(s) 3.1 48 which provide for the following:

(CFR: 41.7)

K4.06 Containment isolation system.

RO 3.1/SRO 3.7

ES-401 12 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 2.2.42 Ability to recognize indications 008 Component Cooling Water X for system operating parameters 3.4 49 which are entry-level conditions for technical specifications.

(CFR: 43.2 / 43.3 / 45.3)

RO 3.4/ SRO 4.0 Knowledge of the effect that a loss or 026 Containment Spray X malfunction of the CSS will have on 4.2 50 the following:

(CFR: 41.7 / 45.6)

K3.02 Recirculation spray system RO 4.2/SRO 4.3 Knowledge of the physical connections 063 DC Electrical Distribution X and/or cause/effect relationships 2.9 51 between the DC electrical system and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.03 Battery charger and battery RO 2.9/SRO 3.5 Ability to (a) predict the impacts of the 064 Emergency Diesel Generator X following malfunctions or operations 2.7 52 on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45.3 / 45.13)

A2.08 Consequences of opening/closing breaker between buses (VARS, out-of-phase, voltage).

RO 2.7/SRO 3.1 Ability to manually operate and/or 076 Service Water X monitor in the control room: 2.9 53 (CFR: 41.7 / 45.5 to 45.8)

A4.01 SWS pumps RO 2.9/ SRO 2.9

ES-401 13 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 Ability to monitor automatic 078 Instrument Air X operation of the IAS, including: 3.1 54 (CFR: 41.7 / 45.5)

A3.01 Air Pressure.

RO 3.1/SRO 3.2 Knowledge of bus power supplies to 005 Residual Heat Removal X the following: 3.2 55 (CFR: 41.7)

K2.01 RHR pumps RO 3.0/ SRO 3.2 K/A Category Point Totals: 2 2 3 3 2 2 3 3 3 3 2 Group Point Total: 28/

5

ES-401 14 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K1 K K K K K A A A A G K/A Topic(s) IR #

2 3 4 5 6 1 2 3 4 001 Control Rod Drive 002 Reactor Coolant 011 Pressurizer Level Control X Knowledge of bus power supplies to the 3.1 56 following:

(CFR: 41.7)

K2.01 Charging pumps RO 3.1/SRO 3.2 014 Rod Position Indication Knowledge of NIS design feature(s) 015 Nuclear Instrumentation X and/or interlock(s) provide for the 3.7 57 following:

(CFR: 41.7)

K4.07 Permissives RO 3.7/SRO 3.8 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control Ability to (a) predict the impacts of the 029 Containment Purge X following malfunctions or operations on 2.9 58 the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45.3 / 45.13)

A2.01 Maintenance or other activity taking place inside containment.

RO 2.9/SRO 3.6 Ability to monitor automatic operation 033 Spent Fuel Pool Cooling X of the Spent Fuel Pool Cooling System 2.9 59 including:

(CFR: 41.7 / 45.5)

A3.02 Spent fuel leak or rupture RO 2.9/SRO 3.1 034 Fuel Handling Equipment

ES-401 15 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K1 K K K K K A A A A G K/A Topic(s) IR #

2 3 4 5 6 1 2 3 4 035 Steam Generator X Knowledge of the effect of a loss or 2.6 60 malfunction on the following will have on the S/GS:

(CFR: 41.7 / 45.7)

K6.03 S/G level detector RO 2.6/SRO 3.0 041 Steam Dump/Turbine X Ability to predict and/or monitor 3.1 61 Bypass Control changes in parameters (to prevent exceeding design limits) associated with operating the SDS controls including:

(CFR: 41.5 / 45.5)

A1.02 Steam pressure RO 3.1/SRO 3.2 Knowledge of the effect that a loss or 045 Main Turbine Generator X malfunction of the MT/G system will 2.9 62 have on the following:

(CFR: 41.7 / 45.6)

K3.01 Remainder of the plant RO 2.9/SRO 3.2 055 Condenser Air Removal Knowledge of the physical connections 056 Condensate X and/or cause-effect relationships 2.6 63 between the Condensate System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.03 MFW RO 2.6*/SRO 2.6 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring

ES-401 16 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K1 K K K K K A A A A G K/A Topic(s) IR #

2 3 4 5 6 1 2 3 4 Ability to (a) predict the impacts of the 075 Circulating Water X following malfunctions or operations on 2.5 64 the circulating water system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45.3 / 45.13)

A2.02 Loss of circulating water pumps RO 2.5 / SRO 2.7 079 Station Air Ability to monitor automatic operation 086 Fire Protection X of the Fire Protection System including: 65 2.9 (CFR: 41.7 / 45.5)

A3.01 Starting mechanisms of fire water pumps RO 2.9/SRO 3.3 K/A Category Point Totals: 1 1 1 1 0 1 1 2 1 1 0 Group Point Total: 10/

3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) FORM ES-401-3 Facility: STP Date of Exam:

Category K/A # Topic RO SRO-Only IR # IR #

2.1.18 Ability to make accurate, clear, and concise logs, 2.1. 3.6 66 records, status boards, and reports.

(CFR: 41.10 / 45.12 / 45.13) 1.

Conduct RO 3.6 SRO 3.8 of Operations 2.1.21 Ability to obtain and verify controlled procedure copy.

2.1. 3.1 67 (CFR: 45.10 / 45.13)

RO 3.1 SRO 3.2 2.1.3 Knowledge of shift turnover practices.

2.1. 3.0 68 (CFR: 41.10 / 45.13)

RO 3.0 SRO 3.4 Subtotal 2.2.13 Knowledge of tagging and clearance procedures.

2.2. 3.6 69 (CFR: 41.10 / 45.13)

RO 3.6 SRO 3.8

2. 2.2.22 Knowledge of limiting conditions for operations and 2.2. 3.4 70 Equipment safety limits.

Control (CFR: 43.2 / 45.2)

RO 3.4 SRO 4.1 Subtotal 2.3.12 Knowledge of radiological safety principles pertaining 2.3. 3.2 71 to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

3.

Radiation Control (CFR: 41.12 / 45.9 / 45.10)

IMPORTANCE RO 3.2 SRO 3.7 2.3.4 Knowledge of radiation exposure limits and 2.3. 2.5 72 contamination control, including permissible levels in excess of those authorized.

(CFR: 43.4 / 45.10)

RO 2.5 SRO 3.1 Subtotal 2.1.18 Ability to make accurate, clear, and concise logs, 2.4. 3.6 73 records, status boards, and reports.

(CFR: 41.10 / 45.12 / 45.13) 4.

Emergency RO 3.6 SRO 3.8 Procedures / 2.4.16 Knowledge of EOP implementation hierarchy and 2.4. 3.5 74 Plan coordination with other support procedures.

(CFR: 41.10 / 43.5 / 45.13)

RO 3.5 SRO 4.4

ES-401 Generic Knowledge and Abilities Outline (Tier 3) FORM ES-401-3 Facility: STP Date of Exam:

Category K/A # Topic RO SRO-Only IR # IR #

2.4.17 Knowledge of EOP terms and definitions.

2.4. 3.9 75 (CFR: 41.10 / 45.13)

IMPORTANCE RO 3.9 SRO 4.3 Subtotal Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As FORM ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/1 EK1.02 This was supposed to be a generic K/A, EK 1.02 mistakenly selected. Replace with Generic K/A 2.4.1 2/1 2.1.33 This K/A is not one of the topics for Tiers 1 and 2 Generic K/As. Replace with K/A 2.1.25 3/1 2.1.11 This K/A was moved with the release of Revision 2, Supplement 1 of NUREG 1021. Replace with K/A 2.1.18 3/3 2.3.1 This K/A was moved with the release of Revision 2, Supplement 1 of NUREG 1021. Replace with K/A 2.3.12 3/4 2.4.15 This K/A was moved with the release of Revision 2, Supplement 1 of NUREG 1021. Replace with K/A 2.4.17 1/1 000022 Loss of Rejected K/A as could not come up with a quality question.

Rx Coolant Replaced with 000015/17 RCP Malfunctions / 4, AA1.22 RCP Makeup / 2 Seal failure/malfunction Ability to operate and / or monitor the following as they apply to the Loss of Reactor Coolant Pump Makeup:

AA1.07 Excess letdown containment isolation valve switches and indicators

ES-401 2 FORM ES-401-4 1/1 000057 Loss There are no Knowledge factors listed in NUREG 1122 Rev 2 of Vital AC Inst. with an importance factor of greater than 2.5.

Bus / 6 Replaced with AK3 of same system.

AK2 Knowledge of the interrelations between the Loss of Vital AC Instrument Bus and the following:

(CFR 41.7 / 45.7) 1/1 000077 Generator Replaced with AK2 of same Emergency/Abnormal system to Voltage and even out the distribution of knowledge attributes Electric Grid Disturbances / 6 AK3 Knowledge of the operational implications of the following concepts as they apply to Generator Voltage and Electric Grid Disturbances:

(CFR: 41.4, 41.5, 41.7, 41.10 / 45.8) 000033 Loss 1/1 There are no Knowledge factors listed in NUREG 1122 Rev 2 of Intermediate with an importance factor of greater than 2.5.

Range NI / 7 K2Knowledge of Replaced with AK3 of same system.

the interrelations between the Loss of Intermediate Range Nuclear Instrumentation and the following:

(CFR 41.7 / 45.7)

ES-401 3 FORM ES-401-4 000065 Loss of 1/1 Instrument Air / 8 Resampled to due to excessive number of Instrument air questions on the exam.

Ability to determine and Replaced with 062 Loss of Nuclear Service Water A2.02 interpret the following as they apply to the Loss of Instrument Air:

(CFR: 43.5 /

45.13)

AA2.08 Failure modes of air-operated equipment RO2.9*/SRO 3.3 026 Containment 2/1 Spray There are no Knowledge factors listed in NUREG 1122 Rev 2 with an importance factor of greater than 2.5.

K5 Knowledge of Replaced with a K4 of the same system operational implications of the following concepts as they apply to the CSS:

(CFR: 41.5 / 45.7) 2/1 039 Main There are no Knowledge factors listed in NUREG 1122 Rev 2 and Reheat with an importance factor of greater than 2.5.

Steam Replaced with a K5 of the same system Knowledge of the effect of a loss or malfunction on the following will have on the MRSS:

(CFR: 41.7 / 45.7)

ES-401 4 FORM ES-401-4 2/ 1 008 Component There are no Knowledge factors listed in NUREG 1122 Rev 2 Cooling Water with an importance factor of greater than 2.5.

Knowledge of the Replaced with a K1 of the same system operational implications of the following concepts as they apply to the CCWS:

(CFR: 41.5 / 45.7) 2/1 026 Containment There are no Knowledge factors listed in NUREG 1122 Rev 2 Spray with an importance factor of greater than 2.5.

Knowledge of the effect of a loss or Replaced with a K3 of the same system malfunction of the following will have on the CSS:

(CFR: 41.7 / 45.7) 045 Main Turbine 2/ 2 There are no Knowledge factors listed in NUREG 1122 Rev 2 Generator with an importance factor of greater than 2.5.

Knowledge of bus power supplies to Replaced with a K3 of the same system the following:

(CFR: 41.7) 2/2 056 Condensate There are no Knowledge factors listed in NUREG 1122 Rev 2 Knowledge of with an importance factor of greater than 2.5.

Condensate Replaced with a K1 of the same system System design feature(s) and/or interlock(s) which provide for the following:

(CFR: 41.7) 079 Station Air 2/2 Knowledge of bus There are no Knowledge factors listed in NUREG 1122 Rev 2 with an importance factor of greater than 2.5.

power supplies to the following: Replaced with system 015 Nuclear Instrumentation K2 (CFR: 41.7)

ES-401 5 FORM ES-401-4 2/2 029 Containment There are no Knowledge factors listed in NUREG 1122 Rev 2 Purge with an importance factor of greater than 2.5.

Knowledge of the Replaced with a A2 of the same system operational implication of the following concepts as they apply to the Containment Purge System:

(CFR: 41.5 / 45.7) 3 2.4.22 Knowledge Difficulty writing a valid RO level question of the basis for prioritizing safety functions during abnormal/emerge ncy operations.

(CFR 41.7/43.5/41.10/4 5.12)

ES-401 PWR SRO Examination Outline FORM ES-401-2 Facility: STP Date of Exam: 9/24/2015 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total

1. 1 3 3 6 Emergency &

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

Plant 2 1 1 1 3 Systems Tier Totals 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 7 Categories 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#)

on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery / 1 000009 Small Break LOCA / 3 X EA2 Ability to determine or interpret the following as 4.2 they apply to a small break LOCA:

76 (CFR 43.5 / 45.13)

EA2.34 Conditions for throttling or stopping HPI EA2 Ability to determine or interpret the following as 000011 Large Break LOCA / 3 X they apply to a Large Break LOCA: 4.7 (CFR 43.5 / 45.13) 77 EA2.01 Actions to be taken, based on RCS temperature and pressure - saturated and superheated 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 000027 Pressurizer Pressure Control System Malfunction / 3 000029 ATWS / 1 EPE: 029 Anticipated Transient Without Scram 4.2 (ATWS)

(CFR: 41.10 / 43.5 / 45.12) 78 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

000038 Steam Gen. Tube Rupture / 3 X APE: 038 Steam Generator Tube Rupture 4.2 (CFR 55.43.2, 55.41.5, 55.41.7) 79 G2.2.25 Knowledge of the basis in the Technical Specifications for limiting conditions and safety limits 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 APE: 062 Loss of Nuclear Service Water 4.0 (CFR: 41.10 / 43.1 / 45.13) 80 2.4.18 Knowledge of the specific bases for EOPs.

ES-401 3 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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 AA2. Ability to determine and interpret the following 000065 Loss of Instrument Air / 8 X as they apply to the Loss of Instrument Air: 4.1 (CFR: 43.5 / 45.13) 81 AA2.05 When to commence plant shutdown if instrument air pressure is decreasing 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

ES-401 4 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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 000001 Continuous Rod Withdrawal / 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 X APE: 032 Loss of Source Range Nuclear 4.6 83 Instrumentation (CFR: 41.10 / 43.5 / 45.12) 2.1.20 Ability to interpret and execute procedure steps.

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 000069 (W/E14) Loss of CTMT Integrity / 5 000074 (W/E06&E07) Inad. Core Cooling / 4 X 2.4.21 Knowledge of the parameters and 4.6 82 logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc (CFR: 41.7 / 43.5 / 45.12)

RO 4.0/SRO 4.6 AA2. Ability to determine and interpret the 000076 High Reactor Coolant Activity / 9 X 85 following as they apply to the High Reactor Coolant Activity:

(CFR: 43.5 / 45.13)

AA2.02 Corrective actions required for high fission product activity in RCS. 3.4 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 X EA2. Ability to determine and interpret the 3.3 84 following as they apply to the (High Containment Radiation)

(CFR: 43.5 / 45.13)

EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

RO 2.9/SRO 3.3 BW/A01 Plant Runback / 1

ES-401 5 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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 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 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 6 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump 004 Chemical and Volume Control 005 Residual Heat Removal 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 010 Pressurizer Pressure Control 010 Pressurizer Pressure Control X 4.1 86 2.2.12 Knowledge of surveillance procedures.

(CFR: 41.10 / 45.13)

RO 3.7/SRO 4.1 012 Reactor Protection 013 Engineered Safety Features X APE: 013 Engineered Safety Features 4.7 87 Actuation Actuation System (ESFAS) 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

(CFR: 41.5 / 43.5 / 45.12 / 45.13)

RO 4.4 SRO 4.7 022 Containment Cooling 025 Ice Condenser 026 Containment Spray 039 Main and Reheat Steam 039 Main and Reheat Steam X 4.5 88 2.2.38 Knowledge of conditions and limitations in the facility license.

(CFR: 41.7 / 41.10 / 43.1 / 45.13)

RO 3.6 / SRO 4.5 059 Main Feedwater 061 Auxiliary/Emergency Feedwater 061 Auxiliary/Emergency X 3.8 89 Feedwater A2 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45.3 / 45.13)

A2.04 pump failure or improper operation.

062 AC Electrical Distribution

ES-401 7 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Monitoring 076 Service Water X A2 Ability to (a) predict the impacts of the 3.7 90 following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45/3 / 45/13)

A2.01 Loss of SWS 078 Instrument Air 103 Containment K/A Category Point Totals: 3 2 Group Point Total: 28/5

ES-401 8 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive 002 Reactor Coolant 011 Pressurizer Level Control 014 Rod Position Indication X 014 Rod position Indication 3.9 91 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.04 Misaligned rod 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation X 016 Non-nuclear Instrumentation 4.6 92 (CFR: 41.7 / 43.5 / 45.12) 2.2.37 Ability to determine operability and/or availability of safety related equipment.

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 034 Fuel Handling Equipment X 3.2 93 A1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the Fuel Handling System controls including:

(CFR: 41.5 / 45.5)

A1.01 Load limits 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

ES-401 9 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 079 Station Air 086 Fire Protection K/A Category Point Totals: 1 1 1 Group Point Total: 10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) FORM ES-401-3 Facility: Date of Exam:

Category K/A # Topic RO SRO-Only IR # IR #

2.1.36 Knowledge of procedures and limitations involved in core 2.1. alterations. 4.1 94 (CFR: 41.10 / 43.6 / 45.7)

1. 2.1.1 Knowledge of conduct of operations requirements.

Conduct 2.1. (CFR: 41.10 / 45.13) 4.2 95 of Operations 2.1.

2.1.

Subtotal 2.2.18 Knowledge of the process for managing maintenance 2.2. activities during shutdown operations, such as risk assessments, 3.9 96 work prioritization, etc.

(CFR: 41.10 / 43.5 / 45.13))

2. 2.2.6 Knowledge of the process for making changes to Equipment 2.2. procedures. 3.6 97 Control (CFR: 41.10 / 43.3 / 45.13) 2.2.

2.2.

Subtotal 2.3.13 Knowledge of radiological safety procedures pertaining to 2.3. licensed operator duties, such as response to radiation monitor 3.8 98 alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning

3. filters, etc.

Radiation (CFR: 41.12 / 43.4 / 45.9 / 45.10)

Control 2.3.

2.3.

Subtotal 2.4.30 Knowledge of events related to system operation/status 2.4. that must be reported to internal organizations or external 4.1 99 agencies, such as the State, the NRC, or the transmission

4. system operator.

Emergency (CFR: 41.10 / 43.5 / 45.11)

Procedures / 2.4.40 Knowledge of SRO responsibilities in emergency plan 2.4. implementation. 4.5 100 Plan (CFR: 41.10 / 43.5 / 45.11) 2.4.

2.4.

Subtotal Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As FORM ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 3/4 2.4.41 A question using this K/A could not be written without duplicating an Admin JPM. Replaced with 2.4.44

Rev. 0 ES-301 Administrative Topics Outline Form ES-301-1 Facility: South Texas Project Date of Examination: 09-28-2015 Examination Level: RO SRO Operating Test Number: LOT 20 NRC Exam Administrative Topic Type Describe activity to be performed (see Note) Code*

A1 Perform an RWST Blended Makeup Calculation Conduct of Operations N,R G2.1.25 Ability to interpret reference materials such as graphs, curves, tables, etc. (4.3/4.4)

A2 Verify an Excore QPTR Calculation Conduct of Operations D,P,R G2.1.20 Ability to interpret and execute procedural steps.

(4.6/4.6)

A3 Equipment Control Using Mechanical Drawings Determine the Isolation N,R Boundaries for a Leak on the RHR System G2.2.41 Ability to obtain and interpret station electrical NOTE: A3 and A7 are the and mechanical drawings. (3.5/3.9) same JPM.

A4 Calculate Stay Times based on Dose Rates M,R G2.3.4 Knowledge of radiation exposure limits under Radiation Control normal or emergency conditions. (3.2/3.7)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 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)

Rev. 0 ES-301 Administrative Topics Outline Form ES-301-1 Facility: South Texas Project Date of Examination: 09-28-2015 Examination Level: RO SRO Operating Test Number: LOT 20 NRC Exam Administrative Topic Type Describe activity to be performed (see Note) Code*

A5 Calculate SDM with a Misaligned Control Rod and Conduct of Operations M,R Determine Applicable Technical Specifications.

G2.1.37 Knowledge of procedures, guidelines or limitations associated with Reactivity Management. (4.3/4.69)

A6 Perform a Calorimetric Heat Balance and Evaluate Technical Conduct of Operations N,R Specifications G2.1.23 Ability to perform specific system and integrated plant procedures during all modes of operation. (4.3/4.4)

Equipment Control A7 Using Mechanical Drawings Determine the Isolation N,R Boundaries for a Leak on the RHR System NOTE: A3 and A7 are the G2.2.41 Ability to obtain and interpret station electrical and same JPM. mechanical drawings. (3.5/3.9)

A8 Approve completed Liquid Waste Release Permit. (alternate Radiation Control N,R path actual release did not match the approved release limits)

G2.3.6 Ability to approve release permits. (2.0/3.8)

A9 Determine EAL Emergency Procedures/Plan M,R G2.4.41 Knowledge of the emergency action level thresholds and classifications. (2.9/4.6)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 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)

Rev. 0 STP LOT-20 NRC Admin JPM Description RO (A1) Perform an RWST Blended Makeup Calculation Demonstrate the ability to set the boric acid flow integrator for a blended makeup to the RWST using 0POP02-CV-0001, Makeup to the Reactor Coolant System.

(A2) Verify an Excore QPTR Calculation Demonstrate the ability to perform and/or verify a QPTR. 0PSP10-NI-0002, Excore QPTR Determination.

(A3) Using Mechanical Drawings Determine the Isolation Boundaries for a Leak on the RHR System Demonstrate the ability to isolate portions of a system using a P&ID.

(A4) Calculate Stay Times based on Dose Rates Demonstrate the ability to determine stay times based on dose rates given in an RWP.

SRO (A5) Calculate SDM with a Misaligned Control Rod and Determine Applicable Technical Specifications Demonstrate the ability perform a SDM and apply appropriate TSs if required.

0PSP10-ZG-0005, Shutdown Margin Verification - Modes 1 and 2.

(A6) Perform a Calorimetric Heat Balance and Evaluate Technical Specifications Demonstrate the ability to perform a Calorimetric Verification and evaluate TSs.

0PEP02-CU-0001, Calorimetric Verification, and 0PSP03-NI-0001, Power Range NI Channel Calibration.

(A7) Using Mechanical Drawings Determine the Isolation Boundaries for a Leak on the RHR System Demonstrate the ability to isolate portions of a system using a P&ID.

(A8) Approve completed Liquid Waste Release Permit. (alternate path actual release did not match the approved release limits)

Demonstrate the ability to review a completed Liquid Waste Release Permit and determine if it was completed correctly. 0PSP07-WL-LDP1, Liquid Effluent Permit.

(A9) Determine Emergency Action Level Demonstrate the ability to correctly determine an Emergency Action Level for a given condition requiring entry into the STPNOC Emergency Action Plan.

Rev 0 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: South Texas Project Date of Examination: 09-28-2015 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 20 NRC Exam Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U)

System/JPM Title Type Safety Code* Function

a. (S1) Manually Load an ESF Bus KA: 062 A4.01 (3.3/3.1) A,D,E,EN,S 6

b. (S2) Cross Connect AFW & Feed 2 SGs from the same AFW Pump E,L,N,S 4S KA: 061 A1.05 (3.6/3.7)

c. (S3) Commence Emergency Boration KA: 004 A4.18 (4.3/4.1) E,N,S 2

d. (S4) Re-Establish Letdown KA: 004 A4.06 (3.6/3.1) A,D,E,S 1

e. (S5) Perform a CCW Valve Operability Test KA: 008 A4.01 (3.3/3.1) N,S 8

f. (S6) Transfer to Hot Leg Recirculation KA: 006 A4.05 (3.9/3.8) D,E,L,P,S 3

g. (S7) Manual Containment Isolation Phase A KA: 103 A3.01 (3.9/4.2) A,E,EN,L,N,S 5

h. (S8) Respond to Radiation Monitor Alarm KA: 073 A4.02 (3.7/3.7) A,D,E,S 7 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. (P1) Locally Operate a SG PORV KA: 035 A1.02 (3.5/3.8) D,E,L 4S

j. (P2) Commence a Liquid Waste Release; then a CW Pump trips requiring A,N,R 9 the release to be secured. KA: 068 A4.02 (3.2/3.1)

k. (P3) Place RWST on Recirculation KA: 006 A4.02 (4.0/3.8) D,E,EN 2 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 Code Criteria for RO/SRO-I/SRO-U (A)lternate Path 4-6 / 4-6 / 2-3 (C)ontrol Room (D)irect from Bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered Safety Features 1 / 1 / 1 (control room system)

(L)ow-Power/Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 Exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator

Rev 0 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: South Texas Project Date of Examination: 09-28-2015 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 20 NRC Exam Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U)

System/JPM Title Type Safety Code* Function

a. (S1) Manually Load an ESF Bus KA: 062 A4.01 (3.3/3.1) A,D,E,EN,S 6

b. (S2) Cross Connect AFW & Feed 2 SGs from the same AFW Pump E,L,N,S 4S KA: 061 A1.05 (3.6/3.7)

c. (S3) Commence Emergency Boration KA: 004 A4.18 (4.3/4.1) E,N,S 2

d. (S4) Re-Establish Letdown KA: 004 A4.06 (3.6/3.1) A,D,E,S 1

f. (S6) Transfer to Hot Leg Recirculation KA: 006 A4.05 (3.9/3.8) D,E,L,P,S 3

g. (S7) Manual Containment Isolation Phase A KA: 103 A3.01 (3.9/4.2) A,E,EN,L,N,S 5

h. (S8) Respond to Radiation Monitor Alarm KA: 073 A4.02 (3.7/3.7) A,D,E,S 7 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. (P1) Locally Operate a SG PORV KA: 035 A1.02 (3.5/3.8) D,E,L 4S

j. (P2) Commence a Liquid Waste Release; then a CW Pump trips requiring A,N,R 9 the release to be secured. KA: 068 A4.02 (3.2/3.1)

k. (P3) Place RWST on Recirculation KA: 006 A4.02 (4.0/3.8) D,E,EN 2 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 Code Criteria for RO/SRO-I/SRO-U (A)lternate Path 4-6 / 4-6 / 2-3 (C)ontrol Room (D)irect from Bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered Safety Features 1 / 1 / 1 (control room system)

(L)ow-Power/Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 Exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator

Rev 0 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: South Texas Project Date of Examination: 09-28-2015 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 20 NRC Exam Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U)

System/JPM Title Type Safety Code* Function

a. (S1) Manually Load an ESF Bus KA: 062 A4.01 (3.3/3.1) A,D,E,EN,S 6

f. (S6) Transfer to Hot Leg Recirculation KA: 006 A4.05 (3.9/3.8) D,E,L,P,S 3

g. (S7) Manual Containment Isolation Phase A KA: 103 A3.01 (3.9/4.2) A,E,EN,L,N,S 5 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

j. (P2) Commence a Liquid Waste Release; then a CW Pump trips requiring A,N,R 9 the release to be secured. KA: 068 A4.02 (3.2/3.1)

k. (P3) Place RWST on Recirculation KA: 006 A4.02 (4.0/3.8) D,E,EN 2 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 Code Criteria for RO/SRO-I/SRO-U (A)lternate Path 4-6 / 4-6 / 2-3 (C)ontrol Room (D)irect from Bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered Safety Features 1 / 1 / 1 (control room system)

(L)ow-Power/Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 Exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator

Rev 0 STP LOT-20 NRC Systems JPM Description Control Room Systems JPMs (S1) Manually Load an ESF Bus - Alternate Path Demonstrate the ability to ensure equipment has properly loaded on to an ESF 4.16KV Bus in accordance with 0POP04-AE-0001, First Response To Loss Of Any Or All 13.8 KV Or 4.16 KV Bus.

(S2) Cross Connect AFW & Feed 2 SGs from the same AFW Pump Demonstrate the ability to control AFW flow to multiple SGS from one AFW Pump in accordance with 0POP01-ZA-0018A, Emergency Operating Procedure Generic Guidance.

(S3) Commence Emergency Boration Demonstrate the ability to align boration flow through the alternate boration isolation valve in accordance with 0POP04-CV-0003, Emergency Boration.

(S4) Re-Establish Letdown - Alternate Path Demonstrate the ability to establish normal letdown flow after an SI in accordance with 0POP05-EO-ES11, SI Termination.

(S5) Perform a CCW Valve Operability Test Demonstrate the ability to perform a CCW System Valve Operability Surveillance in accordance with 0PSP03-CC-0008, Component Cooling Water System Train 1B(2B)

Valve Operability Test.

(S6) Transfer to Hot Leg Recirculation Demonstrate the ability to align ECCS Hot Leg Recirculation in accordance with 0POP05-EO-ES14, Transfer to Hot Leg Recirculation.

(S7) Manual Containment Isolation Phase A - Alternate Path Demonstrate the ability to manually isolate containment penetrations that were not isolated properly following an SI in accordance with 0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 1 and 5.

(S8) Respond to Radiation Monitor Alarm - Alternate Path Demonstrate the ability to respond to Radiation Transmitter alarms on the RM-11 Radiation Monitor Panel in accordance with 0POP04-RA-0001, Radiation Monitoring System Alarm Response.

NOTE: The following JPMs will be performed in pairs; S2 & S7 together, S3 & S5 together and S6 & S8 together. JPMs S1 and S4 will be performed by themselves.

Rev 0 STP LOT-20 NRC Systems JPM Description In Plant Systems JPMs (P1) Locally Operate a SG PORV Demonstrate the ability to locally operate a SG PORV in accordance with 0POP05-EO-EC00, Loss of All AC Power, Addendum 6.

(P2) Commence a Liquid Waste Release; then a CW Pump trips requiring the release to be secured. - Alternate Path Demonstrate the ability to perform a rad waste release and terminate the release when needed in accordance with 0POP02-WL-0100, Liquid Waste Release.

(P3) Place RWST on Recirculation Demonstrate the ability to place the Refueling Water Storage Tank on purification recirculation in accordance with 0POP02-FC-0001, Spent Fuel Pool Cooling and Cleanup System.

Rev. 0 Appendix D Scenario Outline Form ES-D-1 Facility: South Texas Project Scenario No.: 3 Op-Test No.: LOT 20 NRC Examiners: Operators:

Initial Conditions:

• Reactor Power is in Mode 2 at 10-8 AMPs and Stable. BOL (IC #217)

Turnover:

• Unit 1 is returning to service after a forced 7 day outage.

• After the Reactor was taken critical, HHSI & LHSI Pumps 1B and ECW Pump 1B were taken out of service to repair an issue with the breakers. Expected return to service is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The crew is to continue raising power per 0POP03-ZG-0004, Reactor Startup, Step 6.32 and be prepared to enter Mode 1 as soon as the breakers are returned to service.

• Circulating Water Pump #14 is removed from service for maintenance.

• SU SGFP #14 is in service. Lineups are being performed on SGFPT #11 so that warmup of the pump can begin. Lineups have not been started yet for SGFPTs #12 and #13.

Event Malf. Event Event No. No. Type* Description 1 RO (R)

NA SRO (R) Withdraw control rods to raise reactor power to 1% - 3%

(0 min) 2 05-12-04 BOP (I) 1 SRO (I, TS) SG 1D Controlling NR level channel fails low. LT-0549 (20 min) 3 04-09-03 RO (C) 1 SRO (C, TS) Over current trip on ECW Pump 1C (30 min) 4 08-12-04 BOP (C) 1 SRO (C, TS) Over current trip on SU SGFP #14. When aligning AFW, AFW Pump (40 min) #12 fails to start.

5 50-HV-01 1 ALL (M) PZR PORV RC-PSV-655A fails open. Manual closure attempt is (50 min) unsuccessful. Manual block valve will not close. (Requires a Rx trip if not already)

SBLOCA due to PORV (Critical Task) 6 01-12-04B 1 ALL (C) Train B of Phase A fails to auto actuate with CV-MOV-0023 failed (60 min) open 7 10-09-01 During SBLOCA, a lockout on 13.8KV STBY Bus 1F causes 1 ALL (C) Sequencer Mode 3 on Train A. ECW Pump 1A fails to auto start.

(N/A)

(Critical Task)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specification Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Malfunctions after EOP entry (1-2) 2

2. Abnormal events (2-4) 3

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 1

5. EOP contingencies requiring substantive actions (0-2) 0

6. Critical tasks (2-3) 2

Rev. 0 STP LOT-20 NRC Scenario #3 Description Initial Conditions: Unit 1 being returned to service after a forced 7 day outage. Reactor power is currently at 10-8 AMPs and stable. After the Reactor was taken critical, HHSI & LHSI Pumps 1B and ECW Pump 1B were taken out of service to repair an issue with the breakers. Expected return to service is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The crew is to continue raising power per 0POP03-ZG-0004, Reactor Startup, Step 6.32 and be prepared to enter Mode 1 as soon as the breakers are returned to service. CW Pump #14 is removed form service for maintenance. SU MFWP #14 is in service.

Lineups are being performed on SGFPT #11 so that warmup of the pump can begin. Lineups have not been started yet for SGFPTs #12 and #13.

Event 1: The crew will take the Reactor from 10-8 AMPs to 3% to 4% power using 0POP04-ZG-0004, Reactor Startup, and 0POP03-ZG-0005, Plant Startup to 100% Power.

Event 2: SG 1D controlling NR channel, LT-0549, will fail low causing the LPFRV for SG 1D to open. The crew will respond using 0POP04-FW-0001, Loss of Steam Generator Level Control. The SRO will address Tech Spec implications.

Event 3: ECW Pump 1C will trip on over current. The crew will respond using.0POP09-AN-02M4, annunciator C-7, ECW PUMP 1C TRIP. The SRO will address Tech Spec implications.

Event 4: SU SGFP #14 will trip on over current. A SGFPT will not be available yet. The crew will respond using 0POP04-FW-0002, Steam Generator Feed Pump Turbine Trip, to put AFW in service. AFW Pump #12 will not start. The crew will have to cross connect to feed SG 1B. The SRO will address Tech Spec implications.

Event 5: PZR PORV RC-PSV-0655A fails open. The valve will not manually. When operators try to close the block valve, RC-MOV-0001, the block valve will not close. This creates a SBLOCA on PZR and a Reactor Trip and Safety Injection are required. The crew will respond using 0POP05-EO-EO00, Reactor Trip or Safety Injection. RCS pressure will lower below the RCP trip criteria. (Critical Task)

Event 6: Train B of Phase A will fail to actuate. CV-MOV-0023, normal letdown ICIV, fails to close. This creates a penetration that is not isolated. The crew will use 0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 5 to ensure the penetration is isolated by performing a manual CVI to actuate the Train B valves.

Event 7: During the SBLOCA, there will be a lockout on 13.8 KV Standby Bus 1F. The sequencer will strip Class 1E 4.16 KV Bus E1A and perform a Mode 3 sequence. During the sequencing of Train A loads. ECW Pump 1A will fail to auto start. The crew will have to manually start ECW Pump 1A. (Critical Task)

Rev. 0 STP LOT-20 NRC Scenario #3 Description Termination: The scenario will be terminated after the crew has manually started ECW Pump 1A and 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant, has been properly exercised.

Critical Tasks:

• Trip all RCPs so that CET temperatures do not become superheated when forced circulation in the RCS stops. NOTE: Within 5 minutes of reaching the RCP trip criteria.

• Manually start at least one ECW Pump (ECW Pump 1A) prior to the associated EDG tripping.

Source: New

Rev. 0 Appendix D Scenario Outline Form ES-D-1 Facility: South Texas Project Scenario No.: 4 Op-Test No.: LOT 20 NRC Examiners: Operators:

Initial Conditions:

• Unit 1 is at 67% power. BOL (IC #218)

Turnover:

• Unit 1 is reducing power to 60% due to an offsite electrical grid disturbance.

• The Unit is at step 5.15 of 0POP03-ZG-0006, Plant Shutdown from 100% to Hot Standby.

• The Crew is to continue the power reduction at 40%/hour.

• At 65% power the crew will remove SGFPT #13 from service and idle the pump at 3300 rpm.

• CW Pump #13 is removed from service for maintenance.

Event Malf. Event Event No. No. Type* Description 1

(0 min) N/A ALL (R) Continue to lower reactor power to 60%

2 (10 min) N/A BOP (N) Remove SGFPT #13 form service and idle at 3300 rpm 3 06-16-02 BOP (I)

(20 min) 0 SRO (I, TS) Turbine Impulse Pressure, PT-0505, fails low 4 05-09-01 BOP (C)

(25 min) 1.0 SRO (C) Gland Steam Pressure Regulator fails open 5 02-26-02 RO (I)

(35 min) 1 SRO (I, TS) Loop 1B Cold Leg RTD T-0420B fails high 6 50-SA-11 (40 min) 0.5 ALL (M) SG 1B Steamline Break upstream of the MSIV 7 05-07-02 (N/A) 1 BOP (C) SG 1B MSIV fails to auto close (Critical Task) 8 A6_A1_

(N/A) S77_4 BOP (C) AFW Pump #12 will not stop from the control room switch (Critical 1 Task)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specification Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Malfunctions after EOP entry (1-2) 2 2 Abnormal events (2-4) 3

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 1

5. EOP contingencies requiring substantive actions (0-2) 0

6. Critical tasks (2-3) 2

Rev. 0 STP LOT-20 NRC Scenario #4BU Description Initial Conditions: During the previous shift Unit 1 started reducing power due to an offsite electrical grid disturbance. Currently the Unit is at 67% power and on step 5.15 of 0POP03-ZG-0006, Plant Shutdown from 100% to Hot Standby. The Crew is to continue to lower power at 40%/hour and stabilize at 60%. At 65% the crew will remove SGFPT #13 and idle the pump at 3300 rpm. CW Pump #13 is removed from service for maintenance.

Event 1: The crew is at step 5.15 of 0POP03-ZG-0006, Plant Shutdown from 100% to Hot Standby, and will continue the power reduction to 60%.

Event 2: At 65% power the crew will remove SGFPT #13 from service and idle the pump at 3300rpm using 0POP02-FW-0002, SGFP Turbine, section 17.

Event 3: Turbine impulse pressure, PT-0505, fails low. The crew will respond using 0POP04-TM-0003, Failure of Turbine Impulse Pressure Transmitter (PT-505/506). The SRO will address Tech Spec implications.

Event 4: The Gland Seal Regulator, PV-6150, fails open causing the gland seal header PSV-6152 to open. The crew will use 0POP04-MS-0001, Excessive Steam Demand, and 0POP02-GS-0001, Turbine Gland Seal Steam System, to bypass the failed regulator.

Event 5: LOOP B Cold Leg RTD T-0420B fails high. The crew will respond using 0POP04-RP-0004, Failure of RCS Loop RTD Protection Channel. The SRO will address Tech Spec implications.

Event 6: SG 1B steamline break upstream of the MSIV. The crew will respond using 0POP05-EO-EO00, Reactor Trip or Safety Injection, and then 0POP05-EO-EO20, Faulted Steam Generator Isolation.

Event 7: SG 1B MSIV will fail to close. The crew will have to manually close SG 1B MSIV using the control board handswitch. (Critical Task)

Event 8: AFW Pump #12 will not stop using the control board handswitch. To complete isolation of the faulted SG the crew will have to manually close valves in the AFW Pump #12 discharge line. (Critical Task)

Rev. 0 STP LOT-20 NRC Scenario #4BU Description Termination: The scenario will be terminated when the crew exits 0POP05-EO-EO20, Faulted Steam Generator Isolation.

Critical tasks:

• Manually actuate main steamline isolation or close MSIVs before a severe (orange-path) challenge develops to either the subcriticality or the integrity CSF or before transition to EC21, whichever happens first.

• Isolate the faulted SG before transition out of EO20.

Source: New

Rev. 0 Appendix D Scenario Outline Form ES-D-1 Facility: South Texas Project Scenario No.: 5 Op-Test No.: LOT 20 NRC Examiners: _____________________ Operators: ______________________

Initial Conditions:

• Unit 1 is at 78% power. BOL (IC #219)

Turnover:

• The crew will continue to raise power to 100%

• CD Pump #13 and SUSGFP #14 are removed from service for maintenance.

• A line of thunderstorms just passed through Markham and are tracking south towards the STP site.

Event Malf. No. Event Event No. Type* Description 1

N/A ALL (R) Power increase.

(0 min) 2 BOP (C)

Multiple CW Pump #14 Traveling Screen high differential level.

(10 min) SRO (C) 3 02-20-01 RO (I) 0 PZR level channel LT-0465 fails low (25 min) SRO (I, TS) 4 05-11-02 BOP (I)

SG 1B controlling steam flow channel FT-0522 fails low (35 min) 0 SRO (I)

EE_E1B1TF 5 ALL (C)

Fault Loss of 480 V LC E1B1 (45 min) 1 SRO (TS) 6 10-06-01 ALL (M) Main Generator Output Breaker trips open and inadvertent FWI.

(60 min) 1 7 06-02-01 BOP (C) Main Turbine fails to auto trip on reactor trip. (Critical Task)

(NA) 1 8

Multiple ALL (C) Loss of Heat Sink and entry into FRH1 (Critical Task)

(NA)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specification Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Malfunctions after EOP entry (1-2) 2

2. Abnormal events (2-4) 4

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 1

5. EOP contingencies requiring substantive actions (0-2) 1

6. Critical tasks (2-3) 2

Rev. 0 STP LOT-20 NRC Scenario #5 Description Initial Conditions: Current reactor power is 78%. The crew is at step 7.51 of 0POP03-ZG-0005, Plant Startup to 100% and hold points have been satisfied. CD Pump #13 and SU SGFP #14 are removed from service for maintenance. A line of thunderstorms are tracking from the north toward the site.

Event 1: The crew is to re-commence raising power per step 7.51 of 0POP03-ZG-0005, Plant Startup to 100%.

Event 2: CW Pump #14 Traveling Screen high differential level. The crew will respond using 0POP04-CW-0001, Loss of Circulating Water Flow. The malfunction simulates trash built up on the traveling screens for CW Pump #14 but the screens will not rotate. CW Pump #14 will have to be secured.

Event 3: PZR level channel LT-0465 fails low. The crew will respond using 0POP04-RP-0002, Loss of Automatic Pressurizer Level Control. The SRO will address Tech Spec implications.

Event 4: SG 1B controlling steam flow channel FT-0522 fails low. The crew will respond using 0POP04-FW-0001, Loss of Steam Generator Level Control. The SRO will address Tech Spec implications.

Event 5: Loss of Class 1E 480 V LC E1B1. The crew will respond using 0POP09-AN-03M3 annunciator E-5, 480V LC E1B1 TRBL. Power can be temporarily restored through the cross-tie breaker using 0POP02-AE-0001, AC Electrical Distribution Breaker Lineup. The SRO will address Tech Spec implications.

Event 6: The Main Generator Output Breaker will open and an inadvertent FWI will cause a reactor trip. The crew will respond using 0POP05-EO-EO00, Reactor Trip or Safety Injection.

Event 7: On the reactor trip the Main Turbine fails to auto trip The Main Turbine must be manually tripped per the immediate action step 2 RNO of 0POP05-EO-EO00, Reactor Trip or Safety Injection. (Critical Task)

Event 8: Loss of Heat Sink and entry into FRH1. When AFW Actuation occurs AFW Pump #14 will trip on over speed, AFW Pump #13 recirc valve will have been left open and AFW Pumps

1. 11 and #12 will trip on over current. After going through 0POP05-EO-EO00, Reactor Trip or Safety Injection, the crew will transition to 0POP05-EO-FRH1, Response to Loss of Secondary Heat Sink. (Critical Task)

Rev. 0 STP LOT-20 NRC Scenario #5 Description Termination: The scenario will terminate after the crew has aligned Auxiliary Feedwater to feed Steam Generators per CIP of 0POP05-EO-FRH1, Response to Loss of Secondary Heat Sink.

Critical Tasks:

• Manually trip the main turbine before a severe ORANGE path challenge develops to either the subcriticality or the integrity CSF or before transition to 0POP05-EO-EC21, Uncontrolled Depressurization of all Steam Generators, whichever happens first.

• Initiate RCS Feed and Bleed so that ECCS injection from at least one SI pump occurs, and the RCS depressurizes sufficiently for intermediate-head injection from a HHSI pump to occur prior to CETs rising to 1200ºF.

Source: New

ES-401 PWR RO Examination Outline FORM ES-401-2 Facility: STP Date of Exam:

RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total

1. 1 3 3 3 3 3 3 18 6 Emergency &

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

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

3. Generic Knowledge and Abilities Categories 1 2 3 4 10 1 2 3 4 7 3 2 2 3 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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery / 1 000008 Pressurizer Vapor Space Accident / 3 Knowledge of the operational implications of the 000009 Small Break LOCA / 3 X following concepts as 3.5 1 they apply to the small break LOCA:

(CFR 41.8 / 41.10 / 45.3)

EK1.02 Use of steam tables RO 3.5/SRO 4.2 000011 Large Break LOCA / 3 000015/17 RCP Malfunctions / 4 X Ability to operate and / or monitor the following 4.0 2 as they apply to the Reactor Coolant Pump Malfunctions (Loss of RC Flow)

(CFR 41.7 / 45.5 / 45.6)

AA1.22 RCP seal failure/malfunction RO 4.0/SRO4.2 000022 Loss of Rx Coolant Makeup / 2 Ability to determine and interpret the following 000025 Loss of RHR System / 4 X as they apply to the Loss of Residual Heat 3.4 3 Removal System:

(CFR: 43.5 / 45.13)

AA2.07 Pump cavitation RO 3.4/SRO 3.7 G 2.4.4 Ability to recognize abnormal indications 000026 Loss of Component Cooling X for systems operating parameters that are entry 3.9 4 Water / 8 level conditions for emergency and abnormal operating procedures.

(CFR: 45.2 / 45.6)

RO 3.9/SRO 4.0 Knowledge of the operational implications of the 000027 Pressurizer Pressure Control X following concepts as they apply to Pressurizer 2.8 5 System Malfunction / 3 Pressure Control Malfunctions:

(CFR 41.8 / 41.10 / 45.3)

AK1.02 Expansion of liquids as temperature increases RO2.8/SRO 3.1

ES-401 3 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 (RO / SRO)

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

1 2 3 1 2 Knowledge of the interrelations between the and 000029 ATWS / 1 X the following an ATWS: 2.9 6 (CFR 41.7 / 45.7)

EK2.06 Breakers, relays, and disconnects RO 2.9*/SRO 3.1*

Knowledge of the reasons for the following 000038 Steam Gen. Tube Rupture / 3 X responses as the apply to the SGTR: 4.4 7 (CFR 41.5 / 41.10 / 45.6 / 45.13)

EK3.02 Prevention of secondary PORV cycling RO 4.4/SRO 4.5 Ability to operate and / or monitor the following 000040 (BW/E05; CE/E05; W/E12) X as they apply to the Steam Line Rupture: 3.9 8 Steam Line Rupture - Excessive Heat Transfer / 4 (CFR 41.7 / 45.5 / 45.6)

AA1.15 T-ave. protection indicators RO 3.9*/SRO 3.8*

Ability to determine and interpret the following 000054 (CE/E06) Loss of Main X as they apply to the Loss of Main Feedwater 4.1 9 Feedwater / 4 (MFW):

(CFR: 43.5 / 45.13)

AA2.03 Conditions and reasons for AFW pump startup RO 4.1/SRO 4.2 000055 Station Blackout / 6 X 2.4.1 Knowledge of EOP entry conditions and 4.6 10 immediate action steps (CFR: 41.10 / 43.5 / 45.13)

RO 4.6 / SRO 4.8 Ability to operate and / or monitor the following 000056 Loss of Off-site Power / 6 X as they apply to 3.6 11 the Loss of Offsite Power:

(CFR 41.7 / 45.5 / 45.6)

AA1.06 Safety injection pump RO 3.6*/SRO 3.6*

Knowledge of the reasons for the following 000057 Loss of Vital AC Inst. Bus / 6 X responses as they apply to 4.1 12 the Loss of Vital AC Instrument Bus:

(CFR 41.5,41.10 / 45.6 / 45.13)

AK3.01 Actions contained in EOP for loss of vital ac electrical instrument bus RO 4.1/SRO 4.4

ES-401 4 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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 Knowledge of the reasons for the following 000058 Loss of DC Power / 6 X responses as they apply to 4.0 13 the Loss of DC Power:

(CFR 41.5,41.10 / 45.6 / 45.1)

AK3.02 Actions contained in EOP for loss of dc power RO 4.0/SRO 4.2 000062 Loss of Nuclear Svc Water / 4 X Ability to determine and interpet the following as 2.9 they apply to the Loss of Nuclear Service Water (SWS):

CFR 43.5 / 45.13) 14 AA2.01 Location of leak in the SWS RO 2.9/SRO3.6 000065 Loss of Instrument Air / 8 2.1.28 Knowledge of the purpose and function of W/E04 LOCA Outside Containment / 3 X major system components and controls. 3.2 15 (CFR: 41.7)

RO 3.2/SRO 3.3 Knowledge of the operational implications of the W/E11 Loss of Emergency Coolant X following concepts as they apply to the (Loss of 16 Recirc. / 4 Emergency Coolant Recirculation)

(CFR: 41.8 / 41.10 / 45.3)

EK1.1 Components, capacity, and function of 3.7 emergency systems.

RO 3.7/SRO 4.0 Knowledge of the interrelations between the BW/E04; W/E05 Inadequate Heat X (Loss of Secondary Heat Sink) and the following: 3.9 17 Transfer - Loss of Secondary Heat Sink / 4 (CFR: 41.7 / 45.7)

EK2.2 Facility*s 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.

RO 3.9/SRO 4.2 Knowledge of the interrelations between 000077 Generator Voltage and Electric X Generator Voltage and Electric Grid Disturbances 3.1 18 Grid Disturbances / 6 and the following:

(CFR: 41.4, 41.5, 41.7, 41.10/ 45.8)

AK 2.0 1 Motors RO 3.1/SRO 3.2 K/A Category Totals: 3 3 3 3 3 3 Group Point Total: 18/6

ES-401 5 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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 000001 Continuous Rod Withdrawal / 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 Knowledge of the reasons for the 000033 Loss of Intermediate Range NI / 7 X 3.6 19 following responses as they apply to the Loss of Intermediate Range Nuclear Instrumentation:

(CFR 41.5,41.10 / 45.6 / 45.13)

AK3.02 Guidance contained in EOP for loss of intermediate range instrumentation.

RO 3.6/SRO 3.9 Ability to operate and / or monitor the 000036 (BW/A08) Fuel Handling Accident / 8 X 3.5 20 following as they apply to the Fuel Handling Incidents:

(CFR 41.7 / 45.5 / 45.6)

AA1.03 Reactor building containment evacuation alarm enable switch.

RO 3.5/SRO 3.9 Ability to operate and / or monitor the 000037 Steam Generator Tube Leak / 3 X 3.8 21 following as they apply to the Steam Generator Tube Leak:

(CFR 41.7 / 45.5 / 45.6)

AA1.06 Main steam line rad monitor meters RO 3.8*/SRO 3.9*

Ability to determine and interpret the 000051 Loss of Condenser Vacuum / 4 X 3.9 22 following as they apply to the Loss of Condenser Vacuum:

(CFR: 43.5 / 45.13)

AA2.02 Conditions requiring reactor and/or turbine trip.

RO 3.9/SRO 4.1 2.1.32 Ability to explain and apply all 000059 Accidental Liquid RadWaste Rel. / 9 X 3.4 23 system limits and precautions.

(CFR: 41.10 / 43.2 / 45.12)

RO 3.4/ SRO 3.8

ES-401 6 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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 Knowledge of the operational 000060 Accidental Gaseous Radwaste Rel. / 9 X 2.5 24 implications of the following concepts as they apply to Accidental Gaseous Radwaste Release:

(CFR 41.8 / 41.10 / 45.3)

AK1.02 Biological effects on humans of the various types of radiation, exposure levels that are acceptable for personnel in a nuclear reactor power plant; the units used for radiation intensity measurements and for radiation exposure levels.

RO 2.5/SRO 3.1*

Knowledge of the interrelations between 000061 ARM System Alarms / 7 X 2.5 25 the Area Radiation Monitoring (ARM)

System Alarms and the following:

(CFR 41.7 / 45.7)

AK2.01 Detectors at each ARM system location.

RO 2.5*/SRO 2.6*

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 X Knowledge of the operational 3.4 26 implications of the following concepts as they apply to the (SI Termination)

(CFR: 41.8 / 41.10, 45.3)

EK1.2 Normal, abnormal and emergency operating procedures associated with (SI Termination).

RO 3.4/SRO 3.9 W/E13 Steam Generator Over-pressure / 4 X Knowledge of the interrelations between 3.0 27 the (Steam Generator Overpressure) and the following:

(CFR: 41.7 / 45.7)

EK2.2 Facility*s 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.

RO 3.0/SRO 3.2 W/E15 Containment Flooding / 5

ES-401 7 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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 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 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 2 1 1 1 Group Point Total: 9/4

ES-401 8 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 Ability to predict and/or monitor 003 Reactor Coolant Pump X changes in parameters (to prevent 2.6 28 exceeding design limits) associated with operating the RCPS controls including:

(CFR: 41.5 / 45.7)

A1.03 RCP motor stator winding temperatures RO 2.6 /SRO 2.6 Knowledge of the effect of a loss or 004 Chemical and Volume X malfunction on the following CVCS 4.4 29 Control components:

(CFR: 41.7 / 45.7)

K6.17 Flow paths for emergency boration RO 4.4/SRO 4.6 Ability to (a) predict the impacts of the 005 Residual Heat Removal X following malfunctions or operations 2.7 30 on the RHRS, and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45.3 / 45.13)

A2.01 Failure modes for pressure, flow, pump motor amps, motor temperature, and tank level instrumentation RO 2.7/SRO 2.9*

Knowledge of the operational 006 Emergency Core Cooling X implications of the following concepts 2.5 31 as they apply to ECCS:

(CFR: 41.5 / 45.7)

K5.11 Basic heat transfer equation RO 2.5/SRO 2.4*

Ability to monitor automatic 007 Pressurizer Relief/Quench X operation of the PRTS, including: 2.7 32 Tank (CFR: 41.7 / 45.5)

A3.01 Components which discharge to the PRT.

RO 2.7*/SRO 2.9

ES-401 9 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 Ability to manually operate and/or 008 Component Cooling Water X monitor in the control room: 2.7 33 (CFR: 41.7 / 45.5)

A4.05 Normal CCW-header total flow rate and the flow rates to the components cooled by the CCWS.

RO 2.7*/ 2.5 Knowledge of bus power supplies to 010 Pressurizer Pressure Control X the following: 3.0 34 (CFR: 41.7)

K2.01 Pressurizer Heaters RO 3.0/SRO 3.4 Knowledge of RPS design feature(s) 012 Reactor Protection X and/or interlock(s) which provide for 3.2 35 the following:

(CFR: 41.7)

K4.06 Automatic or manual enable/disable of RPS trips RO 3.2/ SRO 3.5 Ability to monitor automatic 013 Engineered Safety Features X operation of the ESFAS including: 3.7 36 Actuation (CFR: 41.7/45.5)

A3.01 Input channels and logic RO 3.7*/SRO 3.9 Knowledge of the effect that a loss or 022 Containment Cooling X malfunction of the CCS will have on 3.0 37 the following:

(CFR: 41.7 / 45.6)

K3.02 Containment instrumentation readings.

RO 3.0/SRO 3.3 025 Ice Condenser

ES-401 10 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 Knowledge of CSS design feature(s) 026 Containment Spray X and/or interlock(s) which provide for 4.1 38 the following:

(CFR: 41.7)

K4.08 Automatic swapover to containment sump suction for recirculation phase after LOCA (RWST low-low level alarm)

RO 4.1*/SRO 4.3*

Knowledge of the operational 039 Main and Reheat Steam X implications of the following concepts 2.7 39 as the apply to the MRSS:

(CFR: 41.5 / 45.7)

K5.05 Bases for RCS cooldown limits RO 2.7/SRO 3.1*

Ability to predict and/or monitor 059 Main Feedwater X changes in parameters (to prevent 2.7 40 exceeding design limits) associated with operating the MFW controls including:

(CFR: 41.5 / 45.5)

A1.03 Power level restrictions for operation of MFW pumps and valves RO 2.7*/SRO 2.9*

Ability to (a) predict the impacts of the 061 Auxiliary/Emergency X following malfunctions or operations 3.4 41 Feedwater on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45.3 / 45.13)

A2.07 Air or MOV failure.

RO 3.4/SRO 3.5 2.4.3 Ability to identify post-accident 062 AC Electrical Distribution X instrumentation. 3.7 42 (CFR: 41.6 / 45.4)

RO 3.7/SRO 3.9 063 DC Electrical Distribution X 2.2.39 Knowledge of less than or equal 3.9 43 to one hour Technical Specification action statements for systems.

RO 3.9/SRO 4.5

ES-401 11 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 Knowledge of the effect of a loss or 064 Emergency Diesel Generator X malfunction of the following will have 3.2 44 on the ED/G system:

(CFR: 41.7 / 45.7)

K6.08 Fuel oil storage tanks RO 3.2/ SRO 3.3 Knowledge of the physical connections 073 Process Radiation X and/or cause effect relationships 3.6 45 Monitoring between the PRM system and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.01 Those systems served by PRMs RO 3.6/SRO 3.9 Ability to predict and/or monitor 076 Service Water X changes in parameters (to prevent 2.6 46 exceeding design limits) associated with operating the SWS controls including:

(CFR: 41.5 / 45.5)

A1.02 Reactor and turbine building closed cooling water temperatures RO 2.6*/SRO 2.6*

K3 Knowledge of the effect that a loss 078 Instrument Air X or malfunction of the IAS will have on 3.4 47 the following:

(CFR: 41.7 / 45.6)

K3.02 Systems having pneumatic valves and controls.

RO 3.4/SRO 3.6 Knowledge of containment system 103 Containment X design feature(s) and/or interlock(s) 3.1 48 which provide for the following:

(CFR: 41.7)

K4.06 Containment isolation system.

RO 3.1/SRO 3.7

ES-401 12 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 2.2.42 Ability to recognize indications 008 Component Cooling Water X for system operating parameters 3.4 49 which are entry-level conditions for technical specifications.

(CFR: 43.2 / 43.3 / 45.3)

RO 3.4/ SRO 4.0 Knowledge of the effect that a loss or 026 Containment Spray X malfunction of the CSS will have on 4.2 50 the following:

(CFR: 41.7 / 45.6)

K3.02 Recirculation spray system RO 4.2/SRO 4.3 Knowledge of the physical connections 063 DC Electrical Distribution X and/or cause/effect relationships 2.9 51 between the DC electrical system and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.03 Battery charger and battery RO 2.9/SRO 3.5 Ability to (a) predict the impacts of the 064 Emergency Diesel Generator X following malfunctions or operations 2.7 52 on the ED/G system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45.3 / 45.13)

A2.08 Consequences of opening/closing breaker between buses (VARS, out-of-phase, voltage).

RO 2.7/SRO 3.1 Ability to manually operate and/or 076 Service Water X monitor in the control room: 2.9 53 (CFR: 41.7 / 45.5 to 45.8)

A4.01 SWS pumps RO 2.9/ SRO 2.9

ES-401 13 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 Ability to monitor automatic 078 Instrument Air X operation of the IAS, including: 3.1 54 (CFR: 41.7 / 45.5)

A3.01 Air Pressure.

RO 3.1/SRO 3.2 Knowledge of bus power supplies to 005 Residual Heat Removal X the following: 3.2 55 (CFR: 41.7)

K2.01 RHR pumps RO 3.0/ SRO 3.2 K/A Category Point Totals: 2 2 3 3 2 2 3 3 3 3 2 Group Point Total: 28/

5

ES-401 14 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K1 K K K K K A A A A G K/A Topic(s) IR #

2 3 4 5 6 1 2 3 4 001 Control Rod Drive 002 Reactor Coolant 011 Pressurizer Level Control X Knowledge of bus power supplies to the 3.1 56 following:

(CFR: 41.7)

K2.01 Charging pumps RO 3.1/SRO 3.2 014 Rod Position Indication Knowledge of NIS design feature(s) 015 Nuclear Instrumentation X and/or interlock(s) provide for the 3.7 57 following:

(CFR: 41.7)

K4.07 Permissives RO 3.7/SRO 3.8 016 Non-nuclear Instrumentation 017 In-core Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control Ability to (a) predict the impacts of the 029 Containment Purge X following malfunctions or operations on 2.9 58 the Containment Purge System; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45.3 / 45.13)

A2.01 Maintenance or other activity taking place inside containment.

RO 2.9/SRO 3.6 Ability to monitor automatic operation 033 Spent Fuel Pool Cooling X of the Spent Fuel Pool Cooling System 2.9 59 including:

(CFR: 41.7 / 45.5)

A3.02 Spent fuel leak or rupture RO 2.9/SRO 3.1 034 Fuel Handling Equipment

ES-401 15 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K1 K K K K K A A A A G K/A Topic(s) IR #

2 3 4 5 6 1 2 3 4 035 Steam Generator X Knowledge of the effect of a loss or 2.6 60 malfunction on the following will have on the S/GS:

(CFR: 41.7 / 45.7)

K6.03 S/G level detector RO 2.6/SRO 3.0 041 Steam Dump/Turbine X Ability to predict and/or monitor 3.1 61 Bypass Control changes in parameters (to prevent exceeding design limits) associated with operating the SDS controls including:

(CFR: 41.5 / 45.5)

A1.02 Steam pressure RO 3.1/SRO 3.2 Knowledge of the effect that a loss or 045 Main Turbine Generator X malfunction of the MT/G system will 2.9 62 have on the following:

(CFR: 41.7 / 45.6)

K3.01 Remainder of the plant RO 2.9/SRO 3.2 055 Condenser Air Removal Knowledge of the physical connections 056 Condensate X and/or cause-effect relationships 2.6 63 between the Condensate System and the following systems:

(CFR: 41.2 to 41.9 / 45.7 to 45.8)

K1.03 MFW RO 2.6*/SRO 2.6 068 Liquid Radwaste 071 Waste Gas Disposal 072 Area Radiation Monitoring

ES-401 16 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K1 K K K K K A A A A G K/A Topic(s) IR #

2 3 4 5 6 1 2 3 4 Ability to (a) predict the impacts of the 075 Circulating Water X following malfunctions or operations on 2.5 64 the circulating water system; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45.3 / 45.13)

A2.02 Loss of circulating water pumps RO 2.5 / SRO 2.7 079 Station Air Ability to monitor automatic operation 086 Fire Protection X of the Fire Protection System including: 65 2.9 (CFR: 41.7 / 45.5)

A3.01 Starting mechanisms of fire water pumps RO 2.9/SRO 3.3 K/A Category Point Totals: 1 1 1 1 0 1 1 2 1 1 0 Group Point Total: 10/

3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) FORM ES-401-3 Facility: STP Date of Exam:

Category K/A # Topic RO SRO-Only IR # IR #

2.1.18 Ability to make accurate, clear, and concise logs, 2.1. 3.6 66 records, status boards, and reports.

(CFR: 41.10 / 45.12 / 45.13) 1.

Conduct RO 3.6 SRO 3.8 of Operations 2.1.21 Ability to obtain and verify controlled procedure copy.

2.1. 3.1 67 (CFR: 45.10 / 45.13)

RO 3.1 SRO 3.2 2.1.3 Knowledge of shift turnover practices.

2.1. 3.0 68 (CFR: 41.10 / 45.13)

RO 3.0 SRO 3.4 Subtotal 2.2.13 Knowledge of tagging and clearance procedures.

2.2. 3.6 69 (CFR: 41.10 / 45.13)

RO 3.6 SRO 3.8

2. 2.2.22 Knowledge of limiting conditions for operations and 2.2. 3.4 70 Equipment safety limits.

Control (CFR: 43.2 / 45.2)

RO 3.4 SRO 4.1 Subtotal 2.3.12 Knowledge of radiological safety principles pertaining 2.3. 3.2 71 to licensed operator duties, such as containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning filters, etc.

3.

Radiation Control (CFR: 41.12 / 45.9 / 45.10)

IMPORTANCE RO 3.2 SRO 3.7 2.3.4 Knowledge of radiation exposure limits and 2.3. 2.5 72 contamination control, including permissible levels in excess of those authorized.

(CFR: 43.4 / 45.10)

RO 2.5 SRO 3.1 Subtotal 2.1.18 Ability to make accurate, clear, and concise logs, 2.4. 3.6 73 records, status boards, and reports.

(CFR: 41.10 / 45.12 / 45.13) 4.

Emergency RO 3.6 SRO 3.8 Procedures / 2.4.16 Knowledge of EOP implementation hierarchy and 2.4. 3.5 74 Plan coordination with other support procedures.

(CFR: 41.10 / 43.5 / 45.13)

RO 3.5 SRO 4.4

ES-401 Generic Knowledge and Abilities Outline (Tier 3) FORM ES-401-3 Facility: STP Date of Exam:

Category K/A # Topic RO SRO-Only IR # IR #

2.4.17 Knowledge of EOP terms and definitions.

2.4. 3.9 75 (CFR: 41.10 / 45.13)

IMPORTANCE RO 3.9 SRO 4.3 Subtotal Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As FORM ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 1/1 EK1.02 This was supposed to be a generic K/A, EK 1.02 mistakenly selected. Replace with Generic K/A 2.4.1 2/1 2.1.33 This K/A is not one of the topics for Tiers 1 and 2 Generic K/As. Replace with K/A 2.1.25 3/1 2.1.11 This K/A was moved with the release of Revision 2, Supplement 1 of NUREG 1021. Replace with K/A 2.1.18 3/3 2.3.1 This K/A was moved with the release of Revision 2, Supplement 1 of NUREG 1021. Replace with K/A 2.3.12 3/4 2.4.15 This K/A was moved with the release of Revision 2, Supplement 1 of NUREG 1021. Replace with K/A 2.4.17 1/1 000022 Loss of Rejected K/A as could not come up with a quality question.

Rx Coolant Replaced with 000015/17 RCP Malfunctions / 4, AA1.22 RCP Makeup / 2 Seal failure/malfunction Ability to operate and / or monitor the following as they apply to the Loss of Reactor Coolant Pump Makeup:

AA1.07 Excess letdown containment isolation valve switches and indicators

ES-401 2 FORM ES-401-4 1/1 000057 Loss There are no Knowledge factors listed in NUREG 1122 Rev 2 of Vital AC Inst. with an importance factor of greater than 2.5.

Bus / 6 Replaced with AK3 of same system.

AK2 Knowledge of the interrelations between the Loss of Vital AC Instrument Bus and the following:

(CFR 41.7 / 45.7) 1/1 000077 Generator Replaced with AK2 of same Emergency/Abnormal system to Voltage and even out the distribution of knowledge attributes Electric Grid Disturbances / 6 AK3 Knowledge of the operational implications of the following concepts as they apply to Generator Voltage and Electric Grid Disturbances:

(CFR: 41.4, 41.5, 41.7, 41.10 / 45.8) 000033 Loss 1/1 There are no Knowledge factors listed in NUREG 1122 Rev 2 of Intermediate with an importance factor of greater than 2.5.

Range NI / 7 K2Knowledge of Replaced with AK3 of same system.

the interrelations between the Loss of Intermediate Range Nuclear Instrumentation and the following:

(CFR 41.7 / 45.7)

ES-401 3 FORM ES-401-4 000065 Loss of 1/1 Instrument Air / 8 Resampled to due to excessive number of Instrument air questions on the exam.

Ability to determine and Replaced with 062 Loss of Nuclear Service Water A2.02 interpret the following as they apply to the Loss of Instrument Air:

(CFR: 43.5 /

45.13)

AA2.08 Failure modes of air-operated equipment RO2.9*/SRO 3.3 026 Containment 2/1 Spray There are no Knowledge factors listed in NUREG 1122 Rev 2 with an importance factor of greater than 2.5.

K5 Knowledge of Replaced with a K4 of the same system operational implications of the following concepts as they apply to the CSS:

(CFR: 41.5 / 45.7) 2/1 039 Main There are no Knowledge factors listed in NUREG 1122 Rev 2 and Reheat with an importance factor of greater than 2.5.

Steam Replaced with a K5 of the same system Knowledge of the effect of a loss or malfunction on the following will have on the MRSS:

(CFR: 41.7 / 45.7)

ES-401 4 FORM ES-401-4 2/ 1 008 Component There are no Knowledge factors listed in NUREG 1122 Rev 2 Cooling Water with an importance factor of greater than 2.5.

Knowledge of the Replaced with a K1 of the same system operational implications of the following concepts as they apply to the CCWS:

(CFR: 41.5 / 45.7) 2/1 026 Containment There are no Knowledge factors listed in NUREG 1122 Rev 2 Spray with an importance factor of greater than 2.5.

Knowledge of the effect of a loss or Replaced with a K3 of the same system malfunction of the following will have on the CSS:

(CFR: 41.7 / 45.7) 045 Main Turbine 2/ 2 There are no Knowledge factors listed in NUREG 1122 Rev 2 Generator with an importance factor of greater than 2.5.

Knowledge of bus power supplies to Replaced with a K3 of the same system the following:

(CFR: 41.7) 2/2 056 Condensate There are no Knowledge factors listed in NUREG 1122 Rev 2 Knowledge of with an importance factor of greater than 2.5.

Condensate Replaced with a K1 of the same system System design feature(s) and/or interlock(s) which provide for the following:

(CFR: 41.7) 079 Station Air 2/2 Knowledge of bus There are no Knowledge factors listed in NUREG 1122 Rev 2 with an importance factor of greater than 2.5.

power supplies to the following: Replaced with system 015 Nuclear Instrumentation K2 (CFR: 41.7)

ES-401 5 FORM ES-401-4 2/2 029 Containment There are no Knowledge factors listed in NUREG 1122 Rev 2 Purge with an importance factor of greater than 2.5.

Knowledge of the Replaced with a A2 of the same system operational implication of the following concepts as they apply to the Containment Purge System:

(CFR: 41.5 / 45.7) 3 2.4.22 Knowledge Difficulty writing a valid RO level question of the basis for prioritizing safety functions during abnormal/emerge ncy operations.

(CFR 41.7/43.5/41.10/4 5.12)

ES-401 PWR SRO Examination Outline FORM ES-401-2 Facility: STP Date of Exam: 9/24/2015 RO K/A Category Points SRO-Only Points Tier Group K K K K K K A A A A G A2 G* Total 1 2 3 4 5 6 1 2 3 4

• Total

1. 1 3 3 6 Emergency &

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

Plant 2 1 1 1 3 Systems Tier Totals 5 3 8

3. Generic Knowledge and Abilities 1 2 3 4 1 2 3 4 7 Categories 2 2 1 2 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outlines (i.e., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each K/A category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions. The final RO exam must total 75 points and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher shall be selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

7.* The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.

8. On the following pages, enter the K/A numbers, a brief description of each topic, the topics importance ratings (IRs) for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above; if fuel handling equipment is sampled in other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3, select topics from Section 2 of the K/A catalog, and enter the K/A numbers, descriptions, IRs, and point totals (#)

on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 000007 (BW/E02&E10; CE/E02) Reactor Trip - Stabilization - Recovery / 1 000009 Small Break LOCA / 3 X EA2 Ability to determine or interpret the following as 4.2 they apply to a small break LOCA:

76 (CFR 43.5 / 45.13)

EA2.34 Conditions for throttling or stopping HPI EA2 Ability to determine or interpret the following as 000011 Large Break LOCA / 3 X they apply to a Large Break LOCA: 4.7 (CFR 43.5 / 45.13) 77 EA2.01 Actions to be taken, based on RCS temperature and pressure - saturated and superheated 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 000027 Pressurizer Pressure Control System Malfunction / 3 000029 ATWS / 1 EPE: 029 Anticipated Transient Without Scram 4.2 (ATWS)

(CFR: 41.10 / 43.5 / 45.12) 78 2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc.

000038 Steam Gen. Tube Rupture / 3 X APE: 038 Steam Generator Tube Rupture 4.2 (CFR 55.43.2, 55.41.5, 55.41.7) 79 G2.2.25 Knowledge of the basis in the Technical Specifications for limiting conditions and safety limits 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 APE: 062 Loss of Nuclear Service Water 4.0 (CFR: 41.10 / 43.1 / 45.13) 80 2.4.18 Knowledge of the specific bases for EOPs.

ES-401 3 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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 AA2. Ability to determine and interpret the following 000065 Loss of Instrument Air / 8 X as they apply to the Loss of Instrument Air: 4.1 (CFR: 43.5 / 45.13) 81 AA2.05 When to commence plant shutdown if instrument air pressure is decreasing 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

ES-401 4 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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 000001 Continuous Rod Withdrawal / 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 X APE: 032 Loss of Source Range Nuclear 4.6 83 Instrumentation (CFR: 41.10 / 43.5 / 45.12) 2.1.20 Ability to interpret and execute procedure steps.

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 000069 (W/E14) Loss of CTMT Integrity / 5 000074 (W/E06&E07) Inad. Core Cooling / 4 X 2.4.21 Knowledge of the parameters and 4.6 82 logic used to assess the status of safety functions, such as reactivity control, core cooling and heat removal, reactor coolant system integrity, containment conditions, radioactivity release control, etc (CFR: 41.7 / 43.5 / 45.12)

RO 4.0/SRO 4.6 AA2. Ability to determine and interpret the 000076 High Reactor Coolant Activity / 9 X 85 following as they apply to the High Reactor Coolant Activity:

(CFR: 43.5 / 45.13)

AA2.02 Corrective actions required for high fission product activity in RCS. 3.4 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 X EA2. Ability to determine and interpret the 3.3 84 following as they apply to the (High Containment Radiation)

(CFR: 43.5 / 45.13)

EA2.1 Facility conditions and selection of appropriate procedures during abnormal and emergency operations.

RO 2.9/SRO 3.3 BW/A01 Plant Runback / 1

ES-401 5 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 K K A A G K/A Topic(s) IR #

1 2 3 1 2 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 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 6 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 003 Reactor Coolant Pump 004 Chemical and Volume Control 005 Residual Heat Removal 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 008 Component Cooling Water 010 Pressurizer Pressure Control 010 Pressurizer Pressure Control X 4.1 86 2.2.12 Knowledge of surveillance procedures.

(CFR: 41.10 / 45.13)

RO 3.7/SRO 4.1 012 Reactor Protection 013 Engineered Safety Features X APE: 013 Engineered Safety Features 4.7 87 Actuation Actuation System (ESFAS) 2.1.7 Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation.

(CFR: 41.5 / 43.5 / 45.12 / 45.13)

RO 4.4 SRO 4.7 022 Containment Cooling 025 Ice Condenser 026 Containment Spray 039 Main and Reheat Steam 039 Main and Reheat Steam X 4.5 88 2.2.38 Knowledge of conditions and limitations in the facility license.

(CFR: 41.7 / 41.10 / 43.1 / 45.13)

RO 3.6 / SRO 4.5 059 Main Feedwater 061 Auxiliary/Emergency Feedwater 061 Auxiliary/Emergency X 3.8 89 Feedwater A2 Ability to (a) predict the impacts of the following malfunctions or operations on the AFW; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45.3 / 45.13)

A2.04 pump failure or improper operation.

062 AC Electrical Distribution

ES-401 7 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 1 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 063 DC Electrical Distribution 064 Emergency Diesel Generator 073 Process Radiation Monitoring 076 Service Water X A2 Ability to (a) predict the impacts of the 3.7 90 following malfunctions or operations on the SWS; and (b) based on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

(CFR: 41.5 / 43.5 / 45/3 / 45/13)

A2.01 Loss of SWS 078 Instrument Air 103 Containment K/A Category Point Totals: 3 2 Group Point Total: 28/5

ES-401 8 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 001 Control Rod Drive 002 Reactor Coolant 011 Pressurizer Level Control 014 Rod Position Indication X 014 Rod position Indication 3.9 91 A2 Ability to (a) predict the impacts of the following malfunctions or operations on the RPIS; and (b) based on those on those predictions, use procedures to correct, control, or mitigate the consequences of those malfunctions or operations:

A2.04 Misaligned rod 015 Nuclear Instrumentation 016 Non-nuclear Instrumentation X 016 Non-nuclear Instrumentation 4.6 92 (CFR: 41.7 / 43.5 / 45.12) 2.2.37 Ability to determine operability and/or availability of safety related equipment.

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 034 Fuel Handling Equipment X 3.2 93 A1 Ability to predict and/or monitor changes in parameters (to prevent exceeding design limits) associated with operating the Fuel Handling System controls including:

(CFR: 41.5 / 45.5)

A1.01 Load limits 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

ES-401 9 FORM ES-401-2 ES-401 PWR Examination Outline Form ES-401-2 Plant Systems - Tier 2/Group 2 (RO / SRO)

System # / Name K K K K K K A A A A G K/A Topic(s) IR #

1 2 3 4 5 6 1 2 3 4 079 Station Air 086 Fire Protection K/A Category Point Totals: 1 1 1 Group Point Total: 10/3

ES-401 Generic Knowledge and Abilities Outline (Tier 3) FORM ES-401-3 Facility: Date of Exam:

Category K/A # Topic RO SRO-Only IR # IR #

2.1.36 Knowledge of procedures and limitations involved in core 2.1. alterations. 4.1 94 (CFR: 41.10 / 43.6 / 45.7)

1. 2.1.1 Knowledge of conduct of operations requirements.

Conduct 2.1. (CFR: 41.10 / 45.13) 4.2 95 of Operations 2.1.

2.1.

Subtotal 2.2.18 Knowledge of the process for managing maintenance 2.2. activities during shutdown operations, such as risk assessments, 3.9 96 work prioritization, etc.

(CFR: 41.10 / 43.5 / 45.13))

2. 2.2.6 Knowledge of the process for making changes to Equipment 2.2. procedures. 3.6 97 Control (CFR: 41.10 / 43.3 / 45.13) 2.2.

2.2.

Subtotal 2.3.13 Knowledge of radiological safety procedures pertaining to 2.3. licensed operator duties, such as response to radiation monitor 3.8 98 alarms, containment entry requirements, fuel handling responsibilities, access to locked high-radiation areas, aligning

3. filters, etc.

Radiation (CFR: 41.12 / 43.4 / 45.9 / 45.10)

Control 2.3.

2.3.

Subtotal 2.4.30 Knowledge of events related to system operation/status 2.4. that must be reported to internal organizations or external 4.1 99 agencies, such as the State, the NRC, or the transmission

4. system operator.

Emergency (CFR: 41.10 / 43.5 / 45.11)

Procedures / 2.4.40 Knowledge of SRO responsibilities in emergency plan 2.4. implementation. 4.5 100 Plan (CFR: 41.10 / 43.5 / 45.11) 2.4.

2.4.

Subtotal Tier 3 Point Total 10 7

ES-401 Record of Rejected K/As FORM ES-401-4 Tier / Randomly Reason for Rejection Group Selected K/A 3/4 2.4.41 A question using this K/A could not be written without duplicating an Admin JPM. Replaced with 2.4.44

Rev. 0 ES-301 Administrative Topics Outline Form ES-301-1 Facility: South Texas Project Date of Examination: 09-28-2015 Examination Level: RO SRO Operating Test Number: LOT 20 NRC Exam Administrative Topic Type Describe activity to be performed (see Note) Code*

A1 Perform an RWST Blended Makeup Calculation Conduct of Operations N,R G2.1.25 Ability to interpret reference materials such as graphs, curves, tables, etc. (4.3/4.4)

A2 Verify an Excore QPTR Calculation Conduct of Operations D,P,R G2.1.20 Ability to interpret and execute procedural steps.

(4.6/4.6)

A3 Equipment Control Using Mechanical Drawings Determine the Isolation N,R Boundaries for a Leak on the RHR System G2.2.41 Ability to obtain and interpret station electrical NOTE: A3 and A7 are the and mechanical drawings. (3.5/3.9) same JPM.

A4 Calculate Stay Times based on Dose Rates M,R G2.3.4 Knowledge of radiation exposure limits under Radiation Control normal or emergency conditions. (3.2/3.7)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 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)

Rev. 0 ES-301 Administrative Topics Outline Form ES-301-1 Facility: South Texas Project Date of Examination: 09-28-2015 Examination Level: RO SRO Operating Test Number: LOT 20 NRC Exam Administrative Topic Type Describe activity to be performed (see Note) Code*

A5 Calculate SDM with a Misaligned Control Rod and Conduct of Operations M,R Determine Applicable Technical Specifications.

G2.1.37 Knowledge of procedures, guidelines or limitations associated with Reactivity Management. (4.3/4.69)

A6 Perform a Calorimetric Heat Balance and Evaluate Technical Conduct of Operations N,R Specifications G2.1.23 Ability to perform specific system and integrated plant procedures during all modes of operation. (4.3/4.4)

Equipment Control A7 Using Mechanical Drawings Determine the Isolation N,R Boundaries for a Leak on the RHR System NOTE: A3 and A7 are the G2.2.41 Ability to obtain and interpret station electrical and same JPM. mechanical drawings. (3.5/3.9)

A8 Approve completed Liquid Waste Release Permit. (alternate Radiation Control N,R path actual release did not match the approved release limits)

G2.3.6 Ability to approve release permits. (2.0/3.8)

A9 Determine EAL Emergency Procedures/Plan M,R G2.4.41 Knowledge of the emergency action level thresholds and classifications. (2.9/4.6)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 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)

Rev. 0 STP LOT-20 NRC Admin JPM Description RO (A1) Perform an RWST Blended Makeup Calculation Demonstrate the ability to set the boric acid flow integrator for a blended makeup to the RWST using 0POP02-CV-0001, Makeup to the Reactor Coolant System.

(A2) Verify an Excore QPTR Calculation Demonstrate the ability to perform and/or verify a QPTR. 0PSP10-NI-0002, Excore QPTR Determination.

(A3) Using Mechanical Drawings Determine the Isolation Boundaries for a Leak on the RHR System Demonstrate the ability to isolate portions of a system using a P&ID.

(A4) Calculate Stay Times based on Dose Rates Demonstrate the ability to determine stay times based on dose rates given in an RWP.

SRO (A5) Calculate SDM with a Misaligned Control Rod and Determine Applicable Technical Specifications Demonstrate the ability perform a SDM and apply appropriate TSs if required.

0PSP10-ZG-0005, Shutdown Margin Verification - Modes 1 and 2.

(A6) Perform a Calorimetric Heat Balance and Evaluate Technical Specifications Demonstrate the ability to perform a Calorimetric Verification and evaluate TSs.

0PEP02-CU-0001, Calorimetric Verification, and 0PSP03-NI-0001, Power Range NI Channel Calibration.

(A7) Using Mechanical Drawings Determine the Isolation Boundaries for a Leak on the RHR System Demonstrate the ability to isolate portions of a system using a P&ID.

(A8) Approve completed Liquid Waste Release Permit. (alternate path actual release did not match the approved release limits)

Demonstrate the ability to review a completed Liquid Waste Release Permit and determine if it was completed correctly. 0PSP07-WL-LDP1, Liquid Effluent Permit.

(A9) Determine Emergency Action Level Demonstrate the ability to correctly determine an Emergency Action Level for a given condition requiring entry into the STPNOC Emergency Action Plan.

Rev 0 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: South Texas Project Date of Examination: 09-28-2015 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 20 NRC Exam Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U)

System/JPM Title Type Safety Code* Function

a. (S1) Manually Load an ESF Bus KA: 062 A4.01 (3.3/3.1) A,D,E,EN,S 6

b. (S2) Cross Connect AFW & Feed 2 SGs from the same AFW Pump E,L,N,S 4S KA: 061 A1.05 (3.6/3.7)

c. (S3) Commence Emergency Boration KA: 004 A4.18 (4.3/4.1) E,N,S 2

d. (S4) Re-Establish Letdown KA: 004 A4.06 (3.6/3.1) A,D,E,S 1

e. (S5) Perform a CCW Valve Operability Test KA: 008 A4.01 (3.3/3.1) N,S 8

f. (S6) Transfer to Hot Leg Recirculation KA: 006 A4.05 (3.9/3.8) D,E,L,P,S 3

g. (S7) Manual Containment Isolation Phase A KA: 103 A3.01 (3.9/4.2) A,E,EN,L,N,S 5

h. (S8) Respond to Radiation Monitor Alarm KA: 073 A4.02 (3.7/3.7) A,D,E,S 7 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. (P1) Locally Operate a SG PORV KA: 035 A1.02 (3.5/3.8) D,E,L 4S

j. (P2) Commence a Liquid Waste Release; then a CW Pump trips requiring A,N,R 9 the release to be secured. KA: 068 A4.02 (3.2/3.1)

k. (P3) Place RWST on Recirculation KA: 006 A4.02 (4.0/3.8) D,E,EN 2 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 Code Criteria for RO/SRO-I/SRO-U (A)lternate Path 4-6 / 4-6 / 2-3 (C)ontrol Room (D)irect from Bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered Safety Features 1 / 1 / 1 (control room system)

(L)ow-Power/Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 Exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator

Rev 0 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: South Texas Project Date of Examination: 09-28-2015 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 20 NRC Exam Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U)

System/JPM Title Type Safety Code* Function

a. (S1) Manually Load an ESF Bus KA: 062 A4.01 (3.3/3.1) A,D,E,EN,S 6

b. (S2) Cross Connect AFW & Feed 2 SGs from the same AFW Pump E,L,N,S 4S KA: 061 A1.05 (3.6/3.7)

c. (S3) Commence Emergency Boration KA: 004 A4.18 (4.3/4.1) E,N,S 2

d. (S4) Re-Establish Letdown KA: 004 A4.06 (3.6/3.1) A,D,E,S 1

f. (S6) Transfer to Hot Leg Recirculation KA: 006 A4.05 (3.9/3.8) D,E,L,P,S 3

g. (S7) Manual Containment Isolation Phase A KA: 103 A3.01 (3.9/4.2) A,E,EN,L,N,S 5

h. (S8) Respond to Radiation Monitor Alarm KA: 073 A4.02 (3.7/3.7) A,D,E,S 7 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

i. (P1) Locally Operate a SG PORV KA: 035 A1.02 (3.5/3.8) D,E,L 4S

j. (P2) Commence a Liquid Waste Release; then a CW Pump trips requiring A,N,R 9 the release to be secured. KA: 068 A4.02 (3.2/3.1)

k. (P3) Place RWST on Recirculation KA: 006 A4.02 (4.0/3.8) D,E,EN 2 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 Code Criteria for RO/SRO-I/SRO-U (A)lternate Path 4-6 / 4-6 / 2-3 (C)ontrol Room (D)irect from Bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered Safety Features 1 / 1 / 1 (control room system)

(L)ow-Power/Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 Exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator

Rev 0 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: South Texas Project Date of Examination: 09-28-2015 Exam Level: RO SRO-I SRO-U Operating Test No.: LOT 20 NRC Exam Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U)

System/JPM Title Type Safety Code* Function

a. (S1) Manually Load an ESF Bus KA: 062 A4.01 (3.3/3.1) A,D,E,EN,S 6

f. (S6) Transfer to Hot Leg Recirculation KA: 006 A4.05 (3.9/3.8) D,E,L,P,S 3

g. (S7) Manual Containment Isolation Phase A KA: 103 A3.01 (3.9/4.2) A,E,EN,L,N,S 5 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U)

j. (P2) Commence a Liquid Waste Release; then a CW Pump trips requiring A,N,R 9 the release to be secured. KA: 068 A4.02 (3.2/3.1)

k. (P3) Place RWST on Recirculation KA: 006 A4.02 (4.0/3.8) D,E,EN 2 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 Code Criteria for RO/SRO-I/SRO-U (A)lternate Path 4-6 / 4-6 / 2-3 (C)ontrol Room (D)irect from Bank 9/8/4 (E)mergency or abnormal in-plant 1/1/1 (EN)gineered Safety Features 1 / 1 / 1 (control room system)

(L)ow-Power/Shutdown 1/1/1 (N)ew or (M)odified from bank including 1(A) 2/2/1 (P)revious 2 Exams 3 / 3 / 2 (randomly selected)

(R)CA 1/1/1 (S)imulator

Rev 0 STP LOT-20 NRC Systems JPM Description Control Room Systems JPMs (S1) Manually Load an ESF Bus - Alternate Path Demonstrate the ability to ensure equipment has properly loaded on to an ESF 4.16KV Bus in accordance with 0POP04-AE-0001, First Response To Loss Of Any Or All 13.8 KV Or 4.16 KV Bus.

(S2) Cross Connect AFW & Feed 2 SGs from the same AFW Pump Demonstrate the ability to control AFW flow to multiple SGS from one AFW Pump in accordance with 0POP01-ZA-0018A, Emergency Operating Procedure Generic Guidance.

(S3) Commence Emergency Boration Demonstrate the ability to align boration flow through the alternate boration isolation valve in accordance with 0POP04-CV-0003, Emergency Boration.

(S4) Re-Establish Letdown - Alternate Path Demonstrate the ability to establish normal letdown flow after an SI in accordance with 0POP05-EO-ES11, SI Termination.

(S5) Perform a CCW Valve Operability Test Demonstrate the ability to perform a CCW System Valve Operability Surveillance in accordance with 0PSP03-CC-0008, Component Cooling Water System Train 1B(2B)

Valve Operability Test.

(S6) Transfer to Hot Leg Recirculation Demonstrate the ability to align ECCS Hot Leg Recirculation in accordance with 0POP05-EO-ES14, Transfer to Hot Leg Recirculation.

(S7) Manual Containment Isolation Phase A - Alternate Path Demonstrate the ability to manually isolate containment penetrations that were not isolated properly following an SI in accordance with 0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 1 and 5.

(S8) Respond to Radiation Monitor Alarm - Alternate Path Demonstrate the ability to respond to Radiation Transmitter alarms on the RM-11 Radiation Monitor Panel in accordance with 0POP04-RA-0001, Radiation Monitoring System Alarm Response.

NOTE: The following JPMs will be performed in pairs; S2 & S7 together, S3 & S5 together and S6 & S8 together. JPMs S1 and S4 will be performed by themselves.

Rev 0 STP LOT-20 NRC Systems JPM Description In Plant Systems JPMs (P1) Locally Operate a SG PORV Demonstrate the ability to locally operate a SG PORV in accordance with 0POP05-EO-EC00, Loss of All AC Power, Addendum 6.

(P2) Commence a Liquid Waste Release; then a CW Pump trips requiring the release to be secured. - Alternate Path Demonstrate the ability to perform a rad waste release and terminate the release when needed in accordance with 0POP02-WL-0100, Liquid Waste Release.

(P3) Place RWST on Recirculation Demonstrate the ability to place the Refueling Water Storage Tank on purification recirculation in accordance with 0POP02-FC-0001, Spent Fuel Pool Cooling and Cleanup System.

Rev. 0 Appendix D Scenario Outline Form ES-D-1 Facility: South Texas Project Scenario No.: 3 Op-Test No.: LOT 20 NRC Examiners: Operators:

Initial Conditions:

• Reactor Power is in Mode 2 at 10-8 AMPs and Stable. BOL (IC #217)

Turnover:

• Unit 1 is returning to service after a forced 7 day outage.

• After the Reactor was taken critical, HHSI & LHSI Pumps 1B and ECW Pump 1B were taken out of service to repair an issue with the breakers. Expected return to service is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The crew is to continue raising power per 0POP03-ZG-0004, Reactor Startup, Step 6.32 and be prepared to enter Mode 1 as soon as the breakers are returned to service.

• Circulating Water Pump #14 is removed from service for maintenance.

• SU SGFP #14 is in service. Lineups are being performed on SGFPT #11 so that warmup of the pump can begin. Lineups have not been started yet for SGFPTs #12 and #13.

Event Malf. Event Event No. No. Type* Description 1 RO (R)

NA SRO (R) Withdraw control rods to raise reactor power to 1% - 3%

(0 min) 2 05-12-04 BOP (I) 1 SRO (I, TS) SG 1D Controlling NR level channel fails low. LT-0549 (20 min) 3 04-09-03 RO (C) 1 SRO (C, TS) Over current trip on ECW Pump 1C (30 min) 4 08-12-04 BOP (C) 1 SRO (C, TS) Over current trip on SU SGFP #14. When aligning AFW, AFW Pump (40 min) #12 fails to start.

5 50-HV-01 1 ALL (M) PZR PORV RC-PSV-655A fails open. Manual closure attempt is (50 min) unsuccessful. Manual block valve will not close. (Requires a Rx trip if not already)

SBLOCA due to PORV (Critical Task) 6 01-12-04B 1 ALL (C) Train B of Phase A fails to auto actuate with CV-MOV-0023 failed (60 min) open 7 10-09-01 During SBLOCA, a lockout on 13.8KV STBY Bus 1F causes 1 ALL (C) Sequencer Mode 3 on Train A. ECW Pump 1A fails to auto start.

(N/A)

(Critical Task)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specification Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Malfunctions after EOP entry (1-2) 2

2. Abnormal events (2-4) 3

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 1

5. EOP contingencies requiring substantive actions (0-2) 0

6. Critical tasks (2-3) 2

Rev. 0 STP LOT-20 NRC Scenario #3 Description Initial Conditions: Unit 1 being returned to service after a forced 7 day outage. Reactor power is currently at 10-8 AMPs and stable. After the Reactor was taken critical, HHSI & LHSI Pumps 1B and ECW Pump 1B were taken out of service to repair an issue with the breakers. Expected return to service is 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The crew is to continue raising power per 0POP03-ZG-0004, Reactor Startup, Step 6.32 and be prepared to enter Mode 1 as soon as the breakers are returned to service. CW Pump #14 is removed form service for maintenance. SU MFWP #14 is in service.

Lineups are being performed on SGFPT #11 so that warmup of the pump can begin. Lineups have not been started yet for SGFPTs #12 and #13.

Event 1: The crew will take the Reactor from 10-8 AMPs to 3% to 4% power using 0POP04-ZG-0004, Reactor Startup, and 0POP03-ZG-0005, Plant Startup to 100% Power.

Event 2: SG 1D controlling NR channel, LT-0549, will fail low causing the LPFRV for SG 1D to open. The crew will respond using 0POP04-FW-0001, Loss of Steam Generator Level Control. The SRO will address Tech Spec implications.

Event 3: ECW Pump 1C will trip on over current. The crew will respond using.0POP09-AN-02M4, annunciator C-7, ECW PUMP 1C TRIP. The SRO will address Tech Spec implications.

Event 4: SU SGFP #14 will trip on over current. A SGFPT will not be available yet. The crew will respond using 0POP04-FW-0002, Steam Generator Feed Pump Turbine Trip, to put AFW in service. AFW Pump #12 will not start. The crew will have to cross connect to feed SG 1B. The SRO will address Tech Spec implications.

Event 5: PZR PORV RC-PSV-0655A fails open. The valve will not manually. When operators try to close the block valve, RC-MOV-0001, the block valve will not close. This creates a SBLOCA on PZR and a Reactor Trip and Safety Injection are required. The crew will respond using 0POP05-EO-EO00, Reactor Trip or Safety Injection. RCS pressure will lower below the RCP trip criteria. (Critical Task)

Event 6: Train B of Phase A will fail to actuate. CV-MOV-0023, normal letdown ICIV, fails to close. This creates a penetration that is not isolated. The crew will use 0POP05-EO-EO00, Reactor Trip or Safety Injection, Addendum 5 to ensure the penetration is isolated by performing a manual CVI to actuate the Train B valves.

Event 7: During the SBLOCA, there will be a lockout on 13.8 KV Standby Bus 1F. The sequencer will strip Class 1E 4.16 KV Bus E1A and perform a Mode 3 sequence. During the sequencing of Train A loads. ECW Pump 1A will fail to auto start. The crew will have to manually start ECW Pump 1A. (Critical Task)

Rev. 0 STP LOT-20 NRC Scenario #3 Description Termination: The scenario will be terminated after the crew has manually started ECW Pump 1A and 0POP05-EO-EO10, Loss of Reactor or Secondary Coolant, has been properly exercised.

Critical Tasks:

• Trip all RCPs so that CET temperatures do not become superheated when forced circulation in the RCS stops. NOTE: Within 5 minutes of reaching the RCP trip criteria.

• Manually start at least one ECW Pump (ECW Pump 1A) prior to the associated EDG tripping.

Source: New

Rev. 0 Appendix D Scenario Outline Form ES-D-1 Facility: South Texas Project Scenario No.: 4 Op-Test No.: LOT 20 NRC Examiners: Operators:

Initial Conditions:

• Unit 1 is at 67% power. BOL (IC #218)

Turnover:

• Unit 1 is reducing power to 60% due to an offsite electrical grid disturbance.

• The Unit is at step 5.15 of 0POP03-ZG-0006, Plant Shutdown from 100% to Hot Standby.

• The Crew is to continue the power reduction at 40%/hour.

• At 65% power the crew will remove SGFPT #13 from service and idle the pump at 3300 rpm.

• CW Pump #13 is removed from service for maintenance.

Event Malf. Event Event No. No. Type* Description 1

(0 min) N/A ALL (R) Continue to lower reactor power to 60%

2 (10 min) N/A BOP (N) Remove SGFPT #13 form service and idle at 3300 rpm 3 06-16-02 BOP (I)

(20 min) 0 SRO (I, TS) Turbine Impulse Pressure, PT-0505, fails low 4 05-09-01 BOP (C)

(25 min) 1.0 SRO (C) Gland Steam Pressure Regulator fails open 5 02-26-02 RO (I)

(35 min) 1 SRO (I, TS) Loop 1B Cold Leg RTD T-0420B fails high 6 50-SA-11 (40 min) 0.5 ALL (M) SG 1B Steamline Break upstream of the MSIV 7 05-07-02 (N/A) 1 BOP (C) SG 1B MSIV fails to auto close (Critical Task) 8 A6_A1_

(N/A) S77_4 BOP (C) AFW Pump #12 will not stop from the control room switch (Critical 1 Task)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specification Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Malfunctions after EOP entry (1-2) 2 2 Abnormal events (2-4) 3

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 1

5. EOP contingencies requiring substantive actions (0-2) 0

6. Critical tasks (2-3) 2

Rev. 0 STP LOT-20 NRC Scenario #4BU Description Initial Conditions: During the previous shift Unit 1 started reducing power due to an offsite electrical grid disturbance. Currently the Unit is at 67% power and on step 5.15 of 0POP03-ZG-0006, Plant Shutdown from 100% to Hot Standby. The Crew is to continue to lower power at 40%/hour and stabilize at 60%. At 65% the crew will remove SGFPT #13 and idle the pump at 3300 rpm. CW Pump #13 is removed from service for maintenance.

Event 1: The crew is at step 5.15 of 0POP03-ZG-0006, Plant Shutdown from 100% to Hot Standby, and will continue the power reduction to 60%.

Event 2: At 65% power the crew will remove SGFPT #13 from service and idle the pump at 3300rpm using 0POP02-FW-0002, SGFP Turbine, section 17.

Event 3: Turbine impulse pressure, PT-0505, fails low. The crew will respond using 0POP04-TM-0003, Failure of Turbine Impulse Pressure Transmitter (PT-505/506). The SRO will address Tech Spec implications.

Event 4: The Gland Seal Regulator, PV-6150, fails open causing the gland seal header PSV-6152 to open. The crew will use 0POP04-MS-0001, Excessive Steam Demand, and 0POP02-GS-0001, Turbine Gland Seal Steam System, to bypass the failed regulator.

Event 5: LOOP B Cold Leg RTD T-0420B fails high. The crew will respond using 0POP04-RP-0004, Failure of RCS Loop RTD Protection Channel. The SRO will address Tech Spec implications.

Event 6: SG 1B steamline break upstream of the MSIV. The crew will respond using 0POP05-EO-EO00, Reactor Trip or Safety Injection, and then 0POP05-EO-EO20, Faulted Steam Generator Isolation.

Event 7: SG 1B MSIV will fail to close. The crew will have to manually close SG 1B MSIV using the control board handswitch. (Critical Task)

Event 8: AFW Pump #12 will not stop using the control board handswitch. To complete isolation of the faulted SG the crew will have to manually close valves in the AFW Pump #12 discharge line. (Critical Task)

Rev. 0 STP LOT-20 NRC Scenario #4BU Description Termination: The scenario will be terminated when the crew exits 0POP05-EO-EO20, Faulted Steam Generator Isolation.

Critical tasks:

• Manually actuate main steamline isolation or close MSIVs before a severe (orange-path) challenge develops to either the subcriticality or the integrity CSF or before transition to EC21, whichever happens first.

• Isolate the faulted SG before transition out of EO20.

Source: New

Rev. 0 Appendix D Scenario Outline Form ES-D-1 Facility: South Texas Project Scenario No.: 5 Op-Test No.: LOT 20 NRC Examiners: _____________________ Operators: ______________________

Initial Conditions:

• Unit 1 is at 78% power. BOL (IC #219)

Turnover:

• The crew will continue to raise power to 100%

• CD Pump #13 and SUSGFP #14 are removed from service for maintenance.

• A line of thunderstorms just passed through Markham and are tracking south towards the STP site.

Event Malf. No. Event Event No. Type* Description 1

N/A ALL (R) Power increase.

(0 min) 2 BOP (C)

Multiple CW Pump #14 Traveling Screen high differential level.

(10 min) SRO (C) 3 02-20-01 RO (I) 0 PZR level channel LT-0465 fails low (25 min) SRO (I, TS) 4 05-11-02 BOP (I)

SG 1B controlling steam flow channel FT-0522 fails low (35 min) 0 SRO (I)

EE_E1B1TF 5 ALL (C)

Fault Loss of 480 V LC E1B1 (45 min) 1 SRO (TS) 6 10-06-01 ALL (M) Main Generator Output Breaker trips open and inadvertent FWI.

(60 min) 1 7 06-02-01 BOP (C) Main Turbine fails to auto trip on reactor trip. (Critical Task)

(NA) 1 8

Multiple ALL (C) Loss of Heat Sink and entry into FRH1 (Critical Task)

(NA)

• (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor, (TS) Technical Specification Target Quantitative Attributes (Per Scenario; See Section D.5.d) Actual Attributes

1. Malfunctions after EOP entry (1-2) 2

2. Abnormal events (2-4) 4

3. Major transients (1-2) 1

4. EOPs entered/requiring substantive actions (1-2) 1

5. EOP contingencies requiring substantive actions (0-2) 1

6. Critical tasks (2-3) 2

Rev. 0 STP LOT-20 NRC Scenario #5 Description Initial Conditions: Current reactor power is 78%. The crew is at step 7.51 of 0POP03-ZG-0005, Plant Startup to 100% and hold points have been satisfied. CD Pump #13 and SU SGFP #14 are removed from service for maintenance. A line of thunderstorms are tracking from the north toward the site.

Event 1: The crew is to re-commence raising power per step 7.51 of 0POP03-ZG-0005, Plant Startup to 100%.

Event 2: CW Pump #14 Traveling Screen high differential level. The crew will respond using 0POP04-CW-0001, Loss of Circulating Water Flow. The malfunction simulates trash built up on the traveling screens for CW Pump #14 but the screens will not rotate. CW Pump #14 will have to be secured.

Event 3: PZR level channel LT-0465 fails low. The crew will respond using 0POP04-RP-0002, Loss of Automatic Pressurizer Level Control. The SRO will address Tech Spec implications.

Event 4: SG 1B controlling steam flow channel FT-0522 fails low. The crew will respond using 0POP04-FW-0001, Loss of Steam Generator Level Control. The SRO will address Tech Spec implications.

Event 5: Loss of Class 1E 480 V LC E1B1. The crew will respond using 0POP09-AN-03M3 annunciator E-5, 480V LC E1B1 TRBL. Power can be temporarily restored through the cross-tie breaker using 0POP02-AE-0001, AC Electrical Distribution Breaker Lineup. The SRO will address Tech Spec implications.

Event 6: The Main Generator Output Breaker will open and an inadvertent FWI will cause a reactor trip. The crew will respond using 0POP05-EO-EO00, Reactor Trip or Safety Injection.

Event 7: On the reactor trip the Main Turbine fails to auto trip The Main Turbine must be manually tripped per the immediate action step 2 RNO of 0POP05-EO-EO00, Reactor Trip or Safety Injection. (Critical Task)

Event 8: Loss of Heat Sink and entry into FRH1. When AFW Actuation occurs AFW Pump #14 will trip on over speed, AFW Pump #13 recirc valve will have been left open and AFW Pumps

1. 11 and #12 will trip on over current. After going through 0POP05-EO-EO00, Reactor Trip or Safety Injection, the crew will transition to 0POP05-EO-FRH1, Response to Loss of Secondary Heat Sink. (Critical Task)

Rev. 0 STP LOT-20 NRC Scenario #5 Description Termination: The scenario will terminate after the crew has aligned Auxiliary Feedwater to feed Steam Generators per CIP of 0POP05-EO-FRH1, Response to Loss of Secondary Heat Sink.

Critical Tasks:

• Manually trip the main turbine before a severe ORANGE path challenge develops to either the subcriticality or the integrity CSF or before transition to 0POP05-EO-EC21, Uncontrolled Depressurization of all Steam Generators, whichever happens first.

• Initiate RCS Feed and Bleed so that ECCS injection from at least one SI pump occurs, and the RCS depressurizes sufficiently for intermediate-head injection from a HHSI pump to occur prior to CETs rising to 1200ºF.

Source: New